Of Uranium Hexafluoride

IAEA-TECDOC-608

Interim guidance on the safe transport of uranium hexafluoride

INTERNATIONAL ATOMIC ENERGY AGENCY The IAEA doe t normallsno y maintain stock f reportso thin si s series. However, microfiche copies of these reports can be obtained from

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Orders shoul accompaniee db prepaymeny db f Austriao t n Schillings 100, for e forcheque a th f m th IAEf m o n i o n i r eAo microfiche service coupons which may be ordered separately from the INIS Clearinghouse. INTERIM GUIDANCE ON THE SAFE TRANSPORT OF URANIUM HEXAFLUORIDE IAEA, VIENNA, 1991 IAEA-TECDOC-608 ISSN 1011-4289

Printed by the IAEA in Austria June 1991 FOREWORD

Sinc earle th e y 1940s, million f tonneso uraniuf o s m hexafluoride

(UFfi) have been transported throughout the world. During this time there has bee o significann t transport accident involvin whic, gUF s resulte hha d in serious injury or the loss of life from either the radiological or the chemical. naturF U f eo o Despite this safety record, recent events have caused the packaging and transporrt e re-evaluaterequirementb o t F U r y expertdb sfo fors UadvisinF te o bth ge re-ev< International Atomic Energy Agency (IAEA).

In 1984 a ship, the Mont-Louis, carrying 30 large packages of UF, Norte th sun hn i kSea .packagee th Althoug f o sl werhal e recovered wito hn release of contents — and therefore no chemical or radiological contamination environmene oth f — tsignifican t attentio transpore draws th nwa o t n f o t UF, by the proximity of this incident to large population centres and important commercial sea-lanes.

In 1986, at a production plant in Oklahoma, USA, a cylinder containing unauthorizen a , rupture o UF t e du d d heatin n attempa n i gremovo t e excess contents e consequen Th phase . th en i changt , expansioUF ee froth f mno solid to liquid overpressurized the packaging, which ruptured releasing large quantities of liquid and gaseous UF into the plant area resulting in the e persondeaton f o h . This deate th chemicale s cause hth wa t no y db d ,an radiological, hazards of UF,. Although this accident did not occur during transport and the scenario is conceivably too improbable to take account of in transport operations, it illustrates that, should the contents of a large package of depleted, natural or low-enriched UF, be released in a transport o accident involving a fire, the radiological consequences would be small, wherea chemicae th s l consequences coul e significantb d .

In 1985 e IAE,th A issue w editioRegulatione ne th a d Safe f o nth e r fo s Transport of Radioactive Materials, Safety Series No. 6, 1985 Edition, in whics requirei t i h d that:

radioactivr fo ) (a e material having other dangerous propertiese ,th transport regulation dangerour fo s s good eacf o s h country througr ho into whic materiae e transportedb th ho t e regulations i lth d ,an f so the cognizant transport organizations mus e complietb d withd ;an possible th ) e(b formatio productf no s having dangerous propertiey sb the interaction of contents with the atmosphere or with water (e.g., the case of UF, ) must be taken into account, o

e fiftTh h meetinStandine th f o g g Advisory Saf e Grouth e n pTransporo f to Radioactive Material (SAGSTRAM), convened in Vienna, Austria in March 1986, recommended that the IAEA take the lead, on a high priority basis, to assess the adequacy of the regulations for the transport of UF,, considering both the radiologica d chemicalan l hazards pose y thidb s material d prepar,an e appropriate documentation to guide the further development of regulations in this area. In making this recommendation SAGSTRAM recognized that safety provision transpore th r fo sdangerouf to s goods having other than radiological hazard generalle sar historicalld yan y establishe othey db r cognizant international organizations. However s felwa tt ,i tha t guidance froe th m

Agenc n transporyo woul, UF beneficia e df b to dangeroue th o t l s goodo s transport community

In July 1986, a group of consultants was convened by the IAEA to provide initial guidanc n thieo s topicTechnicaa d ,an l Committee meetin s helgn wa i d November 1986 to finalize the development of these recommendations.

IAEA-TECDOC-423, "Recommendations for Providing Protection During the Transport of Uranium Hexafluoride", was published in 1987 and distributed for comments e sixtTh . h meetin SAGSTRAMf go , convene Viennn i d Novemben ai r 1987, reviewed the comments and recommended that the Agency should publish a Safety Series document to provide the necessary guidance which takes account of the comments received orden I .achievo t r e this goa consultantla s meetins gwa convened in April 1988 followed by a Technical Committee meeting in May 1988, whose work was the basis of a new draft text.

e seventTh h meetin SAGSTRAf go M then endorse w drafne e t th dtext , subject to some editorial amendments, whic s thehwa n circulate commentr fo e d th o st Member States involve developments it n i d naturcommentse e th Th . f eo , however, revealed essentiall rathet ylaca bu agreemenf w ko r fe a n to fundamental provision drafe th tn e IAE si text th A d decide,an defeo t d r publication. In October 1990 another consultants meeting was convened by the Agenc resolvo yt outstandine eth g issuesdrafe th s amendee tex twa Th f . o t d according to the consultants' advice. An extract of the Consultants' Report comprising the contentious issues is appended to the Foreword to highlight the problem area and the uncertainties that still exist.

The present document, which supersedes IAEA-TECDOC-423, is the outcome of two Technical Committee Meetings, three Consultants Service Meetings and three rounds of comments by Member States. The eighth meeting of SAGSTRAM convened in Vienna in December 1990 recommended, contrary to earlier recommendations, the publication of the document again as a TECDOC, representing a statement of the work don n thii e s area. SAGSTRAM considered thaprevailine th t g uncertainties, in particular those concerning the release criteria during the projected fire test, preclude publicatio Safeta s na y Guide d tha,an ta Co-ordinated Research Programme unde auspicee Agence th r th f yo s should provid necessare th e y inpu resolvo t remainine eth g problems. Since eth

intention to incorporate the provisions on UFfi in the next major revision (1996IAEe th A f )Regulationo supportine th d san g documents still standse ,th tex n thii t s documen bees tha n split into regulatory, advisor d explanatoryan y material. Any additional information arising from experience gained in the thif o se TECDOus C should the takee nb n into account. Extract from the Report of the Consultants Service Meeting (CSM) on the Development of a Safety Guide on Guidance for Providing Protection during the Transpor Uraniuf to m Hexafluoride (UF ), Vienna Octobe3 ,1- r 1990. r o

. 1 Required Test Pressure structurae th n o K U l e testh td requirementan A CommentUS e th y sb were discussed e latesTh . tproposee drafth f o t d regulations "Guidance th n eo Safe Transpor Uraniuf to m Hexafluoride", dated January 1990, contained two versions of paragraph 217 on the structural test for consideration by the CSM. One version required a minimum test pressure of 2.8 MPa. The second version require a tesd t pressure whic minimua 5 time s 1. i h sf o m the maximum allowable working pressure but not lower than 1.4 MPa. The versio requiremenna MP involvin 8 2. bases e twa th gcylindern o d s currentl wite us hn i ythi s requirement versioe Th . n requirin 5 time1. g s the maximum allowable working pressur bases i e n nationao d d lan international pressure vessel code requirements e loweTh . r 4 limi1. f o t MPa used with this requirement was specified to give assurance for the required resistance to impact damage and to be consistent with plant operation conditions.

The version requiring a minimum of 1.5 times the maximum pressure but not minimu5 s adopteCSMe lowe1. wa a th e a s .ri y mTh MP db tha4 1. n universally accepted code requirement. The 1.4 MPa allows the use of all UF, cylinders currently in use. The ability of cylinders designed to a pressurMP 4 th meeo 1. et e t drop tesd othetan r transportation requirements is documented and presented as Working Paper No. 2 in the y 198Ma 8 Technical Committee Meetin n "Guidancgo Safe th e n Transporeo t of Uranium Hexafluoride", (TC-587.2). This is documented in the Chairman's Repor f thao t t meeting.

above Fo approvaa th r MP e 8 reason2. l e requirementh s s alstwa o removed from para 2.28 on "Transition Arrangements and Approval of Shipments".

2. Allowed Release during the Fire Test and Test Duration

The CSM considered that the fire test specification and duration to be applied to UF, packages should correspond in all respects to the thermal test currently applicable to Type B packages - viz. para 628 of Safety . Serie6 . sNo

Concernin allowable th g e release durin fire th g e M considere testCS e ,th d that a necessary pass criterion would be to demonstrate "no rupture" of the cylinder. The consultants could not be certain, however, whether this could also be considered a sufficient condition.

Consideration was given to placing a specific leakage figure (e.g. an wore base"equivalen, f th o k kg n o d0 4 o ordee figur" t th tA 0 1 rf eo C. Ringot and J. Hamard and A. Biaggio and J. Lopez-Vietri) during one week following the fire test. However, there was insufficient data availabl judgo et relative eth e importanc preventinf eo g rupture/ preventing excessive leakage, given that these phenomene aar interrelated s therefori t I . e suggested that further consideratiof no the need for the magnitude of permitted release criterion be undertaken within the framework of the mentioned Co-ordinated Research Project.

