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DRAGON & DONJON程序在MSR中堆芯燃耗计算的适用性
Feasibility of DRAGON & DONJON code for MSR core burnup calculation
- 核技术 2017年40卷第6期 文章编号：060602
- 作者机构：
南华大学 核科学与技术学院 衡阳 421001
- 作者简介：
[ "赵文博, 男, 1992年出生, 2014年毕业于东华理工大学, 现为硕士研究生, 从事反应堆物理计算研究", "ZHAO Wenbo, male, born in 1992, graduated from East China Univercity of Technology, master student, focusing on reactor physics research" ]
于涛, E-mail:yutao29@sina.com YU Tao, E-mail:yutao29@sina.com
- 基金信息：国家自然科学基金(11305088);湖南省自然科学基金(14JJ2088)
DOI：10.11889/j.0253-3219.2017.hjs.40.060602
中图分类号： TL99收稿日期：2016-11-28，
修回日期：2016-12-26，
纸质出版日期：2017-06-10
- 稿件说明：
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赵文博, 谢金森, 谢芹, 等. DRAGON & DONJON程序在MSR中堆芯燃耗计算的适用性[J]. 核技术, 2017,40(6):060602
Wenbo ZHAO, Jinsen XIE, Qin XIE, et al. Feasibility of DRAGON & DONJON code for MSR core burnup calculation[J]. Nuclear techniques, 2017, 40(6): 060602
赵文博, 谢金森, 谢芹, 等. DRAGON & DONJON程序在MSR中堆芯燃耗计算的适用性[J]. 核技术, 2017,40(6):060602 DOI： 10.11889/j.0253-3219.2017.hjs.40.060602.
Wenbo ZHAO, Jinsen XIE, Qin XIE, et al. Feasibility of DRAGON & DONJON code for MSR core burnup calculation[J]. Nuclear techniques, 2017, 40(6): 060602 DOI： 10.11889/j.0253-3219.2017.hjs.40.060602.
摘要
DRAGON & DONJON组件-堆芯“两步法”程序通过合理简化，理论可适用于任何堆芯与工况。使用蒙特卡罗方法RMC（Reactor Monte Carlo code）、MCNP（Monte Carlo Neutron Particle transport code）程序验证DRA & DON程序是否能够承担快/热谱型熔盐堆（Molten Salt Reactor，MSR）焚烧TRU、ThU燃料燃耗计算。选出熔盐增殖堆（Molten Salt Breeder Reactor，MSBR）与熔盐锕系元素再循环和嬗变堆（Molten Salt Advanced Reactor Transmuter，MOSART）堆型进行比较，同时分别利用RMC程序验证DRAGON程序组件燃耗计算的准确性，利用MCNP程序验证DRAGON程序组件均匀化方法以及DONJON程序截面调用和程序全堆扩散的准确性。结果表明，组件燃耗计算中，TRU和ThU燃料满足燃耗计算要求；堆芯临界计算中，快/热谱堆芯计算误差均小于0.001。证明DRA & DON程序可以胜任快、热谱型MSR焚烧TRU、ThU燃料的物理计算任务。
Abstract
Background
2
Simplify DRAGON & DONJON lattice-core "two step" process reasonably
this method can be applied to any reactor and any working condition.
Purpose
2
This study aims at verifying the feasibility of using DRAGON & DONJON physical analysis for burning TRU and ThU fuel in molten salt reactor (MSR) by combination of reactor Monte Carlo code (RMC) and Monte Carlo neutron particle transport code (MCNP).
Methods
2
Both the molten salt breeder reactor (MSBR) and molten salt advanced reactor transmuter (MOSART) reactor were taken as examples for comparison and analysis. RMC program was employed to verify accuracy of burnup calculated by DRAGON program whilst MCNP program was used to verify both the accuracy of lattice homogenization embedded in DRAGON program and the few group cross-section call and diffusion in whole reactor adopted in DONJON program.
Results
2
The results show that DRAGON program can be used in MSR for burning TRU and ThU fuel. The calculation errors of fast spectrum and thermal spectrum diffusion are less than 0.001 in critical calculation.
Conclusion
2
DRAGON & DONJON is suitable for physical analysis of TRU and ThU fuel burning in MSR.
关键词
Keywords
references
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