Numerical modelling of modular high-temperature gas-cooled reactors with thorium fuel

IF 0.7 4区物理与天体物理 Q4 CHEMISTRY, INORGANIC & NUCLEAR

Nukleonika Pub Date : 2021-11-25 DOI:10.2478/nuka-2021-0020

M. Oettingen, J. Cetnar

引用次数: 10

Abstract

Abstract The volumetric homogenization method for the simplified modelling of modular high-temperature gas-cooled reactor core with thorium-uranium fuel is presented in the paper. The method significantly reduces the complexity of the 3D numerical model. Hence, the computation time associated with the time-consuming Monte Carlo modelling of neutron transport is considerably reduced. Example results comprise the time evolutions of the effective neutron multiplication factor and fissionable isotopes (233U, 235U, 239Pu, 241Pu) for a few configurations of the initial reactor core.

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含钍燃料的模块化高温气冷堆数值模拟

本文提出了钍铀燃料模块化高温气冷堆芯简化建模的体积均化方法。该方法显著降低了三维数值模型的复杂性。因此，与耗时的中子输运蒙特卡罗建模相关的计算时间大大减少。示例结果包括初始堆芯的几种配置的有效中子增殖因子和可裂变同位素（233U、235U、239Pu、241Pu）的时间演变。

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

Nukleonika 物理-无机化学与核化学

CiteScore

2.00

自引率

0.00%

发文量

审稿时长

4-8 weeks

期刊介绍： "Nukleonika" is an international peer-reviewed, scientific journal publishing original top quality papers on fundamental, experimental, applied and theoretical aspects of nuclear sciences. The fields of research include: radiochemistry, radiation measurements, application of radionuclides in various branches of science and technology, chemistry of f-block elements, radiation chemistry, radiation physics, activation analysis, nuclear medicine, radiobiology, radiation safety, nuclear industrial electronics, environmental protection, radioactive wastes, nuclear technologies in material and process engineering, radioisotope diagnostic methods of engineering objects, nuclear physics, nuclear reactors and nuclear power, reactor physics, nuclear safety, fuel cycle, reactor calculations, nuclear chemical engineering, nuclear fusion, plasma physics etc.