3. Exemption Levels

The CSM adopted an exemption level of 0.1 kg for packages designed to contain UF,. Althoug , itselhUF f e doeexplodet th sno o t e ,du b o buildup of internal pressure caused by the hydraulic expansion or gas durin, formatioUF e firega th f ,no thergreaa s i et ris explosiof ko n of small, bare cylinders. This was documented in a 1966 report by A.J. Mallet, titled "ORGDP Container Test and Development Programme, Fire Test UFg-fillef so wels di lCylinders"g k belo 1 toxie 0. th w e c Th . limit of 10 to 40 kg (based on the work of C. Ringot and J. Hamard and of A. Biaggio and J. Lopez-Vietri), and will permit the shipment of sample tubes containing UF, . These sample tubes are constructed of plastic or other non-pressure containing material d thus,an , cannot explodee Th . sample tubes contain less than 0.06 UF,g 5k . EDITORIAL NOTE

In preparing this material for the press, staff of the International Atomic Energy Agency have mounted paginatedand originalthe manuscripts givenand some attention presentation.to The views expressed do not necessarily reflect those of the governments of the Member States or organizations under whose auspices the manuscripts were produced. The use in this book of particular designations of countries or territories does not imply any judgement publisher,the legalby the IAEA,to the status as of such countries territories,or of their authorities institutionsand delimitation ofthe or theirof boundaries. The mention of specific companies or of their products or brand names does not imply any endorsement recommendationor IAEA. partthe the of on CONTENTS

SECTION I. INTRODUCTION ...... 11

SECTIO. NII RECOMMENDED REQUIREMENT SAFE TH E R TRANSPORSFO F TO URANIUM HEXAFLUORIDE ADDITIONA E THOSO LT TH F EO IAEA REGULATIONS FOR THE SAFE TRANSPORT OF RADIO- ACTIVE MATERIAL, 1985 EDITION (AS AMENDED 1990), SAFETY SERIE ("th6 . eSNo Regulations") ...... 15

Scope (2.01) ...... 5 1 . Definitions (2.02) ...... 15 Design and manufacture (2.03-2.12) ...... 16 Inspectio testind nan g (2.13-2.18) ...... 8 1 . Marking (2.19)...... 9 1 . Us packaginf eo g (2.20-2.23) ...... 9 1 . Quality assurance and maintenance (2.24) ...... 20 Specific maintenance requirements (2.25) ...... 20 Design approval (2.26-2.27) ...... 1 2 . Transitional arrangements and approval of shipment (2.28-2.29) ...... 21

SECTIO . NADVISORin Y MATERIAL ...... 3 2 .

SECTIO . EXPLANATORNIV Y MATERIAL ...... 5 2 .

APPENDI X: I EXISTING IAEA REGULATION TRANSPORE TH 6 ....R 7 UF 2 SFO . F TO

APPENDIX H: PROPERTIES OF UF6 AND ITS REACTION PRODUCTS ...... 33

APPENDI : POTENTIAXHI L ACCIDENT CONSEQUENCE EMERGENCD SAN Y RESPONSE PLANNIN PREPAREDNESD GAN ACCIDENTR SFO S

INVOLVING THE RELEASE OF UF6 ...... 45

REFERENCES 51

CONTRIBUTOR DRAFTINO ST REVIED GAN W ...... 3 5 . Section I INTRODUCTION

Uranium hexafluoride (UF,. ) is a radioactive material that has D significant non-radiological hazardous properties conformitn I . y with international regulatory practic dangerour fo e s goods transport, these properties are classed as "subsidiary risks", although they predominate in the case transportes depletef i so F naturaU d solia an d . s a dF d lU material below atmospheric pressure. An accidental release of UF would result in an immediate chemical reaction with air moisture. One of the reaction products whic, isHF h constitutes basicall majoe th y r subsidiary ris UF,f o k, when packaged in large cylinders. Small bare cylinders of UF constitute an additional subsidiary risk by the reported explosive rupture in a fire [1].

In addition to its radioactive properties, enriched UFfi is a fissile material capable of initiating an uncontrolled self-sustaining neutron reaction, i.e., a critical system, under certain conditions.

The IAEA Regulations for the Safe Transport of Radioactive Material, 1985 Edition, Safety Series No. 6, [2] (hereinafter referred to as "the Regulations") make recommendations that aimed to provide an adequate level of safety against radiologica d criticalitlan y hazards basie thesTh r .fo ss i e thastringence th t packagf yo e performance requirements, operational procedures and approval and administrative procedures is graded relative to the severit hazarde th r examplef yo Fo . , wher radiologicae th e l hazard posed by the contents of a package is small, sufficient but minimal requirements and procedure e specifieds ar radiologica e th s A . l hazard increases additional requirements and procedures are imposed.

The non-radiological hazards of the contents are not specifically addresse Regulatione th n i d parat sbu 5 therei 10 . n states:

5 10 "For radioactive material having other dangerous propertiesd ,an for transport or storage of radioactive material with other dangerous goods, the relevant transport regulations for dangerous goods of each of the countries throug r intho o whic materiae e transportedb th ho t s i l , regulatione th d cognizane an th f o s t transport organizations, shall apply, in addition to these Regulations. It is also necessary to take into accoun possible th t e formatio productf no s having dangerous

11 properties by interaction of contents with the atmosphere or with water (e.g., the case of UF )."

The United Nations Recommendations on the Transport of Dangerous Goods y documenke e th n thi i ts i s ] respecbasie [3 th r relevan sfo s ta t international and national mode-dependent regulations. It provides guidance on the packaging and transport of a multitude of specified dangerous goods classified into 9 classes. In addition to general provisions, specific recommendations are included for most of these classes on packing, on intermediate bulk containers and on multimodal tank containers, with performance tesd desigan t n standards grade relation i dpotentiae th o nt l hazard.

For radioactive material - known as Class 7 - the UN Recommendations make a general citatio IAEe th A f Regulationsno . With respec subsidiaro t y risks of radioactive material, the information in paragraphs 105, 406 and 407 of the Regulations is effectively quoted by including the following clause: "it is necessary, however, for consignments of radioactive material to comply with transport regulations applicable to other hazardous properties which such material may possess."

For materials with toxic and corrosive properties similar to those of RecommendationN U UF, e ,th s provide guidanc packinn eo d shipmengan n ti packages (maximu maximu, mkg mas 0 ms40 , intermediat volumL) 0 e45 e bulk containers (maximum volume 3000 L) and multimodal tank containers (minimum . volumHoweverL) 0 e45 applicatioe ,th thesf no e requiremente th o st transpor , prove extremele UF b f o o t s y difficult becaus followine th f eo g factors: the unique physical and chemical properties of UF, (see Appendix n); the high chemical toxicity of UF, and its hydrolysis products (see Appendix III); the restrictions on some safety related items (e.g. pressure release valves); and the absence of provisions for cylinders and other receptacles in the UN Recommendations.

Other difficulties arise from the fact that the cylinders used for transportin alse ar productione o , th use gUF n e i d th f o , storage us d ean material and that the fraction of their life cycle in which transport is

12 involve smalls i d . Consideration must als large givee oth b eo nt numbe f o r existing cylinders (estimate betweee b o t d n 60,00 70,000)d 0an .

In vie thesf o w e facts d takinan , g into accoun bees t ha ntha, tUF transported safely by the nuclear industry for many years, it was felt that specific recommendations should be provided for its transport. These recommendations, listed in Section II, are additional to the requirements of the Regulations.

e intenTh thesf to e additional recommendation restrico t s i s t contaminatio provido t d nan e protectio generae th workero o t nt l d publisan c agains chemicae th t l hazard possibly resulting fro severma e accident involving the transport of UF,t>, and in addition against the consequences of explosive rupture of small bare cylinders of UF,.

Following the basic format of the Regulations, the additional recommendation generie performance ar sar forn d i c an m e oriented burdee ,th n of providing protection being imposed upon the package as a whole, that is the cylinder service ,th e equipmenoutee th rd protectivan t e structuret no d ,an only upon the cylinder itself.

It is, therefore, recommended that UF,D packagings and packages should, in additio relevane th o t n t requirement Regulationse th f so ,summara f yo which is given in Appendix I, be designed, manufactured and used to conform at least with the requirements given in Section II. In particular, because of the nonradiological hazards associated with UF,, the use of the package types specifie Regulatione th n i d permissibls a s thir fo es material (e.g., IP-1, IP-2, recommendatione acceptabls th Typi s ) a eA r fa eo s onl sn yi specified herei alse nar o observed. Some advisory materiadesigne th r ,lfo manufacturing, testing and use of UF packagings is summarized in Refs. [4-6].

Agence Th prepares yha d these recommendations witassistance th h f eo Member States and in conformity with the recommendations of the Standing Advisor ySafe Grouth e n Transporo p Radioactivf o t e Material (SAGSTRAM). Their purpose is to give guidance on the safe transport of UF,, and to b assist of other international organizations and Member States in providing adequate and harmonized requirements throughout the world. It should be noted that additional requirements may arise from national regulations, e.g. pressure vessel regulations.

Next page(s) left blank ^ Section n RECOMMENDED REQUIREMENTS FOR THE SAFE TRANSPORT OF URANIUM HEXAFLUORBDE ADDITIONA E THOSO LT TH F EO IAEA REGULATION SAFE TH E R TRANSPORSFO RADIOACTIVF TO E MATERIAL, 1985 EDITION (AS AMENDED 1990), SAFETY SERIES No. 6 ("The Regulations")

2.01 Packages containing more than 0.1 kg for the transport of uranium hexafluoride, shall, in addition to the applicable recommendations of the Regulations, be designed, manufactured, tested and used in accordance wit followine hth g recommendations.

Definitions purpose th r thesf eo Fo 2.0e recommendations2 :

(1) "Certified volume" shall mean the water capacity of the cylinder attoleranca reference th 0.1± s f ea o % C wite 0 temperature2 h ; (2) "Cylinder" shall mean the cylindrical shell with heads, penetrations and permanently attached structural equipment; ) "Heel(3 " shall meanonvolatile nth e residueresiduae th d san l amount

of UFfi remaining in the cylinder after routine operational emptying; (4) "Maximum allowable working pressure" shall mean the maximum gauge pressure actually built up in the cylinder and service equipment subjectes i whe maximue t i nth o t dm allowable working temperature determinatios It . n shall take into accoun effece th t t of impurities on the total gas pressure; ) "Maximu(5 m allowable working temperature" shall meamaximue th n m temperature of the cylinder and service equipment as specified for the plant systems where the cylinder shall be operated; ) "Package(6 " shall meapackagine th n g witspecifies it h d contents presentes a transportr fo d ; ) "Packaging(7 " shall meaassemble cylindere nth th f yo , servicd ean structural equipment;

15 (8) "Service equipment" shall mean the closures of penetrations (valve plugs)d san ; (9) "Structural equipment" shall mean any item either permanently attached, or assembled to the cylinder as presented for transport; (10) "Tare mass" shal lcleanee meamasth e f nth so d cylinder including its service equipment and its permanently attached structural equipment measured at a tolerance of ±0.1%.

