FEW-GROUP EQUATIONS OF REACTOR KINETICS

被引：0

|

作者：

SABAEV, EF

SABAEVA, TA

机构：

来源：

SOVIET ATOMIC ENERGY | 1990年 / 68卷 / 01期

关键词：

D O I：

10.1007/BF02069716

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：

[No abstract available]

引用

收藏

页码：12 / 16

页数：5

相关论文

共 50 条

[21] INTERFACE CONDITIONS FOR FEW-GROUP NEUTRON DIFFUSION EQUATIONS WITH FLUX-ADJOINT WEIGHTED CONSTANTS
BUSLIK, AJ
NUCLEAR SCIENCE AND ENGINEERING, 1968, 32 (02) : 233 - &
[22] AUTOMATED PREPARATION OF NEUTRON PHYSICS FEW-GROUP PARAMETERS TO BE USED IN MACROSCOPIC COMPUTATIONS OF THERMAL REACTOR CORES
AGTHE, G
KRETZSCHMAR, HJ
KERNENERGIE, 1990, 33 (04): : 165 - 170
[23] CONSISTENT VS CONVENTIONAL FEW-GROUP REACTIVITY CALCULATIONS
GREENSPAN, E
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1967, 10 (02): : 583 - +
[24] DEVELOPMENT AND VERIFICATION OF A FEW-GROUP PARAMETERS CALCULATION CODE TMSR-LINK FOR MOLTEN SALT REACTOR
Wang, Kailong
Cui, Yong
Zou, Chunyan
Chen, Jingen
Cai, Xiangzhou
PROCEEDINGS OF 2024 31ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 10, ICONE31 2024, 2024,
[25] Building neutron cross-section dependencies for few-group reactor calculations using stepwise regression
Zimin, VG
Semenov, AA
ANNALS OF NUCLEAR ENERGY, 2005, 32 (01) : 119 - 136
[26] FEW-GROUP CONSTANTS FOR FAST-REACTOR CALCULATIONS OF KEFF AND DELTA-(1-KEFF)
SVARNY, J
JADERNA ENERGIE, 1977, 23 (06): : 201 - 207
[27] ADDITIONAL FEW-GROUP AND MULTIGROUP CALCULATIONS OF NEUTRON PENETRATION
SHURE, K
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1974, 18 (JUN23): : 367 - 368
[28] FLUX-ADJOINT WEIGHTED FEW-GROUP CROSS-SECTIONS USED FOR REACTOR TRANSIENT ANALYSIS
KIM, MH
HENRY, AF
NUCLEAR SCIENCE AND ENGINEERING, 1989, 103 (03) : 276 - 282
[29] INFLUENCE OF SPECTRAL DISTURBANCES ON MACROSCOPIC FEW-GROUP PARAMETERS
AGTHE, G
KERNENERGIE, 1986, 29 (11): : 409 - 413
[30] REDUCTION OF FEW-GROUP DIFFUSION-THEORY TO ONE EQUIVALENT GROUP
WOOLLEY, JA
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1971, 14 (02): : 671 - &

← 1 2 3 4 5 →