Preliminary design on core physics of medium-size modular lead-cooled fast reactor M<sup>2</sup>LFR-1000

Yongsong ZHAO; Haitao FANG; Xilin ZHANG; Xingbin ZHOU; Qin ZENG; Hongli CHEN

doi:10.11889/j.0253-3219.2018.hjs.41.100606

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Preliminary design on core physics of medium-size modular lead-cooled fast reactor M²LFR-1000

NUCLEAR ENERGY SCIENCE AND ENGINEERING | 更新时间：2021-05-19

- Preliminary design on core physics of medium-size modular lead-cooled fast reactor M²LFR-1000
- NUCLEAR TECHNIQUES Vol. 41, Issue 10, Article number: 100606(2018)
- 作者机构：
  
  中国科学技术大学合肥 230027
- 作者简介：
- 基金信息：
  
  Anhui Natural Science Foundation of China
- DOI：10.11889/j.0253-3219.2018.hjs.41.100606
  CLC： TL31
- Received：19 November 2017，
  
  Revised：07 May 2018，
  
  Published：10 October 2018
- 稿件说明：
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Yongsong ZHAO, Haitao FANG, Xilin ZHANG, et al. Preliminary design on core physics of medium-size modular lead-cooled fast reactor M²LFR-1000[J]. Nuclear techniques, 2018, 41(10): 100606
DOI：

Yongsong ZHAO, Haitao FANG, Xilin ZHANG, et al. Preliminary design on core physics of medium-size modular lead-cooled fast reactor M²LFR-1000[J]. Nuclear techniques, 2018, 41(10): 100606 DOI： 10.11889/j.0253-3219.2018.hjs.41.100606.

摘要

铅冷快堆运行温度高、压力低，冷却剂化学惰性好并具有优良的热力学特性，在发电、嬗变等方面拥有不可替代的优势。基于此，中国科学技术大学提出了一种中型模块化铅冷快堆（M

LFR-1000）方案，在SRAC/COREBN软件包提供堆芯不同燃耗深度下燃耗核素核子密度的基础上，采用蒙特卡罗程序MCNP（Monte Carlo N Particle Transport Code）进行堆芯物理初步设计和燃耗分析。结果表明：M

LFR-1000堆芯功率分布平坦，反应性控制系统合理，堆芯寿期达到设计要求，同时具有良好的固有安全性。此外，通过嬗变评估，表明M

LFR-1000堆芯具有良好的次锕系核素嬗变性能。

Abstract

Background

The Lead-cooled fast reactor (LFR) features high operation temperature

low-pressure and chemically inert liquid lead with good thermodynamic properties as coolant

hence it has an irreplaceable advantage in production of electricity and consuming actinides from spent pressurized water reactor (PWR) fuel.

Purpose

This study aims to explore preliminary design on core physics of the 1 000 MW (thermo) medium-size modular lead-cooled fast reactor (M

LFR-1000) proposed by University of Science and Technology of China (USTC).

Methods

After obtaining the atom density of the nuclides at different burn-up levels by using SRAC/COREBN code

the Monte Carlo code MCNP (Monte Carlo N Particle Transport Code) was employed to conduct the preliminary neutronic design of the core and burn-up analysis.

Results

The results of calculations cover the core power distribution

reactivity coefficient

neutron kinetic parameters

control rod worth and core lifetime. Especially

the capability of M

LFR-1000 core to transmute minor actinides was evaluated.

Conclusions

Results show that the M

LFR-1000 core scheme is reasonable

satisfies the design requirements and has excellent capability to transmute Minor Actinides.

关键词

Keywords

references

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Preliminary design on core physics of medium-size modular lead-cooled fast reactor M2LFR-1000

DOI：10.11889/j.0253-3219.2018.hjs.41.100606

摘要

Abstract

关键词

Keywords

references

Preliminary design on core physics of medium-size modular lead-cooled fast reactor M²LFR-1000