Desig Manufacturd nan e

2.03 The packaging shall be designed and manufactured in accordance with the provisions of technical codes acceptable to the Competent Authority.

2.04 For transport the design of the package shall take into account an ambient temperature range of -40°C to 38°C. For components of the packagin gtemperatura e rang -40°f eo 70°o Ct C shal takee lb n into account. cylindee Th 2.0r5 includin servics git e equipment, shal designee lb o t d the imnHmmn allowable working temperature maximua o t d m,an allowable working pressure which corresponds to the total pressure of the specified content maximue th t sa m allowable working temperature.

package Th 2.06e shal designee lb manufactured dan withstano t d e th d stati dynamid can c stresses that occu norman i r l handlind gan transport additionn I . cylindee servics ,th it d eran equipment shall be designed to withstand the structural test as specified in para 2.17. Under eac thesf ho e conditions there shalo leakagn e lb e d theran e shalunacceptablo n e lb e stress levele excesn ,i th f sso permissible for the materials as specified in the technical codes acceptabl Competene th o t e t Authority mose th t t ,severela y stressed part of the packaging.

cylindee Th 2.07 r includin permanentls git y attached structural equipment shal preveno designee t lb s a to s dpermanen t deformation and leakage at an external pressure of 0.15 MPa (gauge pressure).

16 2.08 The package shall be so designed that, if it were subjected to the leak test as specified in para 2.18 no leakage in excess of the specifie tese d th valut r woulfo e d occur. e packagTh 2.09e shal preveno e designet lb s a to s dlos r dispersaso f o l the contents subjecte s whei t ni frea o et d drop flata tes n o t, horizontal and unyielding surface. The package attitude shall be such that it suffers maximum damage. The height of the drop, measured froe lowesth m t e specimepoin th e uppe th f to o rt n surface th f o e target, shall be not less than the distance specified in Table I.

TABLE I. FREE DROP DISTANCES FOR TESTING PACKAGES

Package mass (kg) Free drop distanc) (m e

0 < package mass < 500 1.8 packag. i 0 0 50 e00 mas5 s< 1.2 5 000

2.10 Packages designed to contain more than 0.1 kg of uranium hexafluoride shal e capabllb withstandinf eo e thermath g l tess ta specified in para. 628 of the Regulations without rupture of the cylinder. Compliance shall be demonstrated according to para. 601 of the Regulations.

2.11 Cylinder sprovidee shalb t lno d with pressure-relief valvese Th . numbe penetrationf ro cylindern si s shal minimizede lb .

2.12 After fabricatio d testinnan beford an g e fillin e inside th th g f eo cylinder shal e thoroughllb y cleane greasef o d , oil, scale, slag, d othean r foreign matter usin appropriatn ga e proceduree Th . cylinder interior shall als driede ob .

17 Inspection and Testing

2.13 Every manufactured packaging and its components, either together or separately, shal e subjectelb initiao t d l inspectio d testinnan g prior td reinspectioo an firs e us t d retestinnan g periodically thereafter. These inspection d testssan countra , carrie e n whicb i y t yhma ou d other than the country of origin or ownership, shall be performed as approve Competene th y db t Authorit e countrth f f origiyo o y user no , and they shall be certified in accordance with a Quality Assurance programme acceptable to that Competent Authority. e initiaTh 2.14l inspectio d testinnan g shall consisconformite th f o t y inspectio visuad nan l inspection establishmene ,th certifiee th f to d volume, the structural test, the leak test and functional test of the service equipment. e conformitTh 2.15 y inspection shall demonstrate compliance witdesige th h n specification manufacturine th d an s g programme.

2.16 Reinspection and retesting shall consist of a visual inspection, the structural test leae th , k functionaa tesd an t service l th tes f o te equipment. The interval for reinspection and retesting shall not be longer tha years5 n . Packages containing materia whicd lan h have not been inspected and tested within a 5 year period prior to transport, shal e inspectelb d accordin programma o t g e acceptablo t e the Competent Authority. Once such packages have been emptied they e refilleshalb t lno dexecutioe prio th e fulo th t rl f no reinspectio n programme.

2.17 The structural test for the cylinder shall be a hydraulic test to an internal pressure of at least 1.5 times the maximum allowable working pressure e tesTh .t pressure lowee shalb t rlno thaMPa4 r 1. n .Fo retesting any other equivalent non-destructive examination acceptable to the Competent Authority may be applied.

2.17a The structural test for the valve shall be a pressure test to an internal pressure of at least 2.8 MPa.

2.18 The leak test shall be performed by means of a procedure capable of indicating leak rates fro cylindee servics th mit d eran equipment

18 with a sensitivity of 0.1 Pa L/s. The pressure to be used in this test leasshalt a e tlb 0.689 MPa.

Marking

2.19 A plate made from a non-corroding metal shall be durably attached to the cylinder of every packaging for uranium hexafluoride. The metho attachinf o d plate th g e shal t reduclno e strengte th th f o h cylinder least A followin.e th t g particulars including units sa applicable shall be legibly and durably marked on this plate:

- Approval number - Manufacturer's name - Manufacturer's serial number Owner's name - Model type - Mayïmmn allowable working pressure - Maximum allowable working temperature Certified volume - Permissible filling mass of uranium hexafluoride - Tare mass - Date of initial test and most recent periodic test.

UsPackaginf o e g

2.20 The uranium hexafluoride shall be in solid form, and the internal pressure of the cylinder shall be below atmospheric pressure, when the package is offered for transport.

2.20.1 Excep s provideta 2.20.2n i d totae ,th l mas contentf so s shalt lno exceed a value which would lead to ullage smaller than 5% at 121°C.

3 2.20.2 In applying the requirement of 2.20.1 a density of 3.26 g/cm shall be assume calculatinr fo d ullage th g e provided thapurite th t f o y uranium hexafluorid least a s ti e 99.5%. More restrictive limitations shal appliee lb s appropriatda e wher purite th e uraniuf o y m hexafluoride is less than 99.5%.

2.20.3 The maximum mass of contents of certain cylinders designed for long

term storag higf eo h purity deplete e increaseo b t y ds a ma UF o s d i f

19 provide 5% ullage at a maximum working temperature of 113°C based on a

UF& densitdensü y of 3.33 g/cm and the actual certified volume of the cylinder.

2.20. e calculateTh 4 d filling mas UFf so fi , excep depleter fo t d UFfin ,i the solid stat minimue e th shal f exceet o m lno % specifie61 d d volume cylinde e densit, usinC e g/c1 o th fUF 0 Th 5. 2 ga m. f t yo ra volume of solid depleted UF.. at 20 C shall not exceed 62% of the o certified volume of the cylinder.

2.21 Empty cylinders shal closee lb madd an de lea ksame tighth e o t degree as filled cylinders.

2.22 Empty, uncleaned cylinders shall be radiologically monitored to assure tharadiatioe th t n level withie ar s n specified limits.

2.23 During transpor secura t e base shal providee lb suppora s a d t structure for the package. This support structure may be permanently attached vehicle e packagineitheth th o o t r t ro e r go temporarily attache boto t df them o h . Skids, frameworks, cradler o s other similar devices are acceptable.

Quality Assurance and Maintenance

2.2qualitA 4 y assurance programm programmer eo s shal establishee lb r fo d the design, manufacture, use, servicin maintenancd gan packagef eo s of uranium hexafluoride. The level of quality assurance assigned shall also take into account the chemical hazards of uranium hexafluoride.

Specific Maintenance Requirements

) Packaging(a 2.25 s shal maintainee lb designee th o t d d criterid aan verified by appropriate inspection and/or tests. These shall be carrieaccordancn i t ou d e with prescribed procedures which must cover minimuma s ,a relevanl ,al t test d featuresan s described elsewhere in this document. (b) Cleaning of the cylinders shall be performed by using an appropriate procedure only.

20 repairl Al ) s (c shal performee lb accordancn i d e wit specifiee th h d design and manufacturing programme of the packaging. If this is not possible, the proposed repairs and repair programmes shall e subjecb approvao t Competene th y lb t Authorit advancen i y .

Design Approval

2.26 Excep packager fo t s designe contaio t d n uraniuf leso g sk tham1 n0. hexafluoride, each design of package for uranium hexafluoride shall require unilateral approval froCompetene th m t Authorite th f yo countr origif yo n thadesige th t n meet provisione th s f thesso e recommendations e approva.Th l procedurapprovae th pare b f o ty lema procedur r Typ fo epackageB e design and/o approvae th r l procedurr fo e a package design for fissile material, as appropriate, required by the Regulations.

2.27 Upon approva Competene th l t Authority shall issu approvan ea l certificat d allocatan e n approvaea l number. This approval number shall be of the type described in para 724 of the Regulations with

"UF Type placn 6th "i e f Codeeo , e.g. CDN/XXX/UF packaga - g e design for uranium hexafluoride approved by the competent authority of Canada.

Transitional Arrangements and Approval of Shipment

2.28 Packagings, with their components, already constructed in accordance wit requiremente th h n existina f o s g nationa internationar lo l standard, may be allowed to continue to be used for a transition periot leasa f year2 to d s afte entre th r y into forc f theseo e provisions, provided thee re-testeyar d re-inspectean d accordancn i d e with para. 2.15. After the transition period all such packagings shall require multilateral approval of shipment unless the design has been approve accordancn i d e witprovisione th h f thiso s document. e shipmenTh 2.29 package f to complyint sno g witrequiremente th h 2.20.f so 1 as provide 2.20.2n i dcomplyint no r ,o g with 2.20.3, shall require multilateral approval by the Competent Authority of the country of eacorigif o hd ncountran y throug intr ho o whic consignmene hth o t s ti be transported.

