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Enhancing TRU burning and Am transmutation in Advanced Recycling Reactor
Authors:Kazumi Ikeda  Richard A Kochendarfer  Shigeru Kunishima
Affiliation:a Mitsubishi FBR Systems, Inc., 34-17, Jingumae 2-Chome, Shibuya-ku, Tokyo 150-0001, Japan
b AREVA Federal Services LLC, 3315 Old Forest Road Lynchburg, VA 24501, USA
c Mitsubishi Heavy Industries, Ltd., 1-1, 16-5, Konan 2-Chome, Minato-ku, Tokyo 108-8215, Japan
Abstract:This paper presents about conceptual designs of Advanced Recycling Reactor (ARR) focusing on enhancement in transuranics (TRU) burning and americium (Am) transmutation. The design has been conducted in the context of the Global Nuclear Energy Partnership (GNEP) seeking to close nuclear fuel cycle in ways that reduce proliferation risks, reduce the nuclear waste in the US and further improve global energy security. This study strives to enhance the TRU burning and the Am transmutation, assuming the development of related technologies in this study, while the ARR based on mature technologies was designed in the previous study. It has followed that the provided TRU burning core is designed to burn TRU at 28 kg/TWthh, by adding moderator pins of B4C (Enriched B-11) and the Am transmutation core will be able to transmute Am at 34 kg/TWthh, by locating Am blanket of AmN around the TRU burning core. It indicates that these concepts improve TRU burning by 40-50% than the previous core and can transmute Am effectively, keeping the void reactivity acceptable.
Keywords:AAA  Advanced Accelerator Applications  ABTR  Advanced Burning Test Reactor  ADS  Accelerator Driven System  AFCI  Advanced Fuel Cycle Initiative  AFCF  Advanced Fuel Cycle Facility  ANL  Argonne National Laboratory  ARR  Advanced Recycling Reactor  ASTRID  Advanced Sodium Technological Reactor for Industrial Demonstration  ATW  Accelerator Transmutation of Waste  BCR  backup control rod  BR  breeding ratio  CAPRA  Consommation Accrue de Plutonium dans les Rapides  meaning increased consumption of plutonium in fast reactors  CEA  Commissariat à  l&rsquo  É  nergie Atomique  CR  conversion ratio  CRF  Consolidated Recycling Facility  DOE  Department of Energy  dpa  displacement per atom  EFPD  effective full power days  FAIDUS  Fuel Assembly with Inner Duct Structure  FBR  fast breeder reactor  FCA  Fast Critical Assembly  FFTF  Fast Flux Test Facility  FR  fast reactor  GEM  Gas Expansion Module  GNEP  Global Nuclear Energy Partnership  HCDA  hypothetical core disruptive accident  HM  heavy metal  INL  Idaho National Laboratory  INPRO  International Project on Innovative Nuclear Reactors and Fuel Cycles  JAEA  Japan Atomic Energy Agency  JSFR  Japan Sodium cooled Fast Reactor  MA  minor actinoid  MHI  Mitsubishi Heavy Industries  Ltd    MLHR  maximum linear heat rate  MOTA  Material Open Test Assembly  MOX  mixed(U  Pu)oxide  ULOF  unprotected loss of flow  UNF  used nuclear fuel  ODS  oxide dispersion strengthened (steel)  OMEGA  Options Making Extra Gains from Actinides and fission products  PCR  primary control rod  P-T  partitioning and transmutation  RIA  reactivity initiated accident  SFR  sodium cooled fast reactor  SPIN  Separation and Incineration  TRU  transuranics  NA  the Avogadro's number  u  unified atomic mass unit  UNF  used nuclear fuel
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