Appendix B, Part 2

Total Page:16

File Type:pdf, Size:1020Kb

Appendix B, Part 2 PC-055 AVRAVR undund FFon ort St.St. VrainVrain HTGRHTGR fUrftir denden THTRTHTR; ; diesediese AnlagenAnlagen werdenwerden auchauch inin den den USAUSA alsals kammerziellekommerzielle betrachtet.betrachtet. DieDie mmiserable iserable LeistungsbilanzLeistungsbilanz derder deutschen deutschen KKugelhzufen-Reaktorenu gelhaufen-Reaktoren kannkann nichtnicht alsals ArgumentArgument gegengegen derenderen kommerziellekommerzielle Intentionenlntentionen dienen:dienen: SieSie warenwaren kommerzieUekommerzielle Reaktoren!Reaktorenl . EsEs bestehtbesteht keinkein signifikantessignifikantes ProliferationsProliferations-Risiko -Risiko fUrfür denden AVR-MOII,AVR-l\rüll, wiewie verschiedene GutachtenGutacl{en (z.B.(2.B. auchauch vonvon NNSANNSA, , 2013)2013) darlegen.darlegen. 1mlm AligemeinenAllgemeinen enthaltenthailt derderAVR-Müll AVR-MUII keinkein HEU.HEU. EineEine KanditianierungKonditionierung undund EndlageEndlagerung ru ng inin Deutschland Deutschland wawärenr en samitsomit moglichmöglich. •. DieDie BrennelementeBrennelemente wurden hauptsachlichhauptsächlich (zu(zu 96%)96y0) inin Deutschland Deutschland vonvon derder NUKEMNUKEM hergestellthergestellt, , lediglichlediglich derder HEU-AnteHEU-Anteil il (830(830 kg)kg) stammtstarnmt ausaus denden USA.USA. •. Wiewie eineeine unabhangigeunabhängige ExpertengruppeExpertengruppe 20142014 darlegte,darlegte, gabgab eses verschiedeneverschiedene UnfalleUntälle imimAVR, AVR, diedie Uberüber JahrzehnteJahrzehnte verschwiverschwiegen egen wowordenr den warewaren. n. DieDie BrennelemenBrennelemente te sindsind dahedaher r inin einem einem sehrsehr schschlechten lechten Zustand.Zustand. Ihrelhre WiederaufarbeiruWiederaufafbeitung ng wird vermutlic vermutlich h greBegroße MengenMengen sekundarensekundären MOMülls ils erzeugen,erzeugen, diedie diedie beabsichtigtebeabsichtigte SauberungSäuberung derder SRSSRS behindernbehindem dUrften.dürften. UngefahrUnge{ähr 4%4yo derder TTHTR-Brennelemente HTR-Brennelemente sind zerbrochen,zerbrochen, mitmit vermutlich Elhnlichenähnlichen Konsequenzen.Konsequenzen. •. DDieie deutschedeutsche Bundesregierung hathat inin den den vergangenen Jahren ottizielloffiziell erkJart,erklärt, dassdass es keine k€ine Planepläne fOr,für den ExportExport derder THTRTHlR-Brennelemente -Brennelemente inin die die USAUSAgäbe, gabe, sondern nurnur{ü. fOr die desdes AVR. Ausgehend von derderAnnahme, Annahme, dassdass die deutschedeutsche SeiteSeire nunnun dochdoch diedie UmweltvenraglichkeitsprUfungUmweltuenräglichkeitsprüfung desdes amerikanischenamerikanischen DOEDoE fOrfür die THTR-SrennelemenreTHTR-Brennelemente offizielloffiziell unterstUtzt,unterstützt, vermuten wir dassdass diedie deutschendeutschen EExDonolänex portplane fOrfür denden AVR-MOIIAVR-Müll nur derder€rste erste Schritt eines bkologischökolggisch hochsthöchst problematischenproblematischen Exports ailenallen deutschendeutscien AtommOllsAtommülls inin andere andere UinderLänder darstellt. EsEs gibt bereitsbereits entsprechendeentsprechende AnAngebotegebote durch RussRussland. land. DRAFT ENVIRONMENTALENVIROI{MEI{TAL ASSESSMENT I/ Umweltvertraglichkeltsstudle:Umwetwerträgtichkeitsstudiei http://energy.qoy/sjtes/prod/ftles/Z016{Ol!f28/Draft%20pOE%2OEA%2Q1977htto://energy,oov/sites/prod/fi les/2O16/0Uf 28lDraft y62ODOEo/62OEAy.2O1977 FOR %2QPUBUC.pdfo/"2OPUBLlC,pdf With my signature I support these comments against the DEA concerning the processing of German pebble bed NPP fuel elements at SRS_sRs, Nachname, Vorname Wohnort Untej;schriftUnterse$rift Name,prenameName, prename city / 104(natJre 1. ., -1' ----rn"' V (it"., ~'\0p'-l . I tuou*"L-.