Concept Design of Supercritical Water Cooled Reactor Core with Double-Row-Rod Assemblies

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Concept Design of Supercritical Water Cooled Reactor Core with Double-Row-Rod Assemblies

更新时间：2025-07-09

- Concept Design of Supercritical Water Cooled Reactor Core with Double-Row-Rod Assemblies
- Vol. 46, Issue 9, Pages: 78-82(2012)
- 作者机构：
  
  中科华核电技术研究院,广东,深圳,518026
- 作者简介：
- 基金信息：
- DOI：
  CLC： TL421
- Online First：10 September 2012，
  
  Published：2012
- 稿件说明：
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Concept Design of Supercritical Water Cooled Reactor Core with Double-Row-Rod Assemblies[J]. 2012, 46(9): 78-82.
DOI：

Concept Design of Supercritical Water Cooled Reactor Core with Double-Row-Rod Assemblies[J]. 2012, 46(9): 78-82. DOI：

摘要

结合国际上多种超临界水堆堆芯设计方案的优点

提出了一种新的压力容器式低泄漏堆芯设计方案

其特点是

堆芯中采用了双排棒正方形闭式燃料组件和三区低泄漏换料.双排棒燃料组件由两排燃料棒包围一个慢化剂水棒构成

可以使得慢化均匀; 三区低泄漏换料可以大大延长堆芯寿期

降低压力容器快中子注量.通过堆芯三维物理热工耦合计算发现

该方案寿期内的最大包壳温度(MCST)为684 ℃

堆芯寿期为300个有效满功率天

且功率分布平坦.在此基础上

对所有组件进行了更为保守的子通道热工水力计算

得出MCST为685.3 ℃

进一步表明所提堆芯设计方案在物理热工方面是可行的.

Abstract

A new pressure-vessel type supercritical water cooled reactor(SCWR)core concept was proposed by combining merits of several SCWR core designs in the world. This core design employs a new type of closed assembly with double-row fuel rods in square geometry and a three-batch low-leakage refueling scheme. The assembly consists of two rows of fuel rods and a moderator rod

which causes the moderation more uniform. The three-batch low leakage refueling scheme obviously increases the cycle length and reduces the neutron fluence on the pressure vessel. Three-dimensional neutronics/thermohydraulics coupling calculation shows that the maximum cladding surface temperature(MCST)is 684 ℃

the cycle life is 300 effective full power days and the power distribution is flat. Then the more conservative sub-channel analysis was performed for all fuel assemblies. The MCST was evaluated to be 685.3 ℃

showing that the core design is feasible.

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Keywords

references

OKA Y, KOSHIZUKA S. Design concept of once-through cycle supercritical pressure light water cooled reactors [C]∥Proceedings of Supercritical Cooled Reactors. Tokyo,Japan: University of Tokyo, 2000:1-22.

CAO L, OKA Y, ISHIWATARI Y, et al. Fuel, core design and subchannel analysis of a super fast reactor[J]. J Nucl Sci Technol, 2008, 45(2):138-148.

SCHULENBERG T, STARFLINGER J, MARSAULT P, et al. European supercritical water cooled reactor [J]. Nucl Eng Des, 2011, 241(9):3503-3513.

BAE Y, JANG J, KIM H, et al. Research activities on a supercritical pressure water reactor in Korea [J]. Nucl Eng Technol, 2007, 39(4):273-286.

DUFFEY R, SUR B. Towards a sustainable future using pressure tube reactor technology[J]. Energy Procedia, 2011, 7:286-292.

刘晓晶. 混合能谱超临界水冷堆堆芯热工与物理性能的研究 [D].上海:上海交通大学, 2010.

李昌莹. 超临界水堆子通道分析 [D].西安:西安交通大学, 2008.

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