Preliminary transient thermal-hydraulic analysis for new coated UN and UC fuel options in SCWR

被引：19

作者：

Zhao, Hao ^{[1
]}

Zhu, Dahuan ^{[1
]}

Chaudri, Khurrum Saleem ^{[1
]}

Qiu, Suizheng ^{[1
]}

Tian, Wenxi ^{[1
]}

Su, Guanghui ^{[1
]}

机构：

[1] Xi An Jiao Tong Univ, Sch Nucl Sci & Technol, Xian 710049, Peoples R China

来源：

PROGRESS IN NUCLEAR ENERGY | 2014年 / 71卷

关键词：

SCWR; Thermal hydraulic; Transient analysis; Nuclear fuel; Uranium nitride (UN); Uranium carbide (UC); LIGHT-WATER REACTOR; SUPERCRITICAL-PRESSURE; CORE DESIGN; CYCLE;

D O I：

10.1016/j.pnucene.2013.11.008

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：

When UO2 is used for SCWRs, the fuel centerline temperature might exceed the conservatively established industry accepted limit of 1850 degrees C because of low thermal conductivity of UO2 within the operating temperature range of Super Critical Water-cooled Reactors (SCWRs). In our previous study, Neutronic/thermal hydraulic coupled analyses are performed for a new advanced fuel design for SCWR. Uranium nitride (UN) coated with Zirconium carbide (ZrC) and uranium carbide (UC) coated with Silicon carbide (SiC) are proposed as advanced fuel option compared with traditional UO2. The present work is a further investigation aiming to evaluate the transient thermal-hydraulic behaviors for coated UN and UC fuel options. The coated UN, UC and traditional UO2 fuel are selected for the transient analysis. Typical transients of SCWR including partial loss of flow accident and reactivity insertion accident by decrease in feedwater temperature are performed. The TACOS code, which was developed for SCWR safety analysis in Xi'an Jiaotong University, is used in this study. The comparison of the transient thermal hydraulic characteristics is carried out between UO2 and the new coated fuels. The present transient studies cooperating with previous coupled neutronics/thermal hydraulic analyses reveal that coated UN and UC have good thermal behaviors in high temperature reactor like SCWR, much more work in other aspects needs to be done. (C) 2013 Elsevier Ltd. All rights reserved.

引用

页码：152 / 159

页数：8

共 34 条

[1] Studies on supercritical water reactor fuel assemblies using the sub-channel code COBRA-EN [J].

Ammirabile, Luca .

NUCLEAR ENGINEERING AND DESIGN, 2010, 240 (10) :3087-3094

[2]

[Anonymous], 2008, INT ATOMIC ENERGY AG

[3] Thermal and stability considerations for a supercritical water-cooled fast reactor with downward-flow channels during power-raising phase of plant startup [J].

Cai, Jiejin ;

Ishiwatari, Yuki ;

Ikejiri, Satoshi ;

Oka, Yoshiaki .

NUCLEAR ENGINEERING AND DESIGN, 2009, 239 (04) :665-679

[4] A mixed core for supercritical water-cooled reactors [J].

Cheng, Xu ;

Liu, Xiao-Jing ;

Yang, Yan-Hua .

NUCLEAR ENGINEERING AND TECHNOLOGY, 2008, 40 (02) :117-126

[5] Conceptual fuel channel designs for CANDU-SCWR [J].

Chow, Chun K. ;

Khartabil, Hussam F. .

NUCLEAR ENGINEERING AND TECHNOLOGY, 2008, 40 (02) :139-146

[6]

Dell R.M., 1967, T FARADAY SOC, V63

[7] Long operation life reactor for lunar surface power [J].

El-Genk, Mohamed S. ;

Schriener, Timothy M. .

NUCLEAR ENGINEERING AND DESIGN, 2011, 241 (06) :2339-2352

[8]

Grande L C., 2010, Thermal Aspects of Using Alternative Nuclear Fuels in Super-critical Water-cooled Reactor Faculty of Energy Systems and Nuclear Science, P131

[9] Safety analysis of a supercritical-pressure water-cooled fast reactor under supercritical pressure [J].

Ikejiri, Satoshi ;

Ishiwatari, Yuki ;

Oka, Yoshiaki .

NUCLEAR ENGINEERING AND DESIGN, 2010, 240 (05) :1218-1228

[10] Safety of Super LWR, (II) - Safety analysis at supercritical pressure [J].

Ishiwatari, Y ;

Oka, Y ;

Koshizuka, S ;

Yamaji, A ;

Liu, J .

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2005, 42 (11) :935-948

← 1 2 3 4 →