Fission Yield Measurements from Deuterium-Tritium Fusion Produced Neutrons Using Cyclic Neutron Activation Analysis and Γ-Γ Coincidence Counting
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The Transuranium Elements: from Neptunium and Plutonium to Element 112
UCRL-JC- 124728 The Transuranium Elements: From Neptunium and Plutonium to Element 112 Professor Darleane C. Hoffman Lawrence Livermore National Laboratory G. Seaborg Institute for Transactinium Science RECEIVED T. Isotope Sciences Division sEp23 ?9g6 This paper was prepared for submittal to the Conference Proceedings NATO Advanced Study Institute on "Actinides and the Environment" Chania, Crete, Greece July 7-19, 1996 July 26, 1996 DISCWMER This document was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor the University of California nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or the University of California. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or the University of California, and shall not be used for advertising or product endorsement purposes. DISCLAIMER Portions of this document may be illegible in electronic image products. Images are produced from the best avaiiable original document. c THE TRANSURANIUM ELEMENTS: FROM NEPTUNIUM AM) PLUTONIUM TO ELEMENT112 DarIeane C. Hoffman Nuclear Science Division & Chemistry Department, University of California, Berkeley, CA 94720 & G. T. Seaborg Institute for ' Transactinium Science, MS-L23 1, LLNL, Livermore, CA 94550. -
ESTIMATION of FISSION-PRODUCT GAS PRESSURE in URANIUM DIOXIDE CERAMIC FUEL ELEMENTS by Wuzter A
NASA TECHNICAL NOTE NASA TN D-4823 - - .- j (2. -1 "-0 -5 M 0-- N t+=$j oo w- P LOAN COPY: RET rm 3 d z c 4 c/) 4 z ESTIMATION OF FISSION-PRODUCT GAS PRESSURE IN URANIUM DIOXIDE CERAMIC FUEL ELEMENTS by WuZter A. PuuZson una Roy H. Springborn Lewis Reseurcb Center Clevelund, Ohio NATIONAL AERONAUTICS AND SPACE ADMINISTRATION WASHINGTON, D. C. NOVEMBER 1968 i 1 TECH LIBRARY KAFB, NM I 111111 lllll IllH llll lilll1111111111111 Ill1 01317Lb NASA TN D-4823 ESTIMATION OF FISSION-PRODUCT GAS PRESSURE IN URANIUM DIOXIDE CERAMIC FUEL ELEMENTS By Walter A. Paulson and Roy H. Springborn Lewis Research Center Cleveland, Ohio NATIONAL AERONAUTICS AND SPACE ADMINISTRATION For sale by the Clearinghouse for Federal Scientific and Technical Information Springfield, Virginia 22151 - CFSTl price $3.00 ABSTRACl Fission-product gas pressure in macroscopic voids was calculated over the tempera- ture range of 1000 to 2500 K for clad uranium dioxide fuel elements operating in a fast neutron spectrum. The calculated fission-product yields for uranium-233 and uranium- 235 used in the pressure calculations were based on experimental data compiled from various sources. The contributions of cesium, rubidium, and other condensible fission products are included with those of the gases xenon and krypton. At low temperatures, xenon and krypton are the major contributors to the total pressure. At high tempera- tures, however, cesium and rubidium can make a considerable contribution to the total pressure. ii ESTIMATION OF FISSION-PRODUCT GAS PRESSURE IN URANIUM DIOXIDE CERAMIC FUEL ELEMENTS by Walter A. Paulson and Roy H. -
Compilation and Evaluation of Fission Yield Nuclear Data Iaea, Vienna, 2000 Iaea-Tecdoc-1168 Issn 1011–4289
