Preparation Method of ORIGEN2 Library for High Temperature Gas-Cooled Reactors

IF 0.4 Q4 NUCLEAR SCIENCE & TECHNOLOGY Journal of Nuclear Fuel Cycle and Waste Technology Pub Date : 2022-08-08 DOI:10.1115/icone29-90802
I. L. Simanullang, Katsuki Fukuhara, Keisuke Morita, Y. Fukaya, H. Ho, S. Nagasumi, K. Iigaki, E. Ishitsuka, N. Fujimoto
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Abstract

The ORIGEN2 code has been used for fuel depletion calculations of many kinds of reactor fuels but there is no library for high temperature gas cooled reactors (HTGRs). A set of the ORIGEN2 library for the HTGR has been established to evaluate the fuel burnup characteristics. In this study, the ORIGEN2 library was prepared for the high temperature engineering test reactor (HTTR). The HTTR is the first Japanese prismatic type HTGR. The burnup dependent neutron spectrum is necessary for generating the ORIGEN2 library. A pin-cell burnup calculation was conducted to obtain the burnup dependent neutron spectrum in the fuel compact of HTTR. Then, the ORIGEN2 library was generated based on the neutron spectrum of the pin cell model. The calculation results that were calculated by the ORIGEN2 code was validated by comparison with a detailed calculation with use of the MVP-BURN code. This code-to-code method was used to validate the ORIGEN2 code calculation because of no assay data of HTTR spent fuels. One of the isotopes that evaluated was 239Pu. The calculation results showed that the amount of 239Pu calculated by ORIGEN2 code was higher about 35% than that of calculated by the MVP-BURN code. It showed that the ORIGEN2 library using the neutron spectrum of a pin-cell burnup model was not enough for evaluating burnup characteristics of the HTTR. Therefore, an improvement was performed to evaluate the ORIGEN2 library. In this study, the ORIGEN2 library was generated based on the neutron spectrum of a core burnup calculation. The calculation results showed that the ORIGEN2 code and the MVP-BURN code was in a good agreement. The maximum difference of 239Pu amount between the ORIGEN2 and MVP-BURN became 2.4%.
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高温气冷堆ORIGEN2文库的制备方法
ORIGEN2代码已用于多种反应堆燃料的燃料耗尽计算,但没有用于高温气冷堆(htgr)的库。建立了一套用于高温气冷堆燃料燃耗特性评估的ORIGEN2库。本研究为高温工程试验堆(HTTR)准备了ORIGEN2文库。htr是日本第一个棱柱形htr。与燃耗相关的中子谱是生成ORIGEN2库所必需的。通过针电池燃耗计算,得到了HTTR燃料致密体中与燃耗有关的中子能谱。然后,基于引脚电池模型的中子谱生成ORIGEN2库。通过与使用MVP-BURN代码进行详细计算的对比,验证了ORIGEN2代码计算结果的正确性。由于没有HTTR乏燃料的分析数据,因此使用这种代码到代码的方法来验证ORIGEN2代码计算。其中一个被评估的同位素是239Pu。计算结果表明,用ORIGEN2程序计算的239Pu量比用MVP-BURN程序计算的239Pu量高35%左右。结果表明,利用引脚电池燃耗模型中子谱的ORIGEN2库不足以评价HTTR的燃耗特性。因此,我们进行了改进来评估ORIGEN2库。在本研究中,ORIGEN2库是基于堆芯燃耗计算的中子谱生成的。计算结果表明,ORIGEN2代码与MVP-BURN代码具有较好的一致性。与MVP-BURN相比,ORIGEN2的239Pu量最大差异为2.4%。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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来源期刊
CiteScore
0.80
自引率
25.00%
发文量
35
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