(L"~,,, 6~. ·\ (b . :l!A 2. i?(lQ<ti//tllh //;dtIlt/rle /vbt/,rysr/rlA/ocfcrsd;,./ -I- -J? I/J,;, 3. ~ .,..,?< C;tn~It(1l ;vclf"0Y/.4 ~t,,-ti g-~ 4. !llfQrq:l/l, II? ]7osOJ{,j M¥cc ktvsrloy/kktrlar v !J,-,rt? flY 5. v l,., 6. 7. 8. 9. 10. .. EineEme AKionAktlon des BündnissesBundnlsses gegen Castor-Exporte (Buegece), Zusammenschluss aus landes-landes- und bundesweiten Anti-Atom-lnitiativenAnti-Atom-Initiativen und dem BUND NRW www.bund-www.bund­ nrw.denrw.de www.westcastordewww.westcastor.d e BitteSine bis zumzum 01.03.201601.03.2016 anan den BUNDSUND NRW e.VeV senden:senden: MerowingerstraßeMeravvngerstrat:\e 88,88, 40225 40225 Düsseldorf,Dusseldorf, Fax:Fax : 0049 211 302005-26, V-i-S-d.P.:V.i.S.d.P.: Buegece,Buegece, c/oc/o Claudia Baitinger,Baitinger, fT OO4900492369242962369 24296 Claudia.Claudia.Baitinger@[email protected] .net Stand5tand 14.02.14 .02.16L6 Bsup101 2 AVRPC-055 undünd Fort Fon St. St Vrain HTGRHIGR fUrfür den THTR;lH-fR; diese Anlagen werden auch in den USA USAais als kommerzieliekomrier2ielle betrachtet. Die miserable m:serable Leistungsbilanz derdef deutschendeulschen KugelhaufenwReaktorenKugelitalfen-Reaktoren kann nicht als Argument gegen deren kommerzielle Intentionenirteniaonen di€nen:dienen: Sies,e waren kommerziellekotameziele Reaktoren!Reaktorer,l •. EsFs bestehtbosteht kein signifikantessigni:ikanles ProJiferations-RisikoProliferatiots-Risiko fOrfür dendenAVR-Müll, AVR-MOII, v.riewie verschiedene ve.schiedene Gutachtencutachten (z.B.{2.8. auchauch von NNSA, 2013) darlegen.daregen. 1mlm A1lgemeinenAllgemeinen enthEUterthält derdgr AVR-MUlIAVR-Mü! kein:<!:r HEU. Eine KonditionierungKondiaio!ierulC und Endlagerung Endlagerlng inan DeutschlandDe!tsciland warenwären somitsomit..öglich. mtiglich. •' Die BrenneJemente Brennelemente wurden haupts;1chlichhauptsächlich (zu(z! 960/0)96%0) in!r DeutschlandOeu:schland von der NUKEM Na.lX[M hergestellt, lediglichlediglich der HEU-AnteilHEu-Anteit (830 kg) stammt aus dende, USA. •. WieWe eine unabhangigeunabhänglge Expertengruppe 2014201.4 darlegte, gab es verschiedeneve.saliedene UnfaUnfälle lle im AVR, die Obera:rer JahrzehnteJahrzehrte verschwiegenveasciwiegen worden warenwaten. Die Brennelemente sind daher in einem sehrseir schlechtenschlecitel . Zustand.Zlstard. Ihrelhre WiederaufarbeitungWiederaufärteitung wirdwi.d vermutlichvelmutlich groBegroße Mengent\rengea] sekundarense,(rrdären MUllsN4ülls erzeugen,erzeuger, die die beabsichtigte SauberungSäuberung der SRS SiS behindernteiindern dOrften.dürtte.t. UngefahrUngefähr 4%40lo der THTR-Brennelemente tHtR-B.enre,ema.rle sind zerbrochen, mitmitvermutlich vermutlich ahnlichenähtlichen Konsequenzen. •. DieDle deutsche Bundesregierung hat i lnn den vergangenenvergangeren Jahren offizielloffizaell erklart,erklä.t, dass escs keinekeane Planepläne fUrfül den Export Exlo.t der THTRTHTR-Erennelemente -Brennelemente inin ddie ie USA