IAEA-TECDOC-1168 Compilation and evaluation of fission yield nuclear data Final report of a co-ordinated research project 1991–1996 December 2000 The originating Section of this publication in the IAEA was: Nuclear Data Section International Atomic Energy Agency Wagramer Strasse 5 P.O. Box 100 A-1400 Vienna, Austria COMPILATION AND EVALUATION OF FISSION YIELD NUCLEAR DATA IAEA, VIENNA, 2000 IAEA-TECDOC-1168 ISSN 1011–4289 © IAEA, 2000 Printed by the IAEA in Austria December 2000 FOREWORD Fission product yields are required at several stages of the nuclear fuel cycle and are therefore included in all large international data files for reactor calculations and related applications. Such files are maintained and disseminated by the Nuclear Data Section of the IAEA as a member of an international data centres network. Users of these data are from the fields of reactor design and operation, waste management and nuclear materials safeguards, all of which are essential parts of the IAEA programme. In the 1980s, the number of measured fission yields increased so drastically that the manpower available for evaluating them to meet specific user needs was insufficient. To cope with this task, it was concluded in several meetings on fission product nuclear data, some of them convened by the IAEA, that international co-operation was required, and an IAEA co-ordinated research project (CRP) was recommended. This recommendation was endorsed by the International Nuclear Data Committee, an advisory body for the nuclear data programme of the IAEA. As a consequence, the CRP on the Compilation and Evaluation of Fission Yield Nuclear Data was initiated in 1991, after its scope, objectives and tasks had been defined by a preparatory meeting. -
Wo 2009/108331 A2
(12) INTERNATIONAL APPLICATION PUBLISHED UNDER THE PATENT COOPERATION TREATY (PCT) (19) World Intellectual Property Organization International Bureau (10) International Publication Number (43) International Publication Date 3 September 2009 (03.09.2009) WO 2009/108331 A2 (51) International Patent Classification: AO, AT, AU, AZ, BA, BB, BG, BH, BR, BW, BY, BZ, A61K 38/22 (2006.01) CA, CH, CN, CO, CR, CU, CZ, DE, DK, DM, DO, DZ, EC, EE, EG, ES, FI, GB, GD, GE, GH, GM, GT, HN, (21) International Application Number: HR, HU, ID, IL, IN, IS, JP, KE, KG, KM, KN, KP, KR, PCT/US2009/001213 KZ, LA, LC, LK, LR, LS, LT, LU, LY, MA, MD, ME, (22) International Filing Date: MG, MK, MN, MW, MX, MY, MZ, NA, NG, NI, NO, 25 February 2009 (25.02.2009) NZ, OM, PG, PH, PL, PT, RO, RS, RU, SC, SD, SE, SG, SK, SL, SM, ST, SV, SY, TJ, TM, TN, TR, TT, TZ, UA, (25) Filing Language: English UG, US, UZ, VC, VN, ZA, ZM, ZW. (26) Publication Language: English (84) Designated States (unless otherwise indicated, for every (30) Priority Data: kind of regional protection available): ARIPO (BW, GH, 61/066,959 25 February 2008 (25.02.2008) US GM, KE, LS, MW, MZ, NA, SD, SL, SZ, TZ, UG, ZM, Not furnished 25 February 2009 (25.02.2009) US ZW), Eurasian (AM, AZ, BY, KG, KZ, MD, RU, TJ, TM), European (AT, BE, BG, CH, CY, CZ, DE, DK, EE, (71) Applicant and ES, FI, FR, GB, GR, HR, HU, IE, IS, IT, LT, LU, LV, (72) Inventor: FORSLEY, Lawrence, Parker, Galloway MC, MK, MT, NL, NO, PL, PT, RO, SE, SI, SK, TR), [US/US]; 70 Elmwood Avenue, Rochester, NY 1461 1 OAPI (BF, BJ, CF, CG, CI, CM, GA, GN, GQ, GW, ML, (US). -
Relative Fission Product Yield Determination in the Usgs
