Development of ceramics-coated particle fuel for very high-temperature gas-cooled reactors

被引：0

作者：

Japan Atomic Energy Agency, Narita-cho, Oarai-machi, Ibaraki 311-1394, Japan ^{[1
]}

机构：

来源：

Trans. At. Energy Soc. Jpn. | 1600年 / 2卷 / 113-125期

关键词：

Theoretical; (THR); -; Experimental; (EXP);

D O I：

暂无

中图分类号：

学科分类号：

摘要：

Gas cooled reactors

引用

共 50 条

[41] STRENGTH OF PYROLYTIC SIC COATINGS OF FUEL PARTICLES FOR HIGH-TEMPERATURE GAS-COOLED REACTORS
EVANS, AG
PADGETT, C
DAVIDGE, RW
JOURNAL OF THE AMERICAN CERAMIC SOCIETY, 1973, 56 (01) : 36 - 41
[42] 2-DIMENSIONAL MODELING OF THE FUEL ASSEMBLIES OF HIGH-TEMPERATURE GAS-COOLED REACTORS
SEGAL, MD
KHRIPUNOV, VI
SOVIET ATOMIC ENERGY, 1979, 46 (02): : 129 - 131
[43] HEAD-ENG SEPARATION OF FUEL PARTICLES FOR HIGH-TEMPERATURE GAS-COOLED REACTORS
LANGER, S
BALDWIN, NL
PHILLIPS, HR
ABSTRACTS OF PAPERS OF THE AMERICAN CHEMICAL SOCIETY, 1971, (NSEP): : 19 - &
[44] THERMOHYDRAULIC PERFORMANCE OF NEW TYPE OF FUEL BLOCK FOR HIGH-TEMPERATURE GAS-COOLED REACTORS
TAKANO, M
SAWA, K
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1986, 23 (02) : 176 - 178
[45] FUEL CYCLE IN GAS-COOLED HIGH-TEMPERATURE REACTOR
MERZ, E
CHEMIKER-ZEITUNG, 1977, 101 (02): : 81 - 91
[46] Development of a physics analysis procedure for the prismatic very high temperature gas-cooled reactors
Kim, Kang-Seog
Cho, Jin-Young
Lee, Hyun Chul
Noh, Jae Man
Zee, Sung Quun
ANNALS OF NUCLEAR ENERGY, 2007, 34 (11) : 849 - 860
[47] Fuel development for gas-cooled fast reactors
Meyer, M. K.
Fielding, R.
Gan, J.
JOURNAL OF NUCLEAR MATERIALS, 2007, 371 (1-3) : 281 - 287
[48] DEVELOPMENT + UTILIZATION OF PYROLYITC-CARBON-COATED CARBIDE FUEL FOR HIGH-TEMPERATURE GAS-COOLED REACTOR
GOEDDEL, WV
NUCLEAR SCIENCE AND ENGINEERING, 1964, 20 (02) : 201 - &
[49] EMERGENCY CORE COOLING FOR HIGH-TEMPERATURE GAS-COOLED REACTORS
GOODJOHN, AJ
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1968, 11 (01): : 258 - &
[50] 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 - &

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