gabe,gäbe, sondern nur fUrfür die des AVR.AVR, AusgehendAlsgeherd vonyon derderAnnahme, Annahme, dass died;e deutsche Seite nunl}ul dochdoci die UmweUmweltve.träglichkeitspritfungltvertraglichkeitsprUfung des amerikanischenamerikanischer DOEDOL fOrlür die THTR-BrennelementeTHlR-Btenre:emente offiziell unterstOtzt,.rnterstützt, vermuten wir dass die deutschen ExportplaneEX3or1lläne fOrlür den AVR-MOIIAVR-Müll nur derdet erstee.ste SchrittSch,itt eineseires okologischökologisch hochsthöchst problematischenproblema::schen ExportsExpons allen deutschen AtommOllsAtommülls in andere L.anderLairder darstellt.dafstellt. Es gibt bereitsberei:s entsprechende AngeboteArgebots durch Russland. DRAFT ENVIRONMENTALEI'IVIRONMEt'l:Ai- ASSESSMENTA,SSISSMENT I/ Umweltvertraglichkeitsstudie:Umw3llen.äglichkeitsstudie: http://energy.govhttp://enerov. gov/sites/orod/fi/sites/prod/ftles/2016/01lf28JOraft%2000E%2OEA%201977_FORtes/2016/O:f tSltraft%20DOEo/o20lAy":!1t?? :Cl %20PUBLlC.pdfoÄ2OPa,BLlC.odf With my signature I support these comments againstagainsa the DEADfA concerning.onc€rning the processing of German pebblepebb:e bed NPP fuelfu€l elements at SRSsRs., Nachname, Vorname WohnortWohatr: UnterschriftUnterschiift Name, prenameprenäme citycitv signaturesignatrrq-, 1 F"iubo-se,E.,-{ E>e.-(i^ e,Q/ 2. /Ja"t^ {, /L. ö ['-' lie 12 l)q'{ 3. (4,+ (L; rAr-^ Ä< t"r^ 0.,.r ).-,, 9ia** .Cu &,, a,Q;, 5. HiL4äül+,litJF 2 f,(Llrü /z// 6. (tt14. t9ake -kzt, /L' KA 7. .^-a\ ,.1-, ..) ,.- ::,.:, , r.a)rl\f ,\o;. .3u,/',, L $n<| Y,l .' .-, 'i e- 1,.^ z"\"4 L "^ (LhaLze tR<zg,ncc 3rri-i rr &Irz 10. "N-,"/u Rebel ,u,,loiffo.q L, -..4..,-i Eine ne Aktion des BOndnissesBündnisses ge'1engegien Castor-ExporteCaslor Exporte (Buegece).(Buegece), ZusammenschlussZJsanmenschluss aus landes-land€s-und bundesweiten Anti-Atom-lnit;ativenAnti-Atom-Initiativen und dem BUND BUN, NRWNXW www.bund­!r}rr.bund- nrw.de www.westcastor.de BitteBitta bis zum 01.03.2016 an den BUND NRW eVe.V senden: Merowingerstral>eMerowingersfaße 88, 40225 DUsseldorf,Düsseldorf, Fax: 0049 21121.1 302005-26, V.i.S.d.P.:V,i.5.d.P: Buegece, c/o Claudia ' Baitinger, TI 004923692429600492369 24296 [email protected]ä[email protected] Stand 14.02.16 2 Bsup102 AVRPC-055 und FortFortSt St Vrain Vmin HTGR fUrflrr den THTR; diesedieseAnlagen Anlagen werden auch inin den USAalsUsAals korrmerziellekomreziella betrachtetbetrdchbl Die niserablenisemble Leistungsbilanz der deutschendeubclen Kugelhaufen-ReaktorenKJgelhaufen-Reakbren kann nichtnichtals als ArgunErtgegenArgurrentgegen deren kO!TYTerziellekonrr€e ielle IntentionenInbntionen dienen:dieaen: Sie5ie t,€r€nwaren korrtrrerziellekcni.r€rziele Reaktoren!Reakb.enl •. Es bestehtbesiehi keinkdn signifikantes signäkantes ProlProliferdtons-Rjsiko iferations-Risiko fUrfü.denAVR-Müll, den AVR-Mull, wier,!i. verschiedener.€rs.hiedene GutachtenGu:äcaten (z.8.(2.8. auch von NNSA.NNSA, 2013) darlegen.därleg€n. ImAligemeinen!mAllgemeinen enthaltenthä:t derderAVR-Milll AVR-MOII kein HEU.hEU. Eine KondKondidonierung itionierung und E!ndlagerung ndlagerung in Deutschland
Recommended publications
  • KERNFORSCHUNGSANLA JULICH Gmbh