RELATIVE FISSION PRODUCT YIELD DETERMINATION IN THE USGS TRIGA MARK I REACTOR by Michael A. Koehl © Copyright by Michael A. Koehl, 2016 All Rights Reserved A thesis submitted to the Faculty and the Board of Trustees of the Colorado School of Mines in partial fulfillment of the requirements for the degree of Doctor of Philosophy (Nuclear Engineering). Golden, Colorado Date: ____________________ Signed: ________________________ Michael A. Koehl Signed: ________________________ Dr. Jenifer C. Braley Thesis Advisor Golden, Colorado Date: ____________________ Signed: ________________________ Dr. Mark P. Jensen Professor and Director Nuclear Science and Engineering Program ii ABSTRACT Fission product yield data sets are one of the most important and fundamental compilations of basic information in the nuclear industry. This data has a wide range of applications which include nuclear fuel burnup and nonproliferation safeguards. Relative fission yields constitute a major fraction of the reported yield data and reduce the number of required absolute measurements. Radiochemical separations of fission products reduce interferences, facilitate the measurement of low level radionuclides, and are instrumental in the analysis of low-yielding symmetrical fission products. It is especially useful in the measurement of the valley nuclides and those on the extreme wings of the mass yield curve, including lanthanides, where absolute yields have high errors. This overall project was conducted in three stages: characterization of the neutron flux in irradiation positions within the U.S. Geological Survey TRIGA Mark I Reactor (GSTR), determining the mass attenuation coefficients of precipitates used in radiochemical separations, and measuring the relative fission products in the GSTR. Using the Westcott convention, the Westcott flux, ; modified spectral index, ; neutron temperature, ; and gold-based cadmium ratiosφ were determined for various sampling√⁄ positions in the USGS TRIGA Mark I reactor. -
Ornl-Tm-1853
OAK RIDGE NATIONAL LABORATORY operated by UNION CARBIDE CORPORATION for the U.S. ATOMIC ENERGY COMMISSION ORNL- TM-1853 COPY NO. - 0-C kc+- DATE -6-6-67 CFSTI RpICZiS CHEMICAL RESEARCHAND DEVELOPMENTFOR MOLTEN- SALT BREEDERREACTORS W. R. Grimes ABSTRACT kq Results of the 15-year program of chemical research and develop- .; ment for molten salt reactors are summarized in this document. These c results indicate that 7LiF-BeFz-LJFb mixtures are feasible fuels for thermal breeder reactors. Such mixtures show satisfactory phase be- havior, they are compatible with Hastelloy N and moderator graphite, and they appear to resist radiation and tolerate fission product ac- cumulation. Mixtures of 7LiF-BeF2-ThF4 similarly appear suitable as blankets for such machines. Several possible secondary coolant mix- tures are available; NaF-NaBF3 systems seem, at present, to be the most likely possibility. Gaps in the technology are presented along with the accomplish- ments, and an attempt is made to define the information (and the research and development program) needed before a Molten Salt Thermal Breeder can be operated with confidence. NOTICE This document contains information of a preliminary nature and was prepared primarily for internal use at the Oak Ridge National Loboratory. It is subject to revision or correction and therefore does not represent a final report. The information is not to be abstracted, reprinted or otherwise given public dis- 4 .”: semination without the approval of the ORNL potent branch, Legal and Infor- mation Control Department. ’ y a I LEGAL NOTICE This report was prepored as an occount of Government sponsored work. Neither the United States, nw the Commission, nor ony person octing un beholf of the Commission: A. -
The Electronuclear Conversion of Fertile to Fissile Material
