期刊论文

Feasibility of DRAGON&DONJON code for MSR core burnup calculation

Yu, T.

中文

核技术

0253-3219

2017

40

6

060602-1-060602-7

10.11889/j.0253-3219.2017.hjs.40.060602

国家自然科学基金(No.11305088)、湖南省自然科学基金(No.14JJ2088)资助 第一作者：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 通信作者：于涛，E-mail: yutao29@sina.com 收稿日期：2016-11-28，修回日期：2016-12-26 Supported by National Natural Science Foundation of China (No.11305088), Natural Science Foundation of Hunan Province (No.14JJ2088) First author: ZHAO Wenbo, male, born in 1992, graduated from East China Univercity of Technology, master student, focusing on reactor physics research Corresponding author: YU Tao, E-mail: yutao29@sina.com Received date: 2016-11-28, accepted date: 2016-12-26

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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。...

Background: Simplify DRAGON&DONJON lattice - core "two step" process reasonably, this method can be applied to any reactor and any working condition. Purpose: 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: Both the molten salt breeder reactor (MSBR) and molten salt advanced reactor transmuter (MOSART) reactor were taken as examples for c...