    KERNFORSCHUNGSANLA JULICH GmbH Proceedings of the Workshop on Structural Design Criteria for HTR Jiilich, 31. January - 1. February 1989 Editors: G. Breitbach F. Schubert H. Nickel Jiil-Conf-71 April 1989 ISSN 0344-5798 Als Manuskript gedruckt Berichte der Kernforschungsanlage Jülich - Jül-Conf-71 Zu beziehen durch: ZENTRALBIBLIOTHEK der Kernforschungsanlage Jülich GmbH Postfach 1913 • D-5170 Jülich (Bundesrepublik Deutschland) Telefon: 02461/610 • Telex: 833556-0 kf d Proceedings of the Workshop on Structural Design Criteria for HTR Jiilich, 31. January - 1. February 1989 Editors: G. Breitbach F. Schubert H. Nickel Workshop on Structural Design Criteria for HTR Introductural remarks Most of the presentations given in this workshop are based on the German research and development project "HTR Design Criteria" carried out under the sponsorship of the Federal Ministry of Research and Technology. The main emphasis of this work was to acquire the fundamental principles and basic data for the establishment of German KTA-rules (KTA: Nuclear Safety Standards Commission) for the design of HTR-structural components. The project began in 1984 and the research work divided among several working groups and task forces, with participation from several institutions and companies. The role of coordination has been carried out by the Institute for Reactor Materials, Nuclear Research Centre Julien, headed by Prof. Dr. H. Nickel. The work has been organized into four working groups: a) Technical safety boundary conditions; b) Metallic structural components; c) Prestressed concrete pressure vessel; d) Graphitic structural components. The required work in each group was divided between a number of task forces. The membership of each group and task force is given in the appendix.
    [Show full text]
  • Nuclear and Energy Independence
    Meetings ANS WINTER MEETING Nuclear and energy independence HILE ORGANIZATIONS HAVE canceled or altered conferences in W the wake of the events of Sep- Major themes of the plenary: tember 11, the American Nuclear Society at- tracted more than 1100 attendants to its Win- N ter Meeting in November in Reno, Nev. “In H2 power can be an application light of recent events, that is a remarkable ac- complishment,” ANS President Gail Marcus of nuclear commented during the opening plenary. The large gathering was due perhaps to the upbeat mood of the industry in general, thanks N 50 years since first electricity with EBR-I in part to the Bush administration’s support of the continued use and further deployment of N nuclear power, and because any hope for re- A proposal for a continental supergrid ducing greenhouse gas emissions likely would include nuclear power in a national energy policy. oring the EBR-I and the nuclear pioneers who was associate project director of the EBR-I During the plenary Marcus paraphrased developed it. The proclamation recognized the and project manager for another reactor, the Charles Dickens by saying, “It is the best of environmental benefits of nuclear power and EBR-II. He later became director of the Re- times, it is the worst of times,” in reference feted those who worked to provide the world actor Engineering Division at Argonne Na- to the terrorist attacks on the United States with “clean, sustainable energy for the bene- tional Laboratory before moving on to Illinois and the opportunity for nuclear power to fit of humankind for centuries by making use Power Company.