UCRL-52144 THE ELECTRONUCLEAR CONVERSION OF FERTILE TO FISSILE MATERIAL C. M. Van Atta J. D. Lee H. Heckrotto October 11, 1976 Prepared for U.S. Energy Research & Development Administration under contract No. W-7405-Eng-48 II\M LAWRENCE lUg LIVERMORE k^tf LABORATORY UnrmsilyotCatftxna/lJvofmofe s$ PC DISTRIBUTION OF THIS DOCUMENmmT IS UMUMWTED NOTICE Thii npoit WM prepared w u account of wot* •pomond by UM Uiilttd Stalwi GovcmiMM. Nittim Uw United Stain nor the United Statn Energy tUwardi it Development AdrnWrtrtUon, not «y of thei* employee!, nor any of their contricton, •ubcontrecton, or their employe*!, makti any warranty, expreai « Implied, or muMi any toga) liability oc reeponafctUty for the accuracy, completenni or uMfulntat of uy Information, apperatui, product or proem dlecloead, or repreienl. that tu UM would not *nfrkig» prrrtt*)}MWiwd r%hl». NOTICE Reference to a oompmy or product rum don not imply approval or nconm ndatjon of the product by the Untnrtity of California or the US. Energy Research A Devetopnient Administration to the uchvton of others that may be suitable. Printed In the United Stitei or America Available from National Technical Information Service U.S. Department of Commerce 528S Port Royal Road Springfield, VA 22161 Price: Printed Copy S : Microfiche $2.25 DMimtic P»t» Ranflt PHca *•#» Rtnft MM 001-025 $ 3.50 326-350 10.00 026-050 4.00 351-375 10.50 051-075 4.50 376-400 10.75 076-100 5.00 401-425 11.00 101-125 5.50 426-450 31.75 126-150 6.00 451-475 12.00 151-175 6.75 476-500 12.50 176-200 7.50 501-525 12.75 201-225 7.75 526-550 13.00 526-250 8.00 551-575 13.50 251-275 9.00 576-600 I3.7S 276-300 9.25 601 -up 301-325 9.75 *Ml J2.50 fot «ch iddltlOMl 100 pip tacmitMt from 601 ID 1,000 flfcK IM 54.50 for eicli iMUknal I0O plfe feenmMI om 1,000 p*o. -
Use of DD-108 Neutron Generator with ISU Sub-Critical Assembly
From: Ramsey, Kevin To: Maxwell Daniels Cc: Campbell, Vivian; Font, Ossy; Yin, Xiaosong; Gonzalez, Hipolito; Johnson, Robert; Tripp, Christopher Subject: Use of DD-108 neutron generator with ISU sub-critical assembly Date: Thursday, July 20, 2017 3:46:00 PM We have evaluated your proposal to use a neutron generator to pulse your sub-critical assembly, and concluded that you may use the neutron generator under the current authorization in Materials License SNM-1373. Our finding that you may proceed without an amendment is based on the following understanding. If your understanding differs, please inform us. It is our understanding that you want to use the Adelphi Technology DD-108 Neutron Generator described at http://www.adelphitech.com/products/dd108.html. The technical brochure located at http://www.adelphitech.com/pdfs/DD108-9_generator_Flier_24-Nov- 14_A.PDF states that the device uses deuterium gas to produce 2.45 MeV neutrons. The NRC does not regulate the possession and use of deuterium, so there is no need to add the device to one of your NRC licenses. PLEASE NOTE – NRC regulates tritium and a license amendment would be needed to possess and use a tritium neutron generator. Our criticality safety evaluation concluded that using a neutron source will affect the fission rate, but will not affect the neutron multiplication or criticality analysis. From the description and pictures of the neutron generator, it appears that it would only contain a small amount of deuterium. As long as this is not permitted to come into physical contact with the SNM, there should be no issue. -
Gasket Chemical Services Guide