Next page(s) left blank I 2 Section m ADVISORY MATERIAL

A 2.10 No actual fire test is required in order to demonstrate mathematicaa compliancef o e us e l Th .n appropriatmodea d lan e calculatio acceptabls i n s specifieea e th f o paran i d1 .60 Regulations.

A 2.17 The procedure for this test should follow the recommendations of ISO/DIS 4706.2- Refillable Welded Steel Cylinders [7], namely: All cylinders of each batch shall be subjected to pressure test. - It shall be observed that the pressure in the cylinder increases graduall d regularlyan y unti tese th lt pressurs i e reached e cylindeTh . r shal hele lb d long enough under test pressur ascertaio t e n that thero tendencn s i e decreaso t y n i e pressur d thaean t tightnes achieveds i s . recognises i t I A 2.1d9 tha somn i t e cases cylinder e solsar d wite th h contents. Provisions for marking changes of ownership should be preparatioe th mad n i platee th f no .

A 2.20.1 Consideration shoul volume givee th db masd o heelean f t no s s that are present in the cylinder prior to its filling.

A 2.23 In considering the requirements of this section it is recommended [3] that the minimum dynamic loadings, in addition to static loadings withstoode b o ,t , shoul loadinge basee g th db 2 n o df so in the vertical down direction, l g in the vertical up direction, 2 g in the longitudinal direction and l g in the transverse direction, applied through the centre of gravity of the package.

Next page(s) left blank Section IV EXPLANATORY MATERIAL

E 2.02(10) It is important to note that the tare mass is defined for cleaned cylinders procese th n refillinf I so . cylindega actuas rit l initial mas usualls i s y slightly larger, resulting froe th m presence of a certain quantity of heel(s). maximue Th 2.0E m5 allowable working temperatur cylindee th f eo s i r specified for design and plant conditions. The requirement for the package, however, relate ambieno t s t conditions envisioned during routine transport activities.

E 2.06 The requirement in this paragraph is part of all national and international pressure vessel codes purposs ensuro It t . e s i eth e structural adequacy of the cylinder.

e fre Th E 2.0e dro9 p test requirement n thii s s paragrap e similahar o t r those prescribed in the Regulations for testing packages for abilit withstano t y d normal condition f transporto s e heaTh .t resistance test prescribed in para 2.10, however, is similar to the therma Regulationse l th tes n e testi t th r fo sf o ,e whicon s i h demonstrating abilit withstano t y d accident conditionn si transport. Thiunderstandine bases th i s n o d g thae th t requiremen resistancr fo t hydraulio t e c rupture (para 2.17) compensates for the less severe free drop test. If, however, the contents of a package exceed the appropriate limit for a Type A package or constitute fissile material, the normally-applicable requirements for Type B or fissile package design should be met.

E 2.10 Paragraph 2.10 cite sRegulationse paragrapth f o 8 h62 , which specifies the thermal test parameters of 800 C temperature and 30 minutes duration.

25 exemptiog k 1 The0. n level provides assurance againse th t

explosion of small, bare cylinders of UFfi [1]. The 0.1 kg level wels i l belo e toxith w c wore risbase, th f ko kg k n o d0 limi 1 f o t . BiaggiLopez-Vietr. A J f o d oan d HamarRingo. . an J C ] d i[8 dtan [9].

E 2.21 In many cases the filled cylinder can be classified as LSA material based on its specific activity (in terms of Bq/g). The evacuated cylinder, containing only the heels, might require another classification, considering bot concentratioe th h f no radioactive nuclides and the external radiation levels.

26 AppendixI

EXISTING IAEA REGULATIONS FOR THE TRANSPORT OF UF 6

AI.l INTRODUCTION

This Appendix provides a summary of those recommendations in Safety

Seriewhic6 . hsNo relate specificall safe th e o transport y UFf .o t fi

AI.2 REGULATORY REQUIREMENTS

e IAETh A periodically publishe Regulatione th s Safe th e r Transporsfo f o t Radioactive Material (Safet y. SerieThes6) . esNo Regulations serva s ea model for regulations implemented by Member States, and for the regulatory documents promulgate y transport-relatedb d international organizationse Th . latest edition of the Regulations was issued in 1985 and an As Amended version was published in 1990 [2]. The following summarizes these requirements relating to solid unirradiated UF, which lead to six general combinations of material classifications and packaging requirements* as follows:

) 1 Packaged y enrichmentUF,an f ,o emptr ,o y packagings, shall comply with the requirements of excepted packages subject to the constraints of para. 415 of the Regulations, which include:

requiremente Th ) (i othef so r regulation non-radiologicar fo s l hazards must als satisfiee ob d (para. 407);

package (iiTh ) e must retai contents it n s under conditions likely to be encountered in routine transport (para. 419(a));

(iiipackage Th ) e must n internabeaa n ro l surfac markinea g "Radioactive" visibl openinn eo package neet t th gbu dno e— be marked with radioactive labels externally (para. 419(b));

* If UF$ can be classified as LSA-I, the Regulations also would appear to allo unpackages transpore a th wg UF f to d (para. 425(a)); howevere ,du chemicae tth o l reactions which will occur between unpackaged an g dUF waterd an r ,ai such transpor t possibleno s i t .

27 package Th (ive) must satisf generae th y l design requirements (paras 505-514);

(v) The radiation level on the package surface must not exceed 5uSv/h (0.5 mrem/h) (para. 416);

contaminatioe Th (vi) n level excepter fo s d packages muse tb satisfied (para. 408);

uranium-23e Th (vii) 5 enrichmen tgreatee b mus t tno r thaexcep, 1% n t in the cases of items (viii) and (ix) below (para. 560(c));

(viii) If the uranium-235 enrichment is greater than 1% but not greater than 5%, the package must contain not more than 15 g of fissile material, and all its external dimensions must be greater than 10 cm (para. 560(a)); and uranium-23e th f I (ix5) enrichmen greates i t package rth tha, e5% n mus t contaitno nactivitf o mor q TB e ytha 0 (Tabl1 nf o V I e the Regulations) package ,th e mus t contaitno n more g tha 5 1 n of fissil eexternas materialit l al l d dimension,an s muse tb greater (param c tha 0 1 n. 560(a)).

additionn I ) shipmenr (x ,fo emptn a s yta packaging followine ,th g are required (se Regulations)e th e f parao 1 .42 :

well-maintainea n i s i t I ) d (a conditio d securelnan y closed; e leve Th internaf lo ) (b l non-fixed contamination doet sno 2 excee 0 Bq/cbet r 40 d gamm fo aan m a emitterw lo d san 2 toxicity alpha emitters, and 40 Bq/cm for all other alpha emittersd ;an y labelAn s) whic(c havy hma e been displayeo t t i n o d conform with requirements as a filled package are no longer visible.

2) Uranium-235 enrichment not greater than 0.72%

- Classifie non-fissiles a d , LSA-Id ;an - Shall comply with the requirements of IP-1.

28 ) 3 Uranium-235 enrichment greater tha nexceedint 0.72no t %bu g 1.0%

- Classifie fissiles a d , LSA-II; - Regulate non-fissils a d e radioactive material (excepted from packaging requirements for fissile materials); and therefore Shall comply with the requirements of IP-2; and - Shippe packaga s a d e containing non-fissile material.

4) Uranium-235 enrichment greater than 0.72% and maximum contents of package less than 15 g of uranium-235

(a) Enrichment 5% or less

Classified as fissile, LSA-II; - Regulated as non-fissile radioactive material (excepted from packaging requirements for fissile materials); and therefore - Shall comply with the requirements of IP-2; and - Shipped as a package containing non-fissile material.

(b) Enrichment more than 5%

Classifie s fissilda e radioactive material, LSA-I specifif i I c activit t greateyno r tha 0 Bq/g1 n ; - Regulate non-fissils a d e radioactive material (excepted from packaging requirements for fissile materials); and therefore Shall comply with the requirements of either IP-2 (if LSA-II), otherwised Typan ; eA - Shippe packaga s a d e containing non-fissile material.

5) Uranium-235 enrichment greater than 1.0% but not greater than 5.0% maximud an m content packagf so e greate uranium-23f o r g tha 5 1 n 5

Classified as fissile radioactive material, LSA-II; shippee b packagina y n Ma i d - g satisfying IP-2 containmend tan shielding requirements and satisfying criticality safety requirementd an s; Shipped as a package containing fissile material.

29 TABL REQUIREMENTL EAL S IMPOSE 6 TRANSPORUF N DO T PACKAGE IAEY SB A SAFETY SERIE6 . SNo (numbe parenthesen i r s indicate relevant paragraph numbers from Safety ) Serie6 . sNo

Uranium Maximum Material Maximum Fissile Fissile UN Packaging Labelling & Approval Enrichment Contents Classification Radiation Material Packaging Number w Requirements Documentation Require- (f %U-23So ) (g of U-235) Level Classification Requirements Requirements ments

EXCEPTED PACKAGES --SEE TEXT, SECTION I I.I

<• 0.72% (b) LSA-" < 1 10 mSv/h 3 m Non-fissile None 2978 IP-1 (426, 518) (436-453) None

front unshielded

) W if LSA-I or LSA-II >0.72% to 1.0% (b) LSA-n (422) Fissile Fissile 2978 IP-2 (426, 519) (436,453) None Excepted (560) mSv/2 & t a h package > 0.72% 15 g (560 (a)) LSA-I> I" Fissile Fissile 2978 IP-2 if LSA (436-453) None if eurichuieut surfact no f ei Excepted (560) (426,519,560), & 5% under or if enrichment > Type A if not 1 LSA-II, 5% " Exclusive eUs LSA if specific (433). or (524-538) activity < 105 bq/g, otherwise 10mSv/h at not LSA package

surface if under 1.0> o 5.0%t % (b) (f) LSA-II w Fissile Fissile 2977 IP-2 (426, 519); (436-459) Multilateral Excluse Use (434) (559,561,568) and (710) (g) Fissile (559)

> 5.0% (f) LSA-I' I« Fissile Fissile 2977 (IP-2 if LSA (436-459) Multilateral if specific (559,561,568) (426, f i 519) r o , (710) activity (8) not LSA, £ Iff Bq/g. Typ (524eA - otherwise 538) A LS t no r Typo (549eB - 556 or 557-558); and Fissile (559) N numbeU uses i r ) d (a internationall o assist y t hazard identificatio emergencn i n y response.

