EVALUATION OF CORE THERMAL AND HYDRAULIC CHARACTERISTICS OF HTTR

被引：15

作者：

MARUYAMA, S

FUJIMOTO, N

SUDO, Y

MURAKAMI, T

FUJII, S

机构：

[1] JAPAN ATOM ENERGY RES INST,DEPT REACTOR ENGN,TOKAI,IBARAKI 31911,JAPAN

[2] FUJI ELECT CO LTD,DIV NUCL POWER,KAWASAKI,KANAGAWA,JAPAN

[3] KAWASAKI HEAVY IND CO LTD,DEPT ENGN,TOKYO,JAPAN

来源：

NUCLEAR ENGINEERING AND DESIGN | 1994年 / 152卷 / 1-3期

关键词：

D O I：

10.1016/0029-5493(94)90084-1

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：

Japan Atomic Energy Research Institute has started the development of the high temperature engineering test reactor (HTTR), a graphite-moderated, helium gas-cooled reactor with 30 MW thermal power and maximum outlet coolant temperature of 950 degrees C. This paper describes the core thermal and hydraulic (T/H) design procedure, including the validation of the computer code system, design criteria pertaining to the fuel design limit and the evaluated core T/H charateristics. The core T/H design of the HTTR has been carried out considering the specific characteristics of the core structure and the fuel based on R&D results. The coolant flow rate and temperature distribution are evaluated by the flow network analysis code FLOWNET. The fuel temperature distribution is evaluated by the fuel temperature analysis code TEMDIM with multi-cylindrical model using hot spot factors. Fuel design limit for anticipated operational occurrences and fuel temperature limit for normal operation are specified at 1600 degrees C and 1495 degrees C, respectively based on experimental results. Several design considerations are also adopted to realize a high reactor outlet coolant temperature of 950 degrees C. As a result of core T/H design, the effective core flow rate and maximum fuel temperature during the high temperature test operation are 88% and 1492 degrees C, respectively.

引用

页码：183 / 196

页数：14

共 15 条

[1]

FUJIMOTO N, P SNA 90 MITO, P92

[2]

FUJIMOTO N, 1988, JAERIM88187 REP

[3]

HAYASHI K, 1989, JAERIM89162 REP

[4]

KABURAKI H, 1988, J NUCL SCI TECHNOL, V25, P92, DOI [10.3327/jnst.25.92, 10.1080/18811248.1988.9733559]

[5] RESEARCH ON CROSS-FLOW IN VHTR CORE .2. NUMERICAL-ANALYSIS OF 2-BLOCK CROSS-FLOW [J].

KABURAKI, H ;

TAKIZUKA, T ;

HASHIMOTO, K .

JOURNAL OF THE ATOMIC ENERGY SOCIETY OF JAPAN, 1985, 27 (05) :450-456

[6]

KOBAYASHI T, 1978, FAPIG, V88, P12

[7] EVALUATION OF HOT-SPOT FACTORS FOR THERMAL AND HYDRAULIC DESIGN OF HTTR [J].

MARUYAMA, S ;

YAMASHITA, K ;

FUJIMOTO, N ;

MURATA, I ;

SUDO, Y ;

MURAKAMI, T ;

FUJII, S .

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1993, 30 (11) :1186-1194

[8]

MARUYAMA S, 1988, JAERIM88170 REP

[9]

MARUYAMA S, 1988, JAERIM88138 REP

[10]

MELESE G., 1984, THERMAL FLOW DESIGN

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