Using the neutron balance method to access the feed fuel requirements for CANDLE

Kun YANG; Jingen CHEN; Xiangzhou CAI

doi:10.11889/j.0253-3219.2016.hjs.39.060601

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Using the neutron balance method to access the feed fuel requirements for CANDLE

NUCLEAR ENERGY SCIENCE AND ENGINEERING | 更新时间：2021-05-24

- Using the neutron balance method to access the feed fuel requirements for CANDLE
- NUCLEAR TECHNIQUES Vol. 39, Issue 6, Article number: 060601(2016)
- 作者机构：
  
  1.中国科学院上海应用物理研究所嘉定园区上海 201800
  2.中国科学院大学北京 100049
- 作者简介：
- 基金信息：
- DOI：10.11889/j.0253-3219.2016.hjs.39.060601
  CLC： TL329.2
- Received：09 March 2016，
  
  Revised：21 March 2016，
  
  Published：2016-06
- 稿件说明：
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Kun YANG, Jingen CHEN, Xiangzhou CAI. Using the neutron balance method to access the feed fuel requirements for CANDLE[J]. Nuclear techniques, 2016, 39(6): 060601
DOI：

Kun YANG, Jingen CHEN, Xiangzhou CAI. Using the neutron balance method to access the feed fuel requirements for CANDLE[J]. Nuclear techniques, 2016, 39(6): 060601 DOI： 10.11889/j.0253-3219.2016.hjs.39.060601.

摘要

寿期内中子通量、核素浓度和功率分布的轴向形状均保持恒定(Constant Axial shape of Neutron flux

nuclide densities and power shape During Life of Energy produced

CANDLE)是实现原位增殖-焚烧(Breed-and-Burn

#38;B)模式的一种燃耗策略。CANDLE堆经易裂变燃料或外中子源进行点火

启动后由增殖燃料的燃烧实现自稳运行。若要CANDLE堆自稳运行于

eff

必须对堆芯几何及燃料体积分数进行配置优化。最优配置方案可通过蒙特卡罗方法模拟CANDLE堆芯

根据有效增殖因子筛选得出。但该方法需耗费大量的计算时间

若采用1D模型近似模拟

并结合中子平衡方法进行分析

便可大幅节约计算时间

获得具有指导性意义的结果。本文将论证该方法的可行性

并应用该方法估算钠冷贫铀CANDLE堆半径在100-400 cm、燃料体积分数在35%-60%变化时的最优配置。

Abstract

Background

CANDLE (Constant Axial shape of Neutron flux

nuclide densities and power shape During Life of Energy produced) is a burnup strategy for Breed-and-Burn (B&B) reactors in which the effective neutron multiplication factor at an equilibrium state is equal to unity. The radius and fuel volume fraction of such a core play a very important role in the B&B mode of operation. However

using the Monte Carlo method to model a full CANDLE core for optimization costs too much computational effort and time.

Purpose

This study aims to assess the validity of neutron balance analysis with a simplified 1D model for determination of the maximum burnup (

) attainable in a CANDLE mode

and then apply this 1D methodology to optimize the configurations of feed fuel and core radii for a sodium-cooled core to sustain the CANDLE mode.

Methods

When the maximum achievable BU of feed fuel equals the maximum burnup of the CANDLE feed fuel at equilibrium state

the

eff

value of the core is equal to unity. The neutron balance method with the 1D approach for various core radii and fuel volume fractions of feed fuel can provide a quick way to scope the optimized configuration.

Results

Neutron balance analysis with the 1D approach can provide a reasonable estimation of the maximum attainable BU of feed fuel in a CANDLE reactor

despite a small inaccuracy due to the spectrum difference between the 1D and the full core models. A small size of core and a low fuel volume fraction of feed fuel display a small value of the maximum attainable BU

which implies that it is disadvantageous to sustain a CANDLE mode. However

a too big size of core or high fuel volume fraction of feed fuel may lead to

eff

1 at equilibrium state. With the above considerations and optimization

we present a suitable core geometry and its fuel fraction to ensure the stable B

#38;B mode of operation at equilibrium state (

eff

=1).

Conclusion

The neutron balance calculation with 1D approach can save much computational time

and the optimized configurations of feed fuel to sustain a CANDLE mode are proposed based on this methodology.

关键词

Keywords

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