(b) Controlled by unshielded material radiation level at 3 m (422).

(d) LSA-I cannot be fissile material (131)(a)(iii)). Although the package containing uranium enriched to a maximum % shoul1 f e regulateo b d non-fissila s a d e material packag e radioactivth e e materia s stili l l fissile. Therefor classifies i t i e d LSA-II(e).

(e) The specific activity limit for solid LSA-II is (131(b)(ii)):

4 1CT A2/g

Up to 5% enrichment level (including the A2 value is unlimited.

3 4 3 7 Abov enrichmen% 5 e t 2 valuleveA e 10~s i eth l TBq, thus LSA-II limi : 10~is t x 1CT TBq/ 10~= g TBq/g = 105 Bq/g.

Accordin Tablo t g e AII.l (Appendix II), specific enrichmen% activit5 o 4 t Bq/ 10 p u yr x go t 7 leve6. s i l less. Above this enrichment leve g cannoUF l e classifieb t LSA-IIs a d , unless specific activity remains below 5 Bq/10 g also taking into account daughter product f uraniuso m isotopes.

UFg enriched to levels were the specific activity exceeds 105 Bq/g cannot be classified as LSA-III because the requirement of para.!31(c)(ii) is not fulfilled.

(f) Controlled by package design.

) (g Fissile material shal e packageb l d shippean d n suci d mannea h r that subcriticalit maintaines i y d under normal condition f transporso accidentsn i d an tr demonstratin Fo . g thipackagee th s e require ar se teste b o s t da d specified in paras 619-624, 626-628 and 631-633 or 619-624 and 629 (more limiting combination). ) 6 Uranium-235 enrichment greater than 5.0 maximud %an m contentf so package greater than 15 g of uranium-235

(a) Specific activity not greater than 10 Bq/g (see Table AII.l)

- Classifie fissils a d e radioactive material, LSA-II; - Shall comply with IP-2 containment and shielding requirements and satisfying criticality safety requirements; and - Shippe packaga s a d e containing fissile material.

Specifi) (b c activity greater tha 0 Bq/1 n g (see Table AII.l)

- Classified as fissile radioactive material; - Shall comply with Type A containment and shielding requirement activitf i s y doe t exceesno d 0.001 TBq, otherwise shippe packaga n i d e satisfying Typ containmenB e d an t shielding requirements, and in both cases satisfying criticality safety requirementsd ;an - Shippe packaga s a d e containing fissile material.

Key requirements imposed for each of the last five of these six material classification/packaging combination summarizee ar s Tabln i d e AI.l. Shipment

of package ds excepte a UF d package t generallno s i s y practical becausf o e i f the small packagr quantitiepe F eU f involvedso . Requirements imposey b d the Regulations for the shipment of empty packagings were outlined above.

Protectio valvee th UFf f o sno f i package vera s yi s important issue. The extent to which the Regulations requires protection (inherently or directly) depends upon the material classification/package which applies.

UFe Ifth if packag wilt Typa (i l s eB i epackaga als e ob e containing fissile material), the valve must be protected for the accident condition tests (paras 627-629). Similarly other fo , r fissile material shipments (wher package th e e may be either IP-2 or Type A), the mechanical and thermal tests (paras 627 and 628) require assuro t d e preventio criticalitf o n y (para. 564 alsy )ma o inherently require valve protection. An IP-2 package will inherently have the valve protected from normal transport condition drops (para. 622), whereas an IP-1 or excepted package will have the valve protected from accelerations and vibrations which may arise during transport (para. 511).

32 Appendixn

PROPERTIES OF UF6 AND ITS REACTION PRODUCTS

INTRODUCTION

A.II.l. This Appendix give shora s t summarrelevane th f o y t propertief o s the materials involved. Hazards associated with these materials, both from the radiologica d chemicalan l poin viewf o t e discusse,ar wells a d brieA . f description of possible consequences of accidents is given.

PROPERTIE URANIUF SO M HEXAFLUORIDE

A.II.2. Uranium hexafluoride, UF,, is a white solid at room temperature. o It is the only compound of uranium which is a gas at low temperature. At atmospheric pressure (0.101 MPa, 760 mmHg) the partial vapour pressure above the solid at 56.4 C equals atmospheric pressure. It liquefies at 64.0 C at a pressure of 0.151 MPa (1137 mmHg).

Physical properties

A.II.3. The most important physical properties of UF, are given below [10,11]:

Hea sublimatiof o t n (64°C) 137,500 J/kg Heat of fusion (64°C) 54,167 J/kg Heat of vaporization (64°C) 83,333 J/kg Critical pressure 4.61 MPa Critical temperature 230.2°C Triple point 64.0°C

Vapour pressure - temperature relations: r temperatureFo s 64°_t < 120°CCi :

lg1QP (MPa 3.1196)= 41126.288/(- 221.963)t+ r fo d ,an

0°C i t ^ 64°C:

lg1QP (MPa) = 2.50853 + 0.0075377 t - 942.76/(t + 183.416)

33 The diagrams for UF phases, densities and heat capacities of UF, D D (liquid, soli vapour)d an d , UFfi sublimatio vaporizatiod nan n head tan thermal conductivit vapou, UF givee f yo rar Figuren i n s All.1-9.

Usuall F yU contain s small vapou e quantitieTh r. HF pressur f o s e inside a UF packaging is therefore somewhat higher. The phase diagram of mixtureF U-H F gives i s n [10]i n .

Practical grade UF is defined in [12]. This specification gives the limits to impurities and the upper values of vapour pressure designated in Fig. AII.I a "ASTM LIMIT".

100000 —— 1 —— ————— I ————— ,

-h-

*^ ^*~ ^^ *** ^ .IQ UD ^ ^ 10000 ^ 7^ s*

~~100 / /— --f/ / afarenc9 e11~~

~~m T(AVdT , ) —— ~~C3 0.0439 deg-tetm. - W- dp ™ iH, 10 1 L ( 1 50 100 ISO 200 240 TEMPERATURQ E("~~

~~FIG. AII.1. Phase diagram of UF6 [10].~~

~~34 ë »oM~~

~~TemperatureC ,~~

~~FIG. AII.2. Densit f soli yliquio d 6 [10]dan dUF .~~

~~35 1400~~

~~1360~~

~~1320~~

~~1280~~

~~I2-JO~~

~~K p~~

~~OC 1200~~

~~P^ ij -H c Q 1160~~

~~1120~~

~~1080~~

~~Ideal Gas Law Equation of State, Magnuson~~

~~1040 Equatio f Stateno . Wclnstoct ' k; -t t-»-r~~

~~1000 110 ISO 170 TemperatureC ,~~

~~The vapour density of UF is given by the expression:~~

~~p = 4.291 X 10~2 (P/T) (1 + 1.2328 X 104 P/T3) kg/L~~

~~p is the pressure in KPa and T the temperature in degrees Kelvin.~~

~~FIG. AII.3. Vapour density of UF6 (calculated at atmospheric pressure) [10].~~

36 i i i •- ••i'): - _ _ CURVE _ , _ — p- l" 1 E-cpcrlinonldl, Mial ^ \ 2 Calculatod, Berthclot Il 0 ———————— Equation of State —_ —U -L 3 Calculatod, Magnusoa i — 3$ >x~ t Von It/coIfO Parameter 1 i _ ± 4 Calculâ d tV/tlnatoca k 11 1 Non-Ideality Parameter I __ ij \aluc övapoi n do ba i r pressure D - — - s Calculate »•H — data , ttic Cbpc\ron equation and the indi- O r K cjtixi cor rections for thé gafi imperfection _J- - - i n r ~ l i j ^ ! " l i ^ J " " : _ . _j_ - — —— — U — r ~ ~T~ t i X ~~ — _~|_ — — __p_ — - - r * N„4- h - - 7~ ~ S- 1 " S-V'"- Vi u — i — __!__ - —— - — t - S \ — —^ 1 % — «rt -i — — ———— — i — ___. - — ---_- -— t __ e 1 1 J3 3 --r 10 i __ __ M _ _ '„ — — \^^ ~ Uow i i L: :: \ ' ------^ » -- (5 N 0) 11 5 "i" — _. \ 1 1 i ~ r 11 r ~ _ — A N j _ î ^_ . _ L i- ~ \ \ " 1 f \ N 11 4 i _\ — „L. - -_. - — - - -h 3 — — — • _ - - — - - - , - t - - i ^ 11 3 ~ 2 70 280 290 300 310 320 330 31

