THE FORT-ST-VRAIN HIGH-TEMPERATURE GAS-COOLED REACTOR .4. RISE TO POWER TEST PROGRAM

被引：1

作者：

OLSON, HG

BREY, HL

SWART, FE

机构：

[1] PUBL SERV CO COLORADO,FT ST VRAIN NUCL GENERAT STN,PLATTEVILLE,CO 80651

[2] PUBL SERV CO COLORADO,DENVER,CO 80201

来源：

NUCLEAR ENGINEERING AND DESIGN | 1980年 / 61卷 / 03期

关键词：

D O I：

10.1016/0029-5493(80)90001-1

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：295 / 302

页数：8

共 50 条

[1] THE FORT-ST-VRAIN HIGH-TEMPERATURE GAS-COOLED REACTOR .9. RISE-TO-POWER PHYSICS TESTS
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[J]. NUCLEAR ENGINEERING AND DESIGN, 1983, 76 (01) : 71 - 77
[2] FORT-ST-VRAIN HIGH-TEMPERATURE GAS-COOLED REACTOR .2. HELIUM CIRCULATORS
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[J]. NUCLEAR ENGINEERING AND DESIGN, 1979, 53 (01) : 125 - 131
[3] FORT-ST-VRAIN HIGH-TEMPERATURE GAS-COOLED REACTOR .3. HELIUM CIRCULATOR AUXILIARIES
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[J]. NUCLEAR ENGINEERING AND DESIGN, 1979, 53 (01) : 133 - 140
[4] FORT-ST-VRAIN HIGH-TEMPERATURE GAS-COOLED REACTOR .1. LOW-POWER PHYSICS TESTS
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[J]. NUCLEAR ENGINEERING AND DESIGN, 1979, 53 (01) : 117 - 123
[5] THE FORT-ST-VRAIN HIGH-TEMPERATURE GAS-COOLED REACTOR .5. STEAM SYSTEM PERFORMANCE TESTS
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[J]. NUCLEAR ENGINEERING AND DESIGN, 1980, 61 (03) : 303 - 314
[6] ANALYSIS AND RESULTS OF PULSED-NEUTRON EXPERIMENTS PERFORMED ON FORT-ST-VRAIN HIGH-TEMPERATURE GAS-COOLED REACTOR
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[J]. NUCLEAR TECHNOLOGY, 1975, 27 (03) : 352 - 375
[7] THE FORT-ST-VRAIN HIGH-TEMPERATURE GAS-COOLED REACTOR .6. EVALUATION AND REMOVAL OF PRIMARY COOLANT CONTAMINANTS
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[J]. NUCLEAR ENGINEERING AND DESIGN, 1980, 61 (03) : 315 - 322
[8] THE FORT-ST-VRAIN HIGH-TEMPERATURE GAS-COOLED REACTOR .11. CONTROL ROD DRIVE AND ORIFICE ASSEMBLIES
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[J]. NUCLEAR ENGINEERING AND DESIGN, 1980, 61 (03) : 323 - 329
[9] IRRADIATION PERFORMANCE OF FORT-ST-VRAIN HIGH-TEMPERATURE GAS-COOLED REACTOR-FUEL IN CAPSULE F-30
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