    [Show full text]
  • HTGR Dust Safety Issues and Needs for Research and Development
    INL/EXT-11-21097 HTGR Dust Safety Issues and Needs for Research and Development P. W. Humrickhouse June 2011 DISCLAIMER This information was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any agency thereof, nor any of their employees, makes any warranty, expressed 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. References herein to any specific commercial product, process, or service by trade name, trade mark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the U.S. Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the U.S. Government or any agency thereof. INL/EXT-11-21097 HTGR Dust Safety Issues and Needs for Research and Development P. W. Humrickhouse June 2011 Idaho National Laboratory Next Generation Nuclear Plant Project Idaho Falls, Idaho 83415 http://www.inl.gov Prepared for the U.S. Department of Energy Office of Nuclear Energy Under DOE Idaho Operations Office Contract DE-AC07-05ID14517 ABSTRACT This report presents a summary of high temperature gas-cooled reactor dust safety issues. It draws upon a literature review and the proceedings of the Very High Temperature Reactor Dust Assessment Meeting held in Rockville, MD in March 2011 to identify and prioritize the phenomena and issues that characterize the effect of carbonaceous dust on high temperature reactor safety.
    [Show full text]
  • Reactor Technology Safety and Siting
    XA0101477-5/I5* IAEA-TC-389.26 LIMITED DISTRIBUTION REACTOR TECHNOLOGY SAFETY AND SITING REPORT OF A TECHNICAL COMMITTEE MEETING ORGANIZED BY THE INTERNATIONAL ATOMIC ENERGY AGENCY AND HELD IN DIMITROVGRAD, USSR, 21-23 JUNE 1989 Reproduced by the IAEA Vienna, Austria, 1990 NOTE The material in this document has been supplied by the authors and has not been edited by the IAEA. The views expressed remain the responsibility of the named authors and do not necessarily reflect those of the govern- ments) of the designating Member State(s). In particular, neither the IAEA nor any other organization or body sponsoring this meeting can be held responsible for any material reproduced in this document. FOREWORD On the invitation of the Government of the Union of Soviet Socialist Republics, the Eleventh International Conference on the HTGR and the IAEA Technical Committee Meeting on Gas-Cooled Reactor Technology, Safety and Siting were held in Dimitrovgrad, USSR, on June 21-23, 1989. The meetings complemented each other. Due to the large worldwide interest, the conference attracted approximately 60 participants from 18 countries and 130 Soviet delegates. About 50 foreign participants and 100 Soviet delegates stayed over for the Technical Committee Meeting. The Technical Committee Meeting provided the Soviet delegates with an opportunity to display the breadth of their program on HTGR's to an international audience. Nearly one-half of the papers were presented by Soviet participants. Among the highlights of the meeting were the following: - The diverse nature and large magnitude of the Soviet research and development program on high temperature gas-cooled reactors.
    [Show full text]
  • Deployability of Small Modular Nuclear Reactors for Alberta Applications Report Prepared for Alberta Innovates
    PNNL-25978 Deployability of Small Modular Nuclear Reactors for Alberta Applications Report Prepared for Alberta Innovates November 2016 SM Short B Olateju (AI) SD Unwin S Singh (AI) A Meisen (AI) DISCLAIMER NOTICE This report was prepared under contract with the U.S. Department of Energy (DOE), as an account of work sponsored by Alberta Innovates (“AI”). Neither AI, Pacific Northwest National Laboratory (PNNL), DOE, the U.S. Government, nor any person acting on their behalf 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 AI, PNNL, DOE, or the U.S. Government. The views and opinions of authors expressed herein do not necessarily state or reflect those of AI, PNNL, DOE or the U.S. Government. Deployability of Small Modular Nuclear Reactors for Alberta Applications SM Short B Olateju (AI) SD Unwin S Singh (AI) A Meisen (AI) November 2016 Prepared for Alberta Innovates (AI) Pacific Northwest National Laboratory Richland, Washington 99352 Executive Summary At present, the steam requirements of Alberta’s heavy oil industry and the Province’s electricity requirements are predominantly met by natural gas and coal, respectively. On November 22, 2015 the Government of Alberta announced its Climate Change Leadership Plan to 1) phase out all pollution created by burning coal and transition to more renewable energy and natural gas generation by 2030 and 2) limit greenhouse gas (GHG) emissions from oil sands operations.