~~. HeaFIG4 l f sublimatioo tAl . 6 [10UF ]f no~~

C.'J % 1 1 I x CUR Iff "X 1 Exiwrl mental, Mi*l ~~ x 2 Calculated, Mucmifton'f. Non-MoiJIty Puramulor v Xv C.7 '\ 3 CJculalod Weifwtuck's Sun-IdcaJHy Purjmoto~ r > x ~^*, CiUCU lalotj valuer* btuud on vajwr prtu>suro data t the NV N _Clif>l yron equation «jxIndicatec Ih J d corrtcllon gase th _r *to \ V X impe fectlon V i 6 NV ^ "s 1 C x X. o \ \ 2 *X% 3 6 o \ a X t V 3 X \ \ \ \ X HI \ \ \| 9 6 \ X S ——— N N S 7 \ 7 0 37 7 0 36 7 0 35 34 07 3BO 7 300 7 400 7 remp«r*

~~5 Hea l f vaporizatioAl o t G FI 6 [10UF ] f no~~

~~37 46.7 TÏÏT~~

~~45.5~~

~~FIG. AII.6. Heat capacity of the liquid UF [10]. 6~~

~~Temperature, 300~~

~~FIG. AII.7. Heat soli e 6 [10]oth f dUF .~~

~~38 0 90 lOö üU SO 110 0U 7O 0 60 0 50 0 40 0 30 0 20 0 10 TemperatureK ° ,~~

~~FIG. All.8. Heat capacity of UF6 vapour [10].~~

~~2.5~~

~~2.0 luo Ï4 Is~~

~~1.5~~

~~100 150 Temperature, C~~

~~FIG. All.9. Thermal conductivit vapou6 UF f yo r [10].~~

~~39 Chemical properties~~

All.4. Uranium hexafluorid highla s i e y reactive material which reacts chemically with water, ethe d alcohoran foro t l m soluble reaction products. These reactions are very exothermic. Water reacts with UF, to produce

~~uranyl fluoride (UO_F2) and hydrogen fluoride (HF) both of which are very hygroscopic. Two reactions could be mentioned: (a) In gaseous phase:~~

~~UF6(g) + 2H20(g) + U02F2(s) + 4HF(g)~~

~~wher-156.= H eA 8 KJ/mole~~

~~(b) In a condensed state:~~

~~+ UF6(s )2H+ 4HF(g2+ 0(1 ~ U0+ )2F ) 2+~~

~~where AH = -211.6 KJ/mole~~

condensee Ith n d stat reactioe th e solia f no d mas wit, sUF h watey rma o formatioe th o t e sloUO„Ff b e no du w „ hydrate which , coverUF e th s minimizing further reaction with the environment.

oxidizine th o t e g Du propertie UF,f so reactioe ,th f liquino , UF d with some organic material unpredictabls i s explosive b y ma d eean [13]. Small quantities of hydrocarbon oil may react vigorously resulting in a serious explosion resula s A .t extreme caution shoul usee db ensuro t d e that cylinders are clean and free of organics.

e reactivitTh y with fully fluorinated hydrocarbon lows i s F .doeU s not react with oxygen, nitrogen or dry air and it is sufficiently inert to dry aluminium, copper, monel, nickel and aluminium bronze that they can be exposed withou- tUF o t excessive corrosion, o

AII.5. When released to the atmosphere, gaseous UF reacts with humidity tod UO-F- an for F mH . Becaus rate eth e constan e reactioth f to higs i n h the reaction rat dependens i e availabilite th n to waterf yo minimue Th . m amount of water necessary to hydrolize 1000 kg of UF, is 100 kg. At 25 C % anhumidit50 d y this amoun watef to r represent air f s 600so ~ i t .0m I 3 obvious, therefore, tha larga casn i tf eo e scale eth releas, UF f eo hydrolysis might tak econsiderabla e time sucf I .hreleasa e occurn a n si open area, in which case the dispersion is going to be governed by

~~40 meteorological conditions, the plume might still have a considerable concentration of unhydrolysed UF, even at a distance of several hundred metres.~~

~~Activity of UF,~~

All.6e totaTh l.controlles i activit F masU a f n y severaso i yb d l factors including the nature of the feed material, the degree and method of enrichment, the length of time since the UF, has been processed, and its impurity contents. e specifiTh All . c.7 activit UF.f o y variou t .a s level f enrichmeno s s i t D given as an example in Table AII.l.

~~TABLE AII.l SPECIFIC ACTIVITY VALUE URANIUR SFO M HEXAFLUORID VARIOUT EA S LEVEL ENRICHMENF SO ] [6 T~~

~~Mass percent U-235 Specific activity^' present in uranium mixture Bq/g (UF6) Ci/g (UF6)~~

4 -7 0.45 1.2 X 10 3.3 X 10 4 -7 0.72 (natural) 1.7 X 10 4.8 X 10 4 _7 1.0 1.9 X 10 5.1 X 10 4 -7 1.5 2.5 X 10 6.7 X 10 4 -6 5.0 6.7 X 10 1.8 X 10 5 -6 10.0 1.2 X 10 3.2 X 10 5 -6 20.0 2.5 X 10 6.8 X 10 5 5 35 .0 5.0 X 10 1.3 X 10~ 5 -5 50.0 6.2 X 10 1.7 X 10 6 -5 90.0 1.5 X 10 3.9 X 10 6 -5 93 .0 1.8 X 10 4.7 X 10 6 -5 95 .0 2.3 X 10 6.1 X 10

(a) The values of the specific activity include the activity of uranium-234 whic concentrates i h d durin enrichmene th g t process, and do not include any daughter product contribution. The values materiae th r arfo el originating from natural uranium enrichey db gaseous diffusion materiamethodorigie e th th t no f f nI o s . li known the specific activity should be either measured or calculated using isotopic ratio data.

41 All.8. As UF, is produced by a chemical process its equilibrium with its daughter compound disturbes i s d durin process e uraniul th gal s A m. isotopes have very long half lives while the daughters of uranium-238 and uranium-235 (thorium-234 and thorium-231, respectively) have short half lives, a secular equilibrium is going to be attained after a period of approximately 150 days. 4 After that perio specifie th d c activit 0 1 Bq/ x goins e e.g gi b y6 o .3. t g UF for enrichment of 0.45% and 4.0 x 10 Bq/g UF for natural uranium. The specific activity of highly enriched UF, changes only slightly, e.g. at 6 an enrichmenwilt i Bq/1.5e lb 10 % 5gx 90 ÜFf o tß.

All.9. UF, produced from non-irradiated uranium, e.g., uranium ore concentrate, contains no sources of radioactivity other than naturally occurring isotope uraniumf o s , i.e., U-233, U-23 U-23d 5an d thei 4an r daughter products.

~~, produceUF d from irradiate d reprocessean d d uraniu additionalln ca m y contain significant concentrations of:~~

) a other uranium isotopes, e.g., U-232, U-233, U-236, U-237 b) transuranic elements, e.g., Np-237, Pu-239 ) c fission products, e.g., Ru-106, Zr-95/Nb-95, Tc-99 d) daughter products of these species, e.g., Th-228, Tl-208.

The overall composition of this type of UF, will depend upon the reactor type in which the source uranium was irradiated, the burn-up and subsequent cooling history, the efficiency of decontamination for impurities obtained in reprocessing and reconversion and the time elapsed since these processes were carried on. In these circumstances calculation of transport indexes must be madeacr fo eh package based upon specific analytical data.

During its commercial production and enrichment, UF, might be slightly contaminated with reprocessed uranium n sucI .h case materiae th se b y lma treate beins a d non-irradiatef o g d origin, provide meett i de th s specification commerciar fo s , [12]lUF , whic basee har U-23n o d 6 limitations.

All. 10. While UF, packagings often are filled by a liquid transfer they D are emptied by evaporation. The result is that radioactive impurities (or heels volatil)t whicno e har e ten packaginge remaio t dth n i n . Periodic remova f theslo e necessary e heelb y sma .

42 All.11. Depleted and natural UF, are not classified as fissile materials, o and accordingly there is no possibility for nuclear criticality during transport. Although uranium Ü-23% enriche1 classifies o 5i t p u d s fissilea d , uraniu UFs thin ma i f i s enrichment range wil sustait lno nucleana r reaction enricheUF . greateo t d r tha U-23% 1 n fissils 5i e material £ D requiring additional control preveno t s t accidental nuclear criticality. These additional controls are found in the Regulations.

~~Next page(s) left blank AppendiI xH POTENTIAL ACCIDENT CONSEQUENCES AND EMERGENCY RESPONSE PLANNIN PREPAREDNESD GAN S~~

~~ACCIDENTR FO S INVOLVIN RELEASE 6 GTH UF F EO~~

~~Hazards associated wit hreleasa , UF f eo D~~

AIII.l hazarde Th . s associated wite hth releaseo mainle t ar e , du y UF d UO_Fd exposur an d the e dealan „F y H ar o followinte et th wit n i h g sections hazarde Th . exposurf so unhydrolyseo t e highee ar , rdUF than those D involved in the combined exposure to UO„F_ and HF. Although exposure to UF, may result in a hydrolysis reaction occurring within the body, there is currentl o humayn n data available that demonstrate extene th s f damagto e caused by this raeaction. Health effects mentioned in the following sections apply to adults, care should be taken in the use of these values when applied to infants or children.

~~HAZARDS OF URANYL FLUORIDE~~

AIII.2. Uranyl fluoride, UO„F , is produced by hydrolysis of UF . It is a yellow hygroscopic solid which is very soluble in water. The hazards whic associatee har d with UO-F- relat fissileo t e , radiologica d toxilan c properties of UOJF..

AIII.3. Fissile properties of UO_F_ are comparable to UF, from which it is produced by hydrolysis. The most important factors are the enrichment level of uranium and the accident conditions. However, in the case of released gaseous UF, it is highly improbable that UOJF. will develop as a critical system due to the dilution of the uranium which will be dissipated over large areas e fissilTh . e propertiee discussear , UF morn i df so e o detai All.11n i l .

AIII.4 e radiologicaTh . l effec UO„Ff o t n tak pathwayso ca ~tw es i e On . the inhalation of aerosols of UO-F and the other is the potential intake associated with environmental contamination from depostio UO„F„f no .

