Neutronic analysis code for fuel assembly using a vectorized Monte Carlo method

被引：0
|
作者：
机构：
[1] Morimoto, Yuuichi
[2] Maruyama, Hiromi
[3] Ishii, Kazuya
[4] Aoyama, Motoo
来源：
Morimoto, Yuuichi | 1600年 / 103期
关键词：
Neutrons;
D O I：
暂无
中图分类号：
学科分类号：
摘要：
引用
收藏
相关论文
共 50 条
  • [11] A VECTORIZED MONTE-CARLO CODE FOR MODELING PHOTON TRANSPORT IN SPECT
    SMITH, MF
    FLOYD, CE
    JASZCZAK, RJ
    MEDICAL PHYSICS, 1993, 20 (04) : 1121 - 1127
  • [12] A vectorized Monte Carlo code for radiotherapy treatment planning dose calculation
    Weng, XJ
    Yan, YL
    Shu, HZ
    Wang, JW
    Jiang, SB
    Luo, LM
    PHYSICS IN MEDICINE AND BIOLOGY, 2003, 48 (07): : N111 - N120
  • [13] Modeling and neutronic analysis of pin-cell comprising nuclear fuel with different chemical composition and neutron moderator using Monte Carlo code OpenMC
    Reza, Farshid
    Sahadath, Md Hossain
    Akter, Yasmin
    ANNALS OF NUCLEAR ENERGY, 2021, 151
  • [14] Modeling and neutronic analysis of pin-cell comprising nuclear fuel with different chemical composition and neutron moderator using Monte Carlo code OpenMC
    Reza, Farshid
    Sahadath, Md. Hossain
    Akter, Yasmin
    Annals of Nuclear Energy, 2021, 151
  • [15] 3-Dimensional full core neutronic analysis for uranium nitride fuel CANDLE reactor using Monte Carlo MCNP6 code
    Afifah, Maryam
    Su'ud, Zaki
    Trianti, Nuri
    Irwanto, Dwi
    NUCLEAR ENGINEERING AND DESIGN, 2024, 425
  • [16] IMPROVEMENT OF VECTORIZED MONTE-CARLO METHOD FOR NEUTRON-TRANSPORT ANALYSIS
    ISHII, K
    MARUYAMA, H
    MORIMOTO, Y
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1989, 26 (10) : 966 - 969
  • [17] Modeling the consequences of fuel assembly bowing on PWR core neutronics using a Monte-Carlo code
    de Lambert, Stanislas
    Campioni, Guillaume
    Faucher, Vincent
    Leturcq, Bertrand
    Cardolaccia, Jerome
    ANNALS OF NUCLEAR ENERGY, 2019, 134 : 330 - 341
  • [18] Calculation of time-dependent neutronic parameters using Monte Carlo method
    Shayesteh, M.
    Shahriari, M.
    ANNALS OF NUCLEAR ENERGY, 2009, 36 (07) : 901 - 909
  • [19] Comparisons of deterministic neutronic calculations with Monte Carlo results for an advanced BWR fuel assembly with hafnium control blades
    Plaschy, Michael
    Jatuff, Fabian
    Grimm, Peter
    Tani, Filippo
    Jacot-Guillarmod, Roland
    Giust, Flavio
    Krouthen, Jan
    Chawla, Rakesh
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2006, 43 (11) : 1298 - 1310
  • [20] A DISCRETE SAMPLING METHOD FOR VECTORIZED MONTE-CARLO CALCULATIONS
    BROWN, FB
    MARTIN, WR
    CALAHAN, DA
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1981, 38 (JUN): : 354 - 355
12345