Integrity assessment of the high temperature engineering test reactor (HTTR) control rod at very high temperatures

被引:8
作者
Tachibana, Y
Shiozawa, S
Fukakura, J
Matsumoto, F
Araki, T
机构
[1] TOSHIBA CO LTD,HEAVY APPARATUS ENGN LAB,TSURUMI KU,YOKOHAMA,KANAGAWA 230,JAPAN
[2] TOSHIBA CO LTD,KEIHIN PROD OPERAT,NUCL ENERGY EQUIPMENT MFG DEPT,TSURUMI KU,YOKOHAMA,KANAGAWA 230,JAPAN
[3] TOSHIBA CO LTD,NUCL ENERGY GRP,ADV REACTOR ENGN DEPT,ISOGO KU,YOKOHAMA,KANAGAWA 230,JAPAN
关键词
D O I
10.1016/S0029-5493(97)00030-7
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 [核科学与技术]; 082701 [核能科学与工程];
摘要
The high temperature engineering test reactor (HTTR) is the first high temperature gas-cooled reactor (HTGR) in Japan with a reactor outlet coolant temperature of 950 degrees C at high temperature test operation. The HTTR contains 16 pairs of control rods for which Alloy 800H is chosen of the metallic parts. Because the maximum temperature of the control rods reaches about 900 degrees C at reactor scrams, structural design guideline and design material data on Alloy 800H are needed for the high temperature design. The design guideline for the HTTR control rod is based on ASME Code Case N-47-21. Design material data is also determined and shown in this paper. Under the guideline, temperature and stress analysis was conducted, and it is confirmed that the target life of the control rods of 5 years can be achieved. (C) 1997 Elsevier Science S.A.
引用
收藏
页码:93 / 102
页数:10
相关论文
共 14 条
[1]
*AM SOC MECH ENG, 1981, ASME BOIL PRESS VESS
[2]
EDWARDS AL, 1972, UCRL14754 LAWR LIV L
[3]
FUKAKURA J, 1991, T JPN SOC MECH ENG, V57, P1700
[4]
Hirano M., 1990, 90071 JAERIM
[5]
*JAERI, 1992, PRES STAT HTGR RES D
[6]
*JAERI, 1996, PRES STAT HTGR RES D
[7]
MARUYAMA S, 1990, 90104 JAERIM
[8]
MONMA Y, 1984, T NATL RES I MET, V26, P33
[9]
NISHIGUCHI I, 1990, 90152 JAERIM
[10]
*NRIM, 1983, 27A NRIM