DESIGN AND DEVELOPMENT OF A STEAM-TURBINE DRIVEN CIRCULATOR FOR HIGH-TEMPERATURE GAS-COOLED REACTORS

被引：7

作者：

CAVALLARO, L ^{[1
]}

YAMPOLSKY, J ^{[1
]}

机构：

[1] GULF GEN ATOM CO, SAN DIEGO, CA 92138 USA

来源：

NUCLEAR ENGINEERING AND DESIGN | 1974年 / 26卷 / 01期

关键词：

D O I：

10.1016/0029-5493(74)90050-8

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：135 / 157

页数：23

共 50 条

[21] STRUCTURAL GRAPHITE FOR HIGH-TEMPERATURE GAS-COOLED REACTORS
VIRGILIEV, YS
AVRAMENKO, PY
GREBENNIK, VN
KALYAGINA, IP
LEBEDEV, IG
FILIMONOV, VA
SHURSHAKOVA, TN
ENERGY, 1991, 16 (1-2) : 309 - 315
[22] Brayton cycle for high-temperature gas-cooled reactors
Oh, CH
Moore, RL
NUCLEAR TECHNOLOGY, 2005, 149 (03) : 324 - 336
[23] THE SAFETY OF MODULAR HIGH-TEMPERATURE GAS-COOLED REACTORS
KASTEN, PR
NUCLEAR ENGINEERING AND DESIGN, 1992, 137 (02) : 171 - 180
[24] HIGH-TEMPERATURE GAS-COOLED REACTORS FOR PROCESS HEAT
QUADE, RN
POWER ENGINEERING, 1973, 77 (04) : 50 - 53
[25] Status of high-temperature gas-cooled reactor development and design
Mears, L.D., 1600, (31):
[26] DESIGN OF COATED-PARTICLE FUEL FOR HIGH-TEMPERATURE GAS-COOLED REACTORS
GOEDDEL, WV
SCOTT, JL
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1967, 10 (01): : 168 - &
[27] Supercritical steam generator design of modular high-temperature gas-cooled reactor
Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100081, China
不详
Yuanzineng Kexue Jishu, 2006, 6 (707-713):
[28] EMERGENCY CORE COOLING FOR HIGH-TEMPERATURE GAS-COOLED REACTORS
GOODJOHN, AJ
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1968, 11 (01): : 258 - &
[29] EVALUATION OF PLUTONIUM USE IN HIGH-TEMPERATURE GAS-COOLED REACTORS
KASTEN, PR
BENNETT, LL
THOMAS, WE
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1971, 14 (01): : 88 - &
[30] FUEL-ELEMENTS FOR HIGH-TEMPERATURE GAS-COOLED REACTORS
HAMMER, RL
COOBS, JH
SCOTT, JL
ROBBINS, JM
CARBON, 1972, 10 (03) : 347 - &

← 1 2 3 4 5 →