Comparison of burnup calculation results using several evaluated nuclear data files

被引：8
|
作者：
Suyama, K
Katakura, J
Kiyosumi, T
Kaneko, T
Nomura, Y
机构：
[1] Japan Atom Energy Res Inst, Tokai Res Establishment, Dept Fuel Cycle Safety Res, Naka, Ibaraki 3191195, Japan
[2] Japan Atom Energy Res Inst, Tokai Res Establishment, Nucl Data Ctr, Naka, Ibaraki 3191195, Japan
[3] Japan Res Inst, Energy Technol Dept, Chiyoda Ku, Tokyo 1020082, Japan
来源：
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY | 2002年 / 39卷 / 01期
关键词：
JENDL-3.2; ENDF/B-VI; JEF-2.2; burn-up calculations; SWAT; cross section library; calculated amount; fuel cycle; comparison of cross section; chain analysis; comparative evaluations;
D O I：
10.3327/jnst.39.82
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：
BUM-LIP calculation and comparison of the results were carried out to clarify the differences among the following latest evaluated nuclear data libraries: JENDL-3.2. ENDF/B-VI and JEF-2.2. The analyses showed that the differences seen among the current evaluated nuclear data libraries are small for evaluation of the amounts of many uranium and plutonium isotopes. However, several nuclides important for evaluation of nuclear fuel cycle as Pu-238, Cm-244, Sm-149 and Cs-134 showed large differences among used libraries. The chain analyses for the isotopes were conducted and the reasons for the differences were discussed. Based on the discussion. information of important cross section to obtain better agreement with the experimental results for Pu-238, Cm-244, Sm-149 and Cs-134 was shown.
引用
收藏
页码：82 / 89
页数：8
相关论文
共 50 条
  • [31] Comparison of the Signal Level Calculation Results Using Numerical Solution of Parabolic Equation with Experimental Data for the Transhorizon Paths
    Zakharov, F. N.
    Akulinichev, Yu. P.
    Anikin, A. S.
    Krutikov, M. V.
    2015 INTERNATIONAL SIBERIAN CONFERENCE ON CONTROL AND COMMUNICATIONS (SIBCON), 2015,
  • [32] Calculations of spent fuel isotopic composition for fuel rod from VVER-440 fuel assembly benchmark using several evaluated nuclear data libraries
    Blandinskiy, V. Yu
    Dudnikov, A. A.
    KERNTECHNIK, 2018, 83 (04) : 325 - 330
  • [33] Development of a fast reactor multigroup cross section generation code EXUS-F capable of direct processing of evaluated nuclear data files
    Lim, Changhyun
    Joo, Han Gyu
    Yang, Won Sik
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2018, 50 (03) : 340 - 355
  • [34] Comparison of the results of theoretical calculation of transport coefficients of potassium vapor with experimental data
    Kuznetsova, OD
    Semenov, AM
    HIGH TEMPERATURE, 1999, 37 (01) : 52 - 57
  • [35] 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
  • [36] Validation of CENDL and JEFF evaluated nuclear data files for TRIGA calculations through the analysis of integral parameters of TRX and BAPL benchmark lattices of thermal reactors
    Uddin, M. N.
    Sarker, M. M.
    Khan, M. J. H.
    Islam, S. M. A.
    ANNALS OF NUCLEAR ENERGY, 2009, 36 (10) : 1521 - 1526
  • [37] The Reservoir Parameter Calculation Method Using The Nuclear Magnetic Resonance Log Data
    Cao, Gang
    Hou, Jiagen
    Zou, Jingyun
    Dong, Yue
    Xu, Zhaohui
    Ma, Xiaoqiang
    Song, Suihong
    Yang, Wenze
    2015 11TH INTERNATIONAL CONFERENCE ON NATURAL COMPUTATION (ICNC), 2015, : 588 - 593
  • [38] Calculation of dose coefficients for radionuclides produced in a spallation neutron source utilizing nubase and the evaluated nuclear structure data file databases
    Shanahan, J
    Eckerman, K
    Arndt, A
    Gold, C
    Patton, P
    Rudin, M
    Brey, R
    Gesell, T
    Rusetski, V
    Pagava, S
    HEALTH PHYSICS, 2006, 90 (01): : 56 - 65
  • [39] Re-evaluation of Assay Data of Spent Nuclear Fuel obtained at Japan Atomic Energy Research Institute for validation of burnup calculation code systems
    Suyama, Kenya
    Murazaki, Minoru
    Ohkubo, Kiyoshi
    Nakahara, Yoshinori
    Uchiyama, Gunzo
    ANNALS OF NUCLEAR ENERGY, 2011, 38 (05) : 930 - 941
  • [40] Wall gas slot curtain on plate. Comparison of calculation results with experimental data
    Lushchik, V.G.
    Yakubenko, A.E.
    Izvestiya Akademii Nauk. Mekhanika Zhidkosti I Gaza, 1997, (06): : 48 - 63
12345