    [Show full text]
  • Exelon Generation Introduction to the Pebble Bed Modular Reactor
    Exekn.m Exelon Generation Telephone 610.765.5661 Generati on 200 Exelon Way Fax 610.765.5545 KSA3-N www.exeloncorp.com Kennett Square, PA 19348 Project No.: 713 August 30, 2001 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Subject: "Introduction to the Pebble Bed Modular Reactor" Dear Sir/Madam, a general Transmitted here with is a copy of the subject document, which provides presents an description of the Pebble Bed Modular Reactor (PBMR). This document safety analysis, and overview of the PBMR; the concept, the basic principles of design, operation. It is not intended to be used (or maintained) as a design document. Sincerely, Manager, Licensing PBMR Introduction to the Pebble Bed Modular Reactor (PBMR) Doc. No. 009949-185 PBMR Introduction to the Pebble Bed Modular Reactor (PBMR) Doc. No. 009949-1 85 INTRODUCTION TO THE PEBBLE BED MODULAR REACTOR (PBMR) DOCUMENT No.: 009949-185 Revision: 1 Document Status: Approved 1 Page 1 0179 ©@ Copyright 20012001 by PBMR 22/08/200122108/2001 Revision 1 Page 1 of 79 PBMVR Introduction to the Pebble Bed Modular Reactor (PBMR) Doc. No. 009949-185 CHANGE HISTORY Configuration Control Project: PBMR Title: Introduction to the Pebble Bed Modular Reactor (PBMR) Doc. Reference: 009949-185 Created By: A P George Creation Date: August 2001 Classification: Confidential Document History Revision History Revision Date Changes A August 2001 New document 1 August 2001 Document updated after review I Page 2of79 Q© Copyright 2001 byby PB3MRPBMR 22/08/200122108/2001 Revision I Page 2 of 79 PBMVR Introduction to the Pebble Bed Modular Reactor (PBMVR) Doc.
    [Show full text]
  • Granular Dynamics in Pebble Bed Reactor Cores
    Granular Dynamics in Pebble Bed Reactor Cores by Michael Robert Laufer A dissertation submitted in partial satisfaction of the requirements for the degree of Doctor of Philosophy in Engineering – Nuclear Engineering in the Graduate Division of the University of California, Berkeley Committee in Charge: Professor Per Peterson, Chair Professor Brian Wirth Professor Tarek Zohdi Dr. Robert Budnitz Spring 2013 Granular Dynamics in Pebble Bed Reactor Cores Copyright 2013 by Michael Robert Laufer Abstract Granular Dynamics in Pebble Bed Reactor Cores by Michael Robert Laufer Doctor of Philosophy in Engineering – Nuclear Engineering University of California, Berkeley Professor Per F. Peterson, Chair This study focused on developing a better understanding of granular dynamics in pebble bed reactor cores through experimental work and computer simulations. The work completed includes analysis of pebble motion data from three scaled experiments based on the annular core of the Pebble Bed Fluoride Salt-Cooled High- Temperature Reactor (PB-FHR). The experiments are accompanied by the development of a new discrete element simulation code, GRECO, which is designed to offer a simple user interface and simplified two-dimensional system that can be used for iterative purposes in the preliminary phases of core design. The results of this study are focused on the PB-FHR, but can easily be extended for gas-cooled reactor designs. Experimental results are presented for three Pebble Recirculation Experiments (PREX). PREX 2 and 3.0 are conventional gravity-dominated granular systems based on the annular PB-FHR core design for a 900 MWth commercial prototype plant and a 16 MWth test reactor, respectively. Detailed results are presented for the pebble velocity field, mixing at the radial zone interfaces, and pebble residence times.
