添加Gd2O3和Pa-231作为可燃毒物的(Th-U)O2燃料长寿命压水堆三维(X-Y-Z)堆芯设计

D. Hariyanto, S. Permana
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引用次数: 0

摘要

压水堆(PWRs)是世界上最主要的商业运行的核电站之一。本研究的目的是利用钍-二氧化铀((Th-U)O2)燃料,添加钆(Gd2O3)和镤-231 (Pa-231)作为可燃毒物,对长寿命压水堆进行三维(X-Y-Z)核心设计。钍和浓缩铀燃料的组合比其他燃料具有更高的转换率,因此可以保证反应堆运行更长时间。可燃毒性同位素由于具有很高的热中子吸收截面,可用于降低过量反应性。对于堆芯几何分析,采用三维(X-Y-Z)几何形状,燃料体积分数为40%。计算采用日本原子能机构(JAEA)的SRAC 2006计算机代码和JENDL 4.0作为核数据库。在本研究中,对燃料中二氧化铀、铀-235、钆和镤-231的不同馏分进行了研究。研究结果为800 MWt压水堆三维堆芯设计,该堆芯采用60%二氧化铀燃料,铀235浓度为12% ~ 11%,Gd2O3添加量为0.025%,Pa-231添加量为1.0%,可运行10年,无需换料。本研究可为钍铀燃料循环的长寿命压水堆设计提供参考。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Three-dimensional (X-Y-Z) Core Design of Long-Life Pressurized Water Reactor Using (Th-U)O2 Fuels with The Addition of Gd2O3 and Pa-231 as Burnable Poisons
Pressurized water reactors (PWRs) are one of the most dominant types of nuclear power plants that have been operated commercially to produce electricity in the world. The purpose of this study was to perceive a three-dimensional (X-Y-Z) core design of long-life PWR using Thorium-Uranium dioxide ((Th-U)O2) fuels with the addition of Gadolinium (Gd2O3) and Protactinium-231 (Pa-231) as the burnable poisons. A combination of Thorium and enriched Uranium fuels have a higher conversion ratio than other fuels, therefore can guarantee the reactor to operate longer. The burnable poison isotopes could be used to reduce excess reactivity due to the very high thermal neutron absorption cross-section. For core geometry analysis, a three-dimensional (X-Y-Z) geometry and a fuel volume fraction of 40% were applied. The computer code of SRAC 2006 from the Japan Atomic Energy Agency (JAEA) and the JENDL 4.0 as a nuclear data library were used for calculation. In this study, different fractions of Uranium dioxide, Uranium-235, Gadolinium, and Protactinium-231 in fuel were carried out. The result of this study was a three-dimensional core design of 800 MWt PWR using 60% Uranium dioxide fuel with enriched Uranium-235 of 12%-11% and the addition of 0,025% Gd2O3 and 1,0% Pa-231 which could operate for ten years without refueling. This research is expected to be a reference for long-life PWR design using the Thorium and Uranium fuel cycles.
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