Transient analyses for lead-bismuth cooled accelerator-driven system

被引：11

作者：

Sugawara, Takanori ^{[1
]}

Nishihara, Kenji ^{[1
]}

Tsujimoto, Kazufumi ^{[1
]}

机构：

[1] Japan Atom Energy Agcy, Tokai, Ibaraki 3191195, Japan

来源：

ANNALS OF NUCLEAR ENERGY | 2013年 / 55卷

关键词：

Accelerator-Driven System (ADS); Transient analysis; Loss of heat sink; Lead-bismuth eutectic (LBE); SIMMER-III; RELAP5/mod3.2; NEUTRONICS DESIGN; SIMMER-III; TRANSMUTATION; PROGRAM; CODE; ADS;

D O I：

10.1016/j.anucene.2012.12.016

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 transient analyses for the lead-bismuth cooled Accelerator-Driven System (ADS) were performed with the use of the SIMMER-III and RELAP5/mod3.2 codes to investigate the possibility of the core damage. Five accidents; the beam window breakage, the protected loss of heat sink, the beam overpower, the unprotected loss of flow and the unprotected blockage accident were analyzed as the typical accidents in the ADS. Through these calculations, it was confirmed that all calculation results except the protected loss of heat sink satisfied the no-damage criteria. In the protected loss of heat sink, the cladding tube temperature reached at the melting temperature after 20 h although the calculation condition was very conservative. It is required to design a safety system of the ADS to decrease the frequencies of the accidents and to ease the accidents. (C) 2012 Elsevier Ltd. All rights reserved.

引用

页码：238 / 247

页数：10

共 21 条

[1] Thermal-hydraulics analyses of ELSY lead fast reactor with open square core option [J].

Bandini, Giacomino ;

Meloni, Paride ;

Polidori, Massimiliano .

NUCLEAR ENGINEERING AND DESIGN, 2011, 241 (04) :1165-1171

[2]

CROFF AG., 1980, ORNL5621

[3] Development of general-purpose particle and heavy ion transport Monte Carlo code [J].

Iwase, H ;

Niita, K ;

Nakamura, T .

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2002, 39 (11) :1142-1151

[4]

JAEA Nuclear Data Center homepage, DEC HEAT TABL REC AT

[5]

Japan Atomic Energy Agency, 2006, 2006042 JAEA

[6] Transient analyses of the 400MWth-class EFIT accelerator driven transmuter with the multi-physics code: SIMMER-III [J].

Liu, Ping ;

Chen, Xuenong ;

Rineiski, Andrei ;

Maschek, Werner .

NUCLEAR ENGINEERING AND DESIGN, 2010, 240 (10) :3481-3494

[7] Safety aspects of oxide fuels for transmutation and utilization in accelerator driven systems [J].

Maschek, W ;

Rineiski, A ;

Suzuki, T ;

Mori, MG ;

Chen, X ;

Flad, M .

JOURNAL OF NUCLEAR MATERIALS, 2003, 320 (1-2) :147-155

[8]

Maschek W., 2000, P INT TOP M NUCL APP

[9] Thermal Conductivities of Zr-based Transuranium Nitride Solid Solutions [J].

Nishi, Tsuyoshi ;

Takano, Masahide ;

Ichise, Kenichi ;

Akabori, Mitsuo ;

Arai, Yasuo .

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2011, 48 (03) :359-365

[10] Neutronics design of Accelerator-Driven System for power flattening and beam current reduction [J].

Nishihara, Kenji ;

Iwanaga, Kohei ;

Tsujimoto, Kazufumi ;

Kurata, Yuji ;

Oigawa, Hiroyuki ;

Iwasaki, Tomohiko .

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2008, 45 (08) :812-822

← 1 2 3 →