    [Show full text]
  • Annual Report 2015 Forschungszentrum Jülich at a Glance Contents
    Annual Report 2015 Forschungszentrum Jülich at a glance Contents U 2 Facts and Figures 0 2 Highlights 0 4 Board of Directors 0 5 Preface 0 6 60 Years of Research R e s e a r c h at the Centre 22 Climate Research Climate goals. Climate Records. Climate Models. 1 4 Chronology 28 Nanoelectronics Insights into the Resistance Generation 32 Energy Research Breaking New Ground in the Hydrogen World 36 Materials Research The Slipperiness Formula 38 Structural Biochemistry New Light Switch for Nerve Cells 40 Electron Tomography Nanoworld in 3D 42 Brain Research Changes in the Brain Caused by Depression 44 Climate Research A Chance Discovery for Climate Research 46 Computer Simulation The Birth of Elements 48 Materials Research New Steel for Energiewende 5 0 Research in Brief 5 2 Publications Cooperation 5 4 The Computer Diplomat 5 8 International Cooperations (EU) 59 National Cooperations 6 0 Collaborations with Industry 6 1 JARA – Combined Expertise 6 4 Cooperations in Brief 6 8 Research for Practical Applications 7 0 Patents and Licenses P e o p l e 7 2 The Tinkerer and the Networker 7 4 Promoting Young Talent 8 2 Personnel 8 4 Accolades 8 6 Professorial Appointments Campus 8 8 Strategy Process of Forschungszentrum Jülich 98 Finances 9 0 Jülich’s Sustainable Campus 1 0 2 Bodies and Committees 9 1 Excellent Platforms 1 0 4 Organization Chart 9 4 Work at Other Locations 1 0 6 Contact Information/ Publication Details U3 Impressions from 60 Years of Research Forschungszentrum Jülich Annual Report 2015 1 Highlights 2015 Forschungszentrum Jülich is focused on use-inspired basic research.
    [Show full text]
  • Preliminary Failure Modes and Effects Analysis of the US DCLL Test Blanket Module
    INL/EXT-07-13115 Preliminary Failure Modes and Effects Analysis of the US DCLL Test Blanket Module Lee C. Cadwallader August 2007 The INL is a U.S. Department of Energy National Laboratory operated by Battelle Energy Alliance INL/EXT-07-13115 Preliminary Failure Modes and Effects Analysis of the US DCLL Test Blanket Module Lee C. Cadwallader August 2007 Idaho National Laboratory Advanced Nuclear Energy Systems Department Idaho Falls, Idaho 83415 Prepared for the U.S. Department of Energy Office of Fusion Energy Sciences Under DOE Idaho Operations Office Contract DE-AC07-05ID14517 ABSTRACT This report presents the results of a preliminary failure modes and effects analysis (FMEA) of a small tritium-breeding test blanket module design for the International Thermonuclear Experimental Reactor. The FMEA was quantified with “generic” component failure rate data, and the failure events are binned into postulated initiating event families and frequency categories for safety assessment. An appendix to this report contains repair time data to support an occupational radiation exposure assessment for test blanket module maintenance. iii iv CONTENTS ABSTRACT.................................................................................................................................................iii ACRONYMS................................................................................................................................................ 1 1. INTRODUCTION.............................................................................................................................
    [Show full text]
  • The High Temperature Gas-Cooled Reactor
    The High Temperature Gas-cooled Reactor Safety considerations of the (V)HTR-Modul Kugeler, K., Nabielek, H., Buckthorpe, D. Editors: Scheuermann, W., Haneklaus, N., Fütterer, M. 2017 EUR 28712 EN KJ - NA - 28712 - EN - C This publication is a Book with editorship by the Joint Research Centre (JRC), the European Commission’s science and knowledge service. It aims to provide evidence-based scientific support to the European policymaking process. The scientific output expressed does not imply a policy position of the European Commission. Neither the European Commission nor any person acting on behalf of the Commission is responsible for the use that might be made of this publication. Contact information Name: Fütterer, M. Address: European Commission, DG Joint Research Centre – JRC, Directorate G, Unit G.I.4 – Nuclear Reactor Safety & Emergency Preparedness; P.O. Box 2, NL-1755 ZG Petten, Netherlands Email: [email protected] Tel.: +31 22456-5158 JRC Science Hub https://ec.europa.eu/jrc JRC107642 EUR 28712 EN PDF ISBN 978-92-79-71311-8 ISSN 1831-9424 doi:10.2760/270321 Print ISBN 978-92-79-71312-5 ISSN 1018-5593 doi:10.2760/970340 Luxembourg: Publications Office of the European Union, 2017 © European Atomic Energy Community, 2017 Reuse is authorised provided the source is acknowledged. The reuse policy of European Commission documents is regulated by Decision 2011/833/EU (OJ L 330, 14.12.2011, p. 39). For any use or reproduction of photos or other material that is not under the EU copyright, permission must be sought directly from the copyright holders.