45 AIII.5 UO-Fs vers A i .-y solubl botn i e hn lun i wate gd fluiran t i , d should be classified as Lung Class D [14] for which the Annual Limit for Intake (ALI) of all the important isotopes of uranium is 5 x 10 Bq. According to the basic dosimetric considerations upon which the Regulations basede ar withiI n AL intak, a 1 ntim a f eo e periominute0 3 f o dconsideres i s d e limitinth e tob g dosr radiologicafo e l effects y comparisoB . n intakna f eo 25 mg of soluble uranium within the same time period is considered as the threshol renaf o d l damage (see para. AIII.7). Thus consultiny ,b g Table AII.I, it can be seen that it is equivalent to one ALI if the enrichment is approximately 80%estimates i t .I dl circumstance al tha n i t e th s toxicological effects of acute exposures will exceed the radiological consequences. Table AIII.l [15] demonstrates this.

TABLE AIII.l COMPARISON OF CHEMICAL TOXICITY OF SOLUBLE URANIUM*

~~Absorbed Quantity Equivalent of Soluble Radiation Uranium Dose Acute Health Effects (mg-U/kg) (uCi) Chemical Toxicity Radiotoxicity~~

~~0.03 0.16 effeco N t No effect 0.058 0.30 Renal injury o effecN t 1.63 8.45 % lethalit50 y No effect 19.29 100 Lethal Onsef to radiological effects * At 97.5% U-235 and 1.14% U-234 enrichment.~~

AIII.6. ÜO_Fa soli s a _ d particulate compoun groundeposiy e dma th n do t ove rlarga e area. o internationalln Ther e ear y accepted value uraniur sfo m contamination level uncontroller sfo d occupancy. Howeve value rth f eo 2 _5 2 0.3 Bq/cm (10 uCi/cm ) is accepted in many countries [16] for unlimited occupancy of uncontrolled areas. This is equivalent to ground 2 3 concentratio naturar fo approxm f lno g/ uraniu 0.00o 1 t m .0. d 3g/ man for 50% enriched uranium.

AIII.7 e toxicologicaTh . l effect solublf so e uranium compounde sar discussed, e.g., by Just et al [15, 17, 18]. Their findings are summarized in Fig. AIII.l. In order to get the amounts of material inhaled one has to

46 multipl integratee th y d exposur breathine th y eb g rate (0.0 2y m /min b d )an the fraction of inhaled uranium absorbed by the body (0.43). For example, the Renal Injury Leve exposurer fo l s shorte minute0 equar 3 ro o t l125s i s 00.0x 2 x 0.43 = 10.75 mg.

~~35JOOO~~

~~x c~~

~~RENAL INJURY ui £ Ü — z "^ o £ o * RB(AL IUURY LEVEL uj >- 1J250 Z.ce oUic O => OQ CO POSSIBLE MILD HEALTH 750~~

~~650 390 NO EFFECT 30 60 EXPOSURE TIME (MINUTES)~~

~~FIG. AIII.1. Toxicit f acutyo e exposure solublo st e uranium [15].~~

~~HAZARD HYDROGEF SO N FLUORIDE~~

AIII.8. Hydrogen fluorid colourlesa s i e s fuming corrosive liquid which boils at 20 C. It is one of the strongest corrosive agents, and it is mose th t f destructivo consideree on e b o et d inorganic agents know humao t n n tissues. A distinction is made between anhydrous hydrogen fluoride (UN Number aqueoun 1052a d )an s solutio hydrofluorif no c aciNumbeN (U d r 1790), whics hi less dangerous.

~~AIII.9. The toxicology of hydrogen fluoride is discussed, e.g. by Just et . [15 al 18], ,17 findinge .Th summarizee sar Fign i d . AIII. Tabld 2an e AIII.2 Ringo. C any db t [8].~~

~~47 NTRATIONX ) (EXPOSURE EQUALS 53,000 (mg-HF/m3>~~

~~IRRITATION/ POSSIBLE HEALTH EFFECTS SMELL/POSSIBLE:~~

~~M^m^^m^m^m^M^^m^peTECTP* BY SMELL LEVEL SMELL/NO HEALTH EFFECTS 10 60~~

~~FIG. AMI.2. Toxicit f acutyo e exposure hydrogeo st n fluoride [17].~~

~~TABLE AIII.2 SUMMARY OF ESTIMATES OF HYDROGEN FLUORIDE TOXICITY [18]~~

~~Source Effect Concentration Exposure Time (min)~~

~~Threshol detectiof do n 0.01 o 2t by smell~~

~~National Institutr efo Short-Term Exposure 5 15 Occupational Safety Limit (STEL) and Health (NIOSH)~~

~~NIOSH Threshold Limit Value 2.5 480 (TLV)~~

~~Occupational Safet& y Permissibl2 e Exposure 480 Health Administration Limit (PEL) (OSHA)~~

~~National Research Emergency Exposure 13.3 10 Council Limit~~

~~NIOSH/OSHA Immediately Dangerous 25.4 30 to Lif Healtr eo h (IDLH)~~

~~48 POTENTIAL CONSEQUENCES OF ACCIDENTS~~

AIII.10. The chemical hazard may dominate the consequences of transport accidents involving depleted, enrichew naturalo d an ld UF,. Howevee th r radiological and especially criticality hazards may become more important in

~~accidents of high enriched UFfi.~~

~~AIII.ll. A criticality accident that results from the transport of enriched~~

UFfi (see All.11) could temporarily resul a larg n i te puls f radiatioeo n levels in the vicinity of the package. Radiation levels could be significant up to some hundred metres away from the package. Following nuclear criticality there would also be residual high radiation in the vicinity of the package. Specific consequence criticalitf o s y accidents uraniue depenth n o dm enrichmen taccidenn o leve d lan t conditions.

AIII.12. Transport accidents in which UF, is involved may be followed by b content release. The amount of UF, released and release rate depends upon o th openine packagee th sizth f n eo i gavailabilite ,th heaf o yd emergenc an t y measures taken.

AIII.13. As long as fire is not involved, a break of the cylinders valve seems to be the most probable mechanical consequence of a road accident. If suc breaha k occur materiae th s l will escape slowl sublimatioy yb n unless brought into contact with water. The rate of release depends strongly on the ambient temperature. In those cases involving small openings the UO_F_ formed by the hydrolysis of UF, will deposit in the openings and will probably reseal the openings. Properly trained and equipped personnel can overcom negative th e e effect f suc so n acciden ha usiny tb g mechanical plugging devices or taking some similar action. If, however, untrained people try to cope with suc n accidenha t they might aggravat consequencee th e e th f so situation by the use of improper procedures. For this reason shippers of hav, UF e issued detailed instructio sucr nfo h emergencies [19]. When appropriate response procedure e followesar e consequenceth d f thiso s typf o e accident cannot be significant.

AIII.14. Transport accidents involving large fires are considered to have the potentia seriour fo l s effects. Such accident y givs ma release th ris o f t eeo larg relativela en i quantitie - F yU shorf so t perio timef o d .

49 A massive UF release may result in dangerous concentrations of both uranium and HF and may also cause area contamination of several square kilometres. A discussion of such a hypothetical accident is given in Ref. [10]. In that document some emergency procedures are recommended.

AIII.15. In considering possible accidents involving the transport of UF, y seab , scenarios describin sinkine th gshia f pgo followe breece a th y db f ho valve with wate leakagn i r e have been studied [11,20 conclusioe Th ] s thanwa t any water inleakage would not result in a chemical explosion.

AIII.16. Additionally, fire n ship o sknow e s ar hav o nt e long duratiod nan high temperatures that might result in releases with consequent serious exposure ship'e n port i th e shi o s th otheo st i p,t f crewi r d individual,an s withi vicinite vessele th n th f yo .

~~AIII.17. No assessment is known to have been made concerning the risk~~

~~involved in air transport of UF,. However, only small quantities of UF i f are expected to be shipped by air.~~

~~50 REFERENCES~~

~~] MALLET[1 , A.J., ORGDP Container TesDevelopmend tan t Programme: Fire Tests -filleF oU f UFg-filled Cylindersd Cyl,: K-D-1984, Union Carbide Corp. Ridgek ,Oa , Tennessee (1966).~~

[2] INTERNATIONAL ATOMIC ENERGY AGENCY, Regulations for the Safe Transport of Radioactive Material, Safety IAEA, Serie6 . , sNo Vienn a (1985)d ;an Supplement 1986 (1986); and Supplement 1988 (1988); and As Amended 1990 (1990).

~~[3] UNITED NATIONS COMMITTEE OF EXPERTS ON THE TRANSPORT OF DANGEROUS GOODS, Recommendations on the Transport of Dangerous Goods, Rep. ST/SG/AClO/1/Rev. 5, United Nations, New York (1988).~~

~~[4] AMERICAN NATIONAL STANDARDS INSTITUTE, American National Standard for Packaging of Uranium Hexafluoride for Transport. ANSI 14.1, ANSI, New York (1987).~~

~~[5] UNITED STATES DEPARTMENT OF ENERGY, Uranium Hexafluoride: Handling Procedures and Container Descriptions, ORO-651-Rev. 5, US DOE, Oak Ridge, Tennessee (1987).~~

[6] INTERNATIONAL ATOMIC ENERGY AGENCY, Advisory Material for the IAEA Regulation Safe th e r Transporsfo Radioactivf to e Material (1985 Edition), Third Edition, Safety IAEA, Serie37 ,. ViennsNo a (1987).