Gasket Chemical Services Guide Revision: GSG-100 6490 Rev.(AA) • The information contained herein is general in nature and recommendations are valid only for Victaulic compounds. • Gasket compatibility is dependent upon a number of factors. Suitability for a particular application must be determined by a competent individual familiar with system-specific conditions. • Victaulic offers no warranties, expressed or implied, of a product in any application. Contact your Victaulic sales representative to ensure the best gasket is selected for a particular service. Failure to follow these instructions could cause system failure, resulting in serious personal injury and property damage. Rating Code Key 1 Most Applications 2 Limited Applications 3 Restricted Applications (Nitrile) (EPDM) Grade E (Silicone) GRADE L GRADE T GRADE A GRADE V GRADE O GRADE M (Neoprene) GRADE M2 --- Insufficient Data (White Nitrile) GRADE CHP-2 (Epichlorohydrin) (Fluoroelastomer) (Fluoroelastomer) (Halogenated Butyl) (Hydrogenated Nitrile) Chemical GRADE ST / H Abietic Acid --- --- --- --- --- --- --- --- --- --- Acetaldehyde 2 3 3 3 3 --- --- 2 --- 3 Acetamide 1 1 1 1 2 --- --- 2 --- 3 Acetanilide 1 3 3 3 1 --- --- 2 --- 3 Acetic Acid, 30% 1 2 2 2 1 --- 2 1 2 3 Acetic Acid, 5% 1 2 2 2 1 --- 2 1 1 3 Acetic Acid, Glacial 1 3 3 3 3 --- 3 2 3 3 Acetic Acid, Hot, High Pressure 3 3 3 3 3 --- 3 3 3 3 Acetic Anhydride 2 3 3 3 2 --- 3 3 --- 3 Acetoacetic Acid 1 3 3 3 1 --- --- 2 --- 3 Acetone 1 3 3 3 3 --- 3 3 3 3 Acetone Cyanohydrin 1 3 3 3 1 --- --- 2 --- 3 Acetonitrile 1 3 3 3 1 --- --- --- --- 3 Acetophenetidine 3 2 2 2 3 --- --- --- --- 1 Acetophenone 1 3 3 3 3 --- 3 3 --- 3 Acetotoluidide 3 2 2 2 3 --- --- --- --- 1 Acetyl Acetone 1 3 3 3 3 --- 3 3 --- 3 The data and recommendations presented are based upon the best information available resulting from a combination of Victaulic's field experience, laboratory testing and recommendations supplied by prime producers of basic copolymer materials. -
How I Learned to Stop Worrying and Dismantle the Bomb New Approaches to Nuclear Warhead Verification
HOW I LEARNED TO STOP WORRYING AND DISMANTLE THE BOMB NEW APPROACHES TO NUCLEAR WARHEAD VERIFICATION Alex Glaser,* Sébastien Philippe,* and Robert J. Goldston** *Princeton University **Princeton University and Princeton Plasma Physics Laboratory Duke University, January 19, 2017 Revision 1 CONSORTIUM FOR VERIFICATION TECHNOLOGY PNNL Oregon State MIT U Michigan INL Yale U Wisconsin Columbia Penn State Princeton and PPPL U Illinois LBNL LLNL Sandia NNSS Duke ORNL NC State LANL Sandia U Florida (not shown: U Hawaii) Five-year project, funded by U.S. DOE, 13 U.S. universities and 9 national labs, led by U-MICH Princeton participates in the research thrust on disarmament research (and leads the research thrust of the consortium on policy) A. Glaser, S. Philippe, R. Goldston, How I Learned to Stop Worrying and Dismantle the Bomb, Duke University, January 19, 2017 2 INTERNATIONAL PARTNERSHIP FOR NUCLEAR DISARMAMENT VERIFICATION Established in 2015; currently 26 participating countries Working Group One: “Monitoring and Verification Objectives” (chaired by Italy and the Netherlands) Working Group Two: “On-Site Inspections” (chaired by Australia and Poland) Working Group Three: “Technical Challenges and Solutions” (chaired by Sweden and the United States) www.state.gov/t/avc/ipndv A. Glaser, S. Philippe, R. Goldston, How I Learned to Stop Worrying and Dismantle the Bomb, Duke University, January 19, 2017 3 WHAT’S NEXT FOR NUCLEAR ARMS CONTROL? 2015 STATEMENT BY JAMES MATTIS “The nuclear stockpile must be tended to and fundamental questions must be asked and answered: • We must clearly establish the role of our nuclear weapons: do they serve solely to deter nuclear war? If so we should say so, and the resulting clarity will help to determine the number we need. -
