Short design descriptions of other systems of the HTTR

被引：14

作者：

Sakaba, N ^{[1
]}

Furusawa, T ^{[1
]}

Kawamoto, T ^{[1
]}

Ishii, Y ^{[1
]}

Oota, Y ^{[1
]}

机构：

[1] Japan Atom Energy Res Inst, Oarai Res Estab, Dept HTTR Project, Oarai, Ibaraki 3111394, Japan

来源：

NUCLEAR ENGINEERING AND DESIGN | 2004年 / 233卷 / 1-3期

关键词：

D O I：

10.1016/j.nucengdes.2004.08.024

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：

The HTTR mainly consists of the core components, reactor pressure vessel, cooling systems, instrumentation and control systems, and containment structures. The design of remaining utility systems is described in this paper. They are: auxiliary helium systems, which include the helium purification system, the helium sampling system, the helium storage and supply system; fuel handling and storage system. The helium purification systems are installed in the primary and secondary helium cooling systems in order,to reduce the quantity of chemical impurities. The helium sampling systems monitor the concentration of impurities. The helium storage and supply systems keep the steady pressure of the helium system during the normal operation. The fuel handling and storage system is utilised to handle the new- and spent-fuels safely and reliably. (C) 2004 Elsevier B.V. All rights reserved.

引用

页码：147 / 154

页数：8

共 8 条

[1] Cooling system design and structural integrity evaluation [J].

Furusawa, T ;

Shinozaki, M ;

Hamamoto, S ;

Oota, Y .

NUCLEAR ENGINEERING AND DESIGN, 2004, 233 (1-3) :113-124

[2] COOLING PERFORMANCE OF HELIUM-GAS WATER-COOLERS IN HENDEL [J].

INAGAKI, Y ;

TAKADA, S ;

HAYASHI, H ;

KOBAYASHI, T ;

OHTA, Y ;

SHIMOMURA, H ;

MIYAMOTO, Y .

NUCLEAR ENGINEERING AND DESIGN, 1994, 146 (1-3) :301-309

[3]

Iyoku T, 2004, NUCL ENG DES, V233, P71, DOI 10.1016/j.nucengdes.2004.07.0l2

[4]

NAKAGAWA S, 1997, P IAEA S INT SAF 13

[5] Instrumentation and control system design [J].

Saito, K ;

Sawahata, H ;

Homma, F ;

Kondo, M ;

Mizushima, T .

NUCLEAR ENGINEERING AND DESIGN, 2004, 233 (1-3) :125-133

[6]

Saito S, 1994, 1332 JAERI

[7] Leak-tightness characteristics concerning the containment, structures of the HTTR [J].

Sakaba, N ;

Iigaki, K ;

Kondo, M ;

Emori, K .

NUCLEAR ENGINEERING AND DESIGN, 2004, 233 (1-3) :135-145

[8] Reactor pressure vessel design of the high temperature engineering test reactor [J].

Tachibana, Y ;

Nakagawa, S ;

Iyoku, T .

NUCLEAR ENGINEERING AND DESIGN, 2004, 233 (1-3) :103-112

← 1 →