~~[7] INTERNATIONAL ORGANIZATION FOR STANDARDIZATION, Refillable Welded Steel Gas Cylinders, 150 4706, ISO, Geneva (1989).~~

~~] RINGOT[8 HAMARDToxi, e Radiologica,d C. Th can , ,J. l Risk Equivalence~~

~~Approac UFn hi f t Transport (ProcSaf- , e .UF Handling , Processind gan Transporting Ridgek ,Oa , Tennessee 1988)y ,Ma , Conf 880558 29-3. ,pp 6 (1988).~~

~~] BIAGGIO[9 LOPEZ-VIETRI, ,A. Transporn i F U , t, J. Accident s (Proc. PATRAM '86 Symposium, Davos, June 1986), IAEA, Vienna p.381 (1987).~~

~~[10] DeWITT Uraniu, ,R. m Hexafluoride Physico-Chemicae SurveA :th f yo l Properties, GAT-280, Goodyear Atomic Corp, Portsmouth, Ohio, (1960).~~

51 [11] GEFFEN, O.A., JOHNSON, J.F. al.t ,e Assessmenn ,A Rise f th ko f to Transporting Uranium Hexafluoride by Truck and Train, PNL-2211, Battelle Pacific Northwest Laboratories, Richland, WA (1978).

~~[12] AMERICAN SOCIET TESTINR YFO MATERIALSD GAN , Uranium Hexafluoridr efo Enrichment, ASTM Specification 787-76, Philadelphia, PA (1980).~~

~~[13] UNITED STATES DEPARTMENT OF ENERGY, Liquid UFg Explodes When it Contracts Hydrocarbon Oil, Safety Alert No. 3, DOE/EP-0050/3, USDOE, Washington (1983).~~

~~[14] INTERNATIONAL COMMISSION ON RADIOLOGICAL PROTECTION, Limits for Intakes of Radionuclide Workersy sb , Publicatio Pergamo, 30 n n Press, Oxford an d New York (1980).~~

[15] JUST, R.A., Acute Toxicity of Uranium Hexafluoride, Uranyl Fluoride and Hydrogen Fluoride (ProcSaf- , e .UF Handling , Processind gan Transporting, Oak Ridge, Tennessee, May 1988), Conf 880558, pp. 7-10 (1988).

~~[16] NATIONAL RADIOLOGICAL PROTECTION BOARD, Derived Limits for Surface Contamination, NRPB, Harwell (1979).~~

~~[17] JUST, R.A., EMLER, V.S., Generic Repor Healtn o t S hU e Effectth r fo s Gaseous Diffusion Plants, K/D-5050-Section VIII, Par USDOE, 1 t Ridgk ,Oa e Gaseous Diffusion Plant, Tennessee (1984).~~

~~[18] JUST, R.A., Repor Toxicologican o t l Studies Concerning ExposureF U o t s and UF, Hydrolysis Products, K/D-5K/D-5573-Rev.l1 , USDOE, Oak Ridge Gaseous o Diffusion Plant, Tennessee (1984).~~

~~[19] ELDORADO RESOURCES, Radioactive Material: Solid Uranium Hexafluoride, Potential Hazards, Emergency Instruction, Eldorado Resources, Ontario, Canada (1979).~~

~~[20] RINGOT, C., WARNIEZ, P., Behaviour of Uranium Hexafluoride in the Presence of Water, Report No. SAET/86-298, Commissariat à l'énergie atomique, Paris (1986).~~

~~52 CONTRIBUTORS TO DRAFTING AND REVIEW~~

~~CONSULTANTS MEETING Jun0 Jul4 .3 e- y 1986~~

~~Blum . ,P Transnucléaire, France~~

~~Hueston . ,F Eldorado Resources Limited, Canada~~

~~Koponen, H. International Atomic Energy Agency (Scientific Secretary)~~

~~Levin, I. International Atomic Energy Agency~~

~~Pope, R.B. International Atomic Energy Agency~~

~~Pryor, W. US Department of Energy, USA~~

~~TECHNICAL COMMITTEE MEETING, 3-7 November 1986~~

~~Ajuria . ,S International Atomic Energy Agency~~

~~Anda, F. Empresa Nacional del Uranio S.A., Spain~~

~~Baekelandt, L. Ministère de la Santé Publique et de la Famille, Belgium~~

~~Biaggio, A.L. Comision Nacional de Energie Atomica, Argentina~~

~~Blum . ,P Transnucléaire, France~~

~~Cheshire, R.D. British Nuclear Fuels pic, United Kingdom~~

~~Dekker, B.C. Urenco Nederland Operations B.V., Netherlands~~

~~Dufva, B. Swedish Nuclear Power Inspectorate, Sweden~~

~~Forasassi . ,G Universit Pisaf yo , Italy~~

~~53 Jincho. ,M Chulu Electric Powe . Inc.rCo , Japan~~

~~. KaiT , Power Reactor and Nuclear Fuel Development Corporation, Japan~~

~~Kitamura, T. Power Reactor and Nuclear Fuel Development Corporation, Japan~~

~~Koponen, H. International Atomic Energy Agency (Scientific Secretary)~~

~~Levin, I. International Atomic Energy Agency~~

~~May, G. British Nuclear Fuels pic, United Kingdom~~

~~McLellan, J.J. Atomic Energy Control Board, Canada~~

~~Orsini, A. ENE Comitat- A o Nazionale Energia, Italy~~

~~0'Sullivan, R. International Atomic Energy Agency~~

~~Pope, R.B. Sandia National Laboratories, USA~~

~~Pryor, W. US Department of Energy, USA~~

~~Ridder, K. Bundesministeriu Verkehrr fü m , Germany~~

~~Ringot. ,C Commissariat à l'énergie atomique, France~~

~~Sannen, H. Transnubel, Belgium~~

~~Selling, H.A. State Health Inspectorate/Nuclear Inspectorate Netherlands~~

~~Shiomi, S. Central Research Institute of Electric Power Industry, Japan~~

~~Trivelloni, S. ENEA, Italy~~

~~Warniez, P. Commissaria l'énergià t e atomique, France~~

~~54 Webster, A.R. Department of Transport, United Kingdom~~

~~Wieser, K. Bundesanstal Materialprüfunr fü t g (BAM), Germany~~

~~COMMENTATORS ON THE DRAFT TECDOC. November 1986~~

~~Baekelandt, L. Ministère de la Santé Publique et de la Famille, Belgium~~

~~Blum, P. Transnucléaire, France~~

~~Dekker, B.C. Urenco Nederland Operations B.V., Netherlands~~

~~Kitamura. ,T Power Reacto Nuclead ran r Fuel Development Corporation, Japan~~

~~McLellan, J.J. Atomic Energy Control Board, Canada~~

~~Pryor, W. DepartmenS U Energyf to A ,US~~

~~Ringet, C. Commissaria l'énergità e atomique, France~~

~~Warniez, P. Commissariat à l'énergie atomique, France~~

~~Webster, A.R. Department of Transport, United Kingdom~~

~~Wieser. ,K Bundesanstalt für Materialprüfung (BAM), Germany~~

~~FINAL DRAFT TECDOC-423~~

~~Koponen. ,H International Atomic Energy Agency (Scientific Secretary)~~

~~Levin, I. International Atomic Energy Agency~~

~~0'Sullivan, R. International Atomic Energy Agency~~

~~55 CONSULTANTS SERVICES MEETING. 25-28 April 1988~~

~~Levin, I. International Atomic Energy Agency (Scientific Secretary)~~

~~Pryor, W. US Departmen Energyf o t A ,US~~

~~Wieser. ,K Bundesanstal Materialprüfunr fü t g (BAM), Germany~~

~~TECHNICAL COMMITTEE MEETING. 2-6 Mav 1988~~

~~Arendt, J. Institute of Nuclear Materials Management, USA~~

~~Biaggio, A. Comision Naciona Energie ld a Atomica, Argentina~~

~~Cosack. ,M PTB, Germany~~

~~Dekker, B.C. URENCO Nederlands Operations B.V., Netherlands~~

~~Eyre, P. Atomic Energy Control Board, Canada~~

~~Hayes. ,T British Nuclear Fuels pic, United Kingdom~~

~~Levin, I. International Atomic Energy Agency (Scientific Secretary)~~

~~Mauduit. ,C COGEMA, Branche Enrichissement, France~~

~~Nakashima, S. Nuclear Safety Bureau, Japan~~

~~Olsson. ,R Swedish Nuclear Power Inspectorate, Sweden~~

~~0'Sullivan, R.A. International Atomic Energy Agency~~

~~Pryor, W.A. PAI Corporation, USA~~

~~56 Reynolds, R. Martin Marietta Energy Systems, Inc., USA~~

~~Ridder. ,K Budesministerium für Verkehr, Germany~~

~~Ringot. ,C Commissariat à l'énergie atomique, France~~

~~Sannen, H. Transnubel, Belgium~~

~~Sanui. ,T Nuclear Fuel Transport Company, Ltd., Japan~~

~~Selling, H.A. State Health Inspectorate/Nuclear Inspectorate Netherlands~~

~~Shiomi. ,S Central Research Institute of Electric Power Industry, Japan~~

~~Wangler, M. US Department of Transportation, USA~~

~~Warniez. ,P Commissariat à l'énergie atomique, France~~

~~Webster, A.R. Department of Transport, United Kingdom~~

~~Wieser, K. Bundesanstalt für Materialprüfung (BAM), Germany~~

~~Yasogawa. ,Y Japan Marine Surveyors and Sworn Measures Association, Japan~~

~~CONSULTANTS SERVICE MEETING Octobe3 .1- r 1990~~

~~Reynolds. ,R Martin Marietta Engineering Systems Inc., USA~~

~~Ringot. ,C Commissaria tl'énergià e atomique, France~~

~~Selling, H.A. International Atomic Energy Agency (Scientific Secretary)~~

~~57 Shiomij S. Central Research Institute of Electric Power Industry, Japan~~

~~Thomas, B.C. Gaseous Diffusion OperationsA ,US~~

~~Takahashi, M. Power Reacto Nuclead ran r Fuel Development Corporation, Japan~~

~~Young, C. Departmen Transportf o t , United Kingdom~~

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