Radiological Safety Aspects of the Operation of Neutron Generators
\ This publication is no longer valid Nuclear Safety Information Centre, B0655 Please see http://www-ns.iaea.org/standards/ OBSOLETE SAFETY SERIES No. 42 Radiological Safety Aspects of the Operation of Neutron Generators INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA, 1 976 This publication is no longer valid Please see http://www-ns.iaea.org/standards/ This publication is no longer valid Please see http://www-ns.iaea.org/standards/ RADIOLOGICAL SAFETY ASPECTS OF THE OPERATION OF NEUTRON GENERATORS This publication is no longer valid Please see http://www-ns.iaea.org/standards/ The following States are Members of the International Atomic Energy Agency: AFGHANISTAN HOLY SEE PHILIPPINES ALBANIA HUNGARY POLAND ALGERIA ICELAND PORTUGAL A RG EN TIN A IN D IA QATAR AUSTRALIA INDONESIA REPUBLIC OF SOUTH VIETNAM AUSTRIA IRAN ROMANIA BANGLADESH IRAQ SAUDI ARABIA BELG IU M IRELAND SENEGAL BOLIVIAISRAEL SIERRA LEONE BRAZIL ITALY SINGAPORE BULGARIA IVORY COAST SOUTH AFRICA BURMA JAMAICA SPAIN BYELORUSSIAN SOVIET JAPAN SRI LANKA SOCIALIST REPUBLIC JORDANSUDAN CAMBODIA KENYA SWEDEN CANADA KOREA, REPUBLIC OF SWITZERLAND CHILE KUWAIT SYRIAN ARAB REPUBLIC COLOM BIA LEBANON THAILAND COSTA RICA LIBERIA TUNISIA CUBA LIBYAN ARAB REPUBLIC TURKEY CYPRUS LIECHTENSTEIN UGANDA CZECHOSLOVAKIA LUXEMBOURG UKRAINIAN SOVIET SOCIALIST DEMOCRATIC PEOPLE’S MADAGASCAR REPU BLIC REPUBLIC OF KOREA MALAYSIA UNION OF SOVIET SOCIALIST DENMARK MALI REPUBLICS DOMINICAN REPUBLIC MAURITIUS UNITED ARAB EMIRATES ECUADOR M EXICO UNITED KINGDOM OF GREAT EGYPT MONACO BRITAIN AND NORTHERN -
NOI to Prepare an Environmental Impact Statement For
Federal Register / Vol. 64, No. 34 / Monday, February 22, 1999 / Notices 8553 reauthorization of OERI and will hear DEPARTMENT OF ENERGY Orders are summarized in the attached committee and officers' reports. A final appendix. [FE Docket Nos. 99±01±NG, 99±03±NG, 99± agenda will be available from the Board 02±NG, 99±04±NG, 92±24±NG, 99±05±NG, These Orders may be found on the FE office on March 10, 1999, and will be and 99±06±NG] web site at http://www.fe.doe.gov., or posted on the Board's web site, http:// on the electronic bulletin board at (202) www.ed.gov/offices/OERI/NERPPB/. Office of Fossil Energy; Orders 586±7853. Granting and Transferring Records are kept of all Board They are also available for inspection Authorizations To Import and/or Export proceedings and are available for public and copying in the Office of Natural Gas Natural Gas inspection at the office of the National & Petroleum Import & Export Activities, Educational Research Policy and OGE Energy Resources, Inc., National Fuel Docket Room 3E±033, Forrestal Priorities Board, Suite 100, 80 F St., Gas Distribution Corporation, Renaissance Building, 1000 Independence Avenue, NW, Washington, D.C. 20208±7564. Energy (U.S.) Inc., Selkirk Cogen Partners, SW, Washington, DC 20585, (202) 586± L.P., Coral Energy Resources, L.P. (Successor 9478. The Docket Room is open between Dated: February 16, 1999. to Salmon Resources Ltd.), Transco Energy the hours of 8:00 a.m. and 4:30 p.m., Eve M. Bither, Marketing Company, and Petro-Canada Hydrocarbons Inc.