LMFBR FUEL ROD DESIGN USING MONTE-CARLO TECHNIQUES

被引：0

作者：

ATCHESON, DB ^{[1
]}

TEMME, M ^{[1
]}

ORR, G ^{[1
]}

机构：

[1] GE,SUNNYVALE,CA 94086

来源：

TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY | 1972年 / 15卷 / 01期

关键词：

D O I：

暂无

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：

引用

页码：182 / &

共 50 条

[21] COMMENTS ON ADJOINT MONTE-CARLO SAMPLING TECHNIQUES
LEVITT, LB
SPANIER, J
NUCLEAR SCIENCE AND ENGINEERING, 1970, 42 (01) : 118 - &
[22] HYBRID MONTE-CARLO TECHNIQUES WITH A MINIMAL INTERFACE
JERMANN, WH
THOMAS, RC
CALHOUN, MD
SIMULATION, 1971, 17 (06) : 225 - +
[23] MONTE-CARLO TECHNIQUES IN MEDICAL RADIATION PHYSICS
ANDREO, P
PHYSICS IN MEDICINE AND BIOLOGY, 1991, 36 (07) : 861 - 920
[24] OBSERVED CLADDING RESPONSE TO LMFBR FUEL ROD DESIGN PARAMETERS
ROSA, JM
HILBERT, RF
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1976, 23 (JUN18): : 147 - 147
[25] LMFBR FUEL ROD DESIGN LIMITS AND TRANSIENT SURVIVAL CRITERIA
CARELLI, MD
ANDERSON, CA
MARKLEY, RA
NUCLEAR ENGINEERING INTERNATIONAL, 1972, 17 (188): : 43 - &
[26] A DETERMINATION OF RELATIVISTIC SHOCK JUMP CONDITIONS USING MONTE-CARLO TECHNIQUES
ELLISON, DC
REYNOLDS, SP
ASTROPHYSICAL JOURNAL, 1991, 378 (01) : 214 - 226
[27] LMFBR FUEL ROD DESIGN LIMITS AND TRANSIENT SURVIVAL CRITERIA
CARELLI, MD
ANDERSON, CA
MARKLEY, RA
ATOMWIRTSCHAFT, 1971, 16 (02): : 84 - &
[28] A New Coupling CFD/Monte-Carlo Neutron Transport Scheme, Application to a Single Fuel Rod Problem
Henry, Romain
Tiselj, Iztok
23RD INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE, (NENE 2014), 2014,
[29] Determination of burnup limit for CANDU 6 fuel using Monte-Carlo method
Lee, Eun-ki
NUCLEAR ENGINEERING AND TECHNOLOGY, 2021, 53 (03) : 901 - 910
[30] NEUTRONIC ANALYSIS CODE FOR FUEL ASSEMBLY USING A VECTORIZED MONTE-CARLO METHOD
MORIMOTO, Y
MARUYAMA, H
ISHII, K
AOYAMA, M
NUCLEAR SCIENCE AND ENGINEERING, 1989, 103 (04) : 351 - 358

← 1 2 3 4 5 →