    [Show full text]
  • R. HÜPER Fast Breeder Project, Kernforschungszentrum Karlsruhe
    STATUS OF FAST BREEDER REACTOR DEVELOPMENT 500 °C. After several years of operation with a thermal reactor core (KNK I), IN THE FEDERAL REPUBLIC OF GERMANY, the plant has been run with fast, i.e. unmoderated, reactor cores since 1978 (KNK II). BELGIUM AND THE NETHERLANDS February 1987* While the fuel assemblies of the first fast core, KNK II/l, were identical with those of the Mk.Ia first core of the SNR 300 in their key parameters, the fuel assemblies of the second core loading, KNK 11/2 , correspond to the SNR 300 Mk.II R. HÜPER type, which is characterized by a high fuel density, 7.6 mm fuel rod diameter, Fast Breeder Project, and spark eroded spacer grids which, in the fuel assemblies of the test zone, Kernforschungszentrum Karlsruhe GmbH, are attached to the wrapper tube by means of flow aprons. Karlsruhe, Federal Republic of Germany The first fast core had been unloaded in 1982 after a peak burnup of 100.000 MWd/te. The fuel assemblies of the second core, which was commissioned iri mid-1983, have meanwhile reached an average burnup of 47.000 MWd/te. One test Abstract fuel assembly transferred from the first to the second core has reached an average burnup of 125.000 MWd/te by late 1986. In 1967 and 1968, the Federal Republic of Germany, the Kingdom of Belgium, and the Kingdom of the Netherlands ("DeBeNe") agreed in a joint program to develop In the course of the burnup of the second core so far, a change in the outlet breeder reactors.
    [Show full text]
  • Core Physics of Pebble Bed High Temperature Nuclear Reactors
    Core Physics of High Temperature Pebble Bed Nuclear Reactors Pebble of High Temperature Physics Core Uitnodiging Voor het bijwonen van de openbare Core Physics of Pebble Bed verdediging van het proefschrift High Temperature Core Physics of Nuclear Reactors Pebble Bed High Temperature Nuclear Reactors Gert Jan Auwerda door Gert Jan Auwerda 22 december 12:30 Aula, TU Delft, Mekelweg 5 Gert Jan Auwerda Voorafgaand, om 12:00, is een presentatie over het onderzoek Faculty of Applied Sciences Department of Radiation Science & Technology Faculty: Applied Sciences Department: RS&T ISBN 978-94-6295-047-4 Group: NERA Propositions accompanying the dissertation CORE PHYSICSOF PEBBLE BED HIGH TEMPERATURE NUCLEAR REACTORS by Gert Jan AUWERDA 1. Non-isotropic models are required to accurately simulate heat and mass transfer next to the wall in a pebble bed reactor. (This thesis.) 2. In a pebble bed reactor, the higher porosity near the boundaries than in the centre of the randomly stacked pebble bed can be ignored when calculating the neutron flux distribution, but cannot be ignored when calculating the ke f f or the power distribution. (This thesis.) 3. In annular pebble bed designs, the wall-channelling effect results in a significantly lower maximum fuel temperature during both normal operation and during a pres- surized loss of forced cooling accident. (This thesis.) 4. A grid convergence study based on Richardson extrapolation to evaluate the grid convergence index (GCI) should be mandatory to evaluate the mesh quality when solving equations using numerical analysis. (P.J.Roache. Verification and validation in com- putational science and engineering, Hermosa Publishers, USA, 1998.) 5.
    [Show full text]