Accuracy of criticality calculations made using current nuclear data libraries for MOX fuelled fast critical assemblies

被引:4
|
作者
Rowlands, J. L.
机构
[1] Dorchester, Dorset DT1 2DA
关键词
MOX fuelled fast reactor criticality; JEFF-3.1; JEFF-3.1.1; JENDL-3.3; ENDF/B-VII.0; JENDL-3.3;
D O I
10.1016/j.anucene.2010.07.016
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Criticality calculations have been made for a set of ten mixed plutonium-uranium oxide (MOX) fuelled fast critical assemblies using the current nuclear data libraries, JEFF-3.1, JEFF-3.1.1, JENDL-3.3 and ENDF/B-VII.0. The results obtained using the different libraries are compared and conclusions drawn concerning the accuracy of criticality calculations made for MOX fuelled fast reactors. (c) 2010 Elsevier Ltd. All rights reserved.
引用
收藏
页码:1666 / 1673
页数:8
相关论文
共 22 条
  • [1] A SYSTEMATIC STUDY OF ACCURACY OF MULTIGROUP CRITICALITY CALCULATIONS FOR FAST CRITICAL ASSEMBLIES
    BAKER, AR
    JOURNAL OF THE BRITISH NUCLEAR ENERGY SOCIETY, 1967, 6 (03): : 249 - &
  • [2] Analysis of Libraries of Evaluated Nuclear Data Using the Example of Calculations of Np-237 Sphere Criticality
    Khassan, A. A.
    Dikova, T. S.
    Afanasyev, V. V.
    PHYSICS OF PARTICLES AND NUCLEI LETTERS, 2024, 21 (02) : 201 - 206
  • [3] CALCULATIONS OF FAST CRITICAL ASSEMBLIES USING LASL AND ENDF/B VERSION II DATA
    HIRONS, TJ
    BATTAT, ME
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1971, 14 (01): : 348 - &
  • [4] Criticality safety benchmark calculations using the new evaluated data libraries
    Degtyarev, I. I.
    Maslov, V. M.
    INTERNATIONAL CONFERENCE ON NUCLEAR DATA FOR SCIENCE AND TECHNOLOGY, VOL 2, PROCEEDINGS, 2008, : 865 - +
  • [5] Benchmark Calculations for Reflector Effect in Fast Cores by Using the Latest Evaluated Nuclear Data Libraries
    Fukushima, M.
    Ishikawa, M.
    Numata, K.
    Jin, T.
    Kugo, T.
    NUCLEAR DATA SHEETS, 2014, 118 : 405 - 409
  • [6] Nuclear data checking for plutonium isotopes in experiments at fast critical assemblies
    Bednyakov, S.M.
    Dulin, V.A.
    Manturov, G.N.
    Mozhaev, V.K.
    Semenov, M.Yu.
    Tsibulya, A.M.
    Atomnaya Energiya, 1996, 80 (06): : 454 - 461
  • [7] CALCULATIONS OF FAST CRITICAL ASSEMBLIES USING ENDF-B-4 CROSS-SECTION DATA
    HIRONS, TJ
    SEAMON, RE
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1975, 22 (NOV16): : 722 - 722
  • [8] MONTE CARLO EIGENVALUE CALCULATIONS OF FAST CRITICAL ASSEMBLIES USING VIM-1
    LEVITT, LB
    LEWIS, RC
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1970, 13 (01): : 194 - &
  • [9] Nuclear criticality safety aspects of the utilization of weapons-grade plutonium in MOX fuel using current BNFL technology
    Farrington, LM
    Broome, PE
    SAFETY ISSUES ASSOCIATED WITH PLUTONIUM INVOLVEMENT IN THE NUCLEAR FUEL CYCLE, 1999, 23 : 65 - 76
  • [10] An analysis of the nuclear data libraries' impact on the criticality computations performed using Monte Carlo codes
    Gugiu, ED
    Ellis, RJ
    Dumitrache, I
    Constantin, M
    INTERNATIONAL CONFERENCE ON NUCLEAR DATA FOR SCIENCE AND TECHNOLOGY, PTS 1 AND 2, 2005, 769 : 1423 - 1426