Review of uncertainty analysis in sodium-cooled fast reactor systems

Zhe ZHANG; Yi CHEN; Desheng JIN; Tianhao WU; Hanhong ZHAO; Chao JIANG

doi:10.11889/j.0253-3219.2025.hjs.48.250188

NUCLEAR TECHNIQUES, Volume. 48, Issue 7, 070007(2025)

Review of uncertainty analysis in sodium-cooled fast reactor systems

Zhe ZHANG¹, Yi CHEN¹, Desheng JIN², Tianhao WU¹, Hanhong ZHAO², and Chao JIANG^1、*

Author Affiliations

¹College of Mechanical and Vehicle Engineering, Hunan University, Changsha 410082, China

²China Nuclear Power Technology Research Institute Co., Ltd., Shenzhen 518000, China

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Table 1. Information on sodium-cooled fast reactors of the world's major nuclear energy countries^[5]

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Table 1. Information on sodium-cooled fast reactors of the world's major nuclear energy countries^[5]

国家Country	反应堆Reactor	功率Power	类型Type	运行时间Runtime
美国US	EBR-I	200 kWe	回路式快堆Loop-type	1951-1963
美国US	Fermi-1	60 MWe	回路式快堆Loop-type	1963-1972
美国US	EBR-II	20 MWe	池式快堆Pool-type	1964-1994
美国US	FFTF	400 MWt	回路式快堆Loop-type	1980-2001
俄罗斯RUS	BR-5	5 MW	回路式快堆Loop-type	1959-1971
俄罗斯RUS	BR-10	8 MW	回路式快堆Loop-type	1973-2002
俄罗斯RUS	BN-350	135 MWe	回路式快堆Loop-type	1972-1994
俄罗斯RUS	BN-600	600 MWe	池式快堆Pool-type	1980-至今Present
俄罗斯RUS	BN-800	885 MWe	池式快堆Pool-type	2014-至今Present
法国FRA	Rapsodie	40 MWt	池式快堆Pool-type	1967-1983
法国FRA	Phénix	250 MWe	池式快堆Pool-type	1973-2007
法国FRA	Superphénix	1 240 MWe	池式快堆Pool-type	1985-1997
中国CHN	CEFR	20 MWe	池式快堆Pool-type	2011-至今Present
中国CHN	CFR-600	600 MWe	池式快堆Pool-type	2023-至今Present

Table 2. Physics calculation uncertainty analysis code for sodium-cooled fast reactor

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Table 2. Physics calculation uncertainty analysis code for sodium-cooled fast reactor

原理 Principle		机构 Institution	程序名称 Program	分析范围 Scope	优势 Advantages
确定论方法 Deterministic method	微扰理论 Perturbation theory	美国橡树岭国家实验室Oak Ridge National Laboratory	SCALE^[26]	辐射屏蔽、临界安全评估、不确定性量化等Radiation shielding, criticality safety assessment, uncertainty quantification, etc	集成完善的核数据协方差库、工业验证成熟度高等Integrates nuclear data covariance library, high industrial verification maturity, etc
	微扰理论 Perturbation theory	西安交通大学 Xi'an Jiaotong University	SARAX^[27]	快堆全堆芯高保真计算、多物理场耦合等Fast reactor full-core high-fidelity calculation, multi-physics coupling, etc	复杂堆芯计算精度高、并行计算能力高效等High accuracy in complex core simulations, highly efficient parallel computing capabilities, etc
	直接数值扰动Direct numerical perturbation	西安交通大学 Xi'an Jiaotong University	UNICORN^[46]	核数据敏感性分析、BEPU框架应用等Nuclear data sensitivity analysis, BEPU methodolo- gy application, etc	COST抽样方法降低样本量、灵活调用SARAX代码等The COST sampling method is proposed to reduce the sample size, Flexibly invoke the the SARAX code, etc
统计学抽样方法 Statistical sampling method		德国核设施与反应堆安全协会 Gesellschaft für Anlagen-und Reaktorsicherheit	SUSA^[28] XSUSA^[29]	核数据不确定性传播、中子输运计算等Nuclear data uncertainty propagation,neutron transport calculation, etc	适用范围广，灵活性极强等 Wide application scope, extremely flexible, etc
		华北电力大学 North China Electric Power University	SUFR^[41]	统计学抽样方法研究、不确定性量化等Research on statistical sampling method, uncertai- nty quantification, etc	样本量需求小、计算精度高等 Small sample size requirements, high computati- onal accuracy, etc
		西安交通大学 Xi'an Jiaotong University	UNICORN^[46]	核数据敏感性分析、BEPU框架应用等Nuclear data sensitivity analysis, BEPU methodology application, etc	COST抽样方法降低样本量、灵活调用SARAX代码等The COST sampling method is proposed to reduce the sample size, flexibly invoke the the SARAX code, etc
		比利时核研究中心Belgian Nuclear Research Centre	SANDY^[47]	核数据处理、随机截面生成等 Nuclear data processing, randomized cross-section generation, etc	支持全局敏感性分析、协方差矩阵处理强等Supports global sensitivity analysis, covariance matrix processing, etc

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Zhe ZHANG, Yi CHEN, Desheng JIN, Tianhao WU, Hanhong ZHAO, Chao JIANG. Review of uncertainty analysis in sodium-cooled fast reactor systems[J]. NUCLEAR TECHNIQUES, 2025, 48(7): 070007

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Paper Information

Category: Special Issue on The First Academic Annual Conference of the Research Reactor and Innovative Reactor Association of Chinese Nuclear Society and Advanced Nuclear Power System Reactor Engineering

Received: Apr. 29, 2025

Accepted: --

Published Online: Sep. 15, 2025

The Author Email: Chao JIANG (JIANGChao)

DOI:10.11889/j.0253-3219.2025.hjs.48.250188

Topics

laser devices and laser physics

Lasers and Laser Optics

Laser physics

laser manufacturing

Instrumentation, Measurement and Metrology

Table 1. Information on sodium-cooled fast reactors of the world's major nuclear energy countries[5]

Table 1. Information on sodium-cooled fast reactors of the world's major nuclear energy countries[5]

Table 2. Physics calculation uncertainty analysis code for sodium-cooled fast reactor

Table 2. Physics calculation uncertainty analysis code for sodium-cooled fast reactor

Table 1. Information on sodium-cooled fast reactors of the world's major nuclear energy countries^[5]

Table 1. Information on sodium-cooled fast reactors of the world's major nuclear energy countries^[5]