不同燃料循环条件下具有超临界冷却剂参数的反应堆系统特性评估

A. Lapin, A. Bobryashov, V. Blandinsky, E. Bobrov
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引用次数: 1

摘要

如今,核能是在开放式燃料循环中运行的。核能发展的一个最重要的方向是核燃料循环的封闭。使用快中子反应堆可能解决这个问题。为了实现这一目标,考虑了使用超临界水(SCWR)冷却快共振中子谱反应堆的可能性。SCWR反应堆可以有效地用于封闭的核燃料循环,因为它可以使用乏燃料,并在少量添加钚的情况下倾倒铀。考虑了核心区的布局选项,以及核心区和再生区大小的变化。评估了在活动区域内放置各种材料的繁殖区域的可能性。在此基础上,根据系统特性选择了一个可接受的核心版本。为了考虑反应堆堆芯的布置,研究了缩短铀-钚和铀-钍燃料循环的可能性。研究了以下几种燃料负荷方案下反应堆装置的系统特性:将MOX燃料装入堆芯,在再生产的侧区耗尽铀。2. 将铀钍燃料装入堆芯和侧屏。本文考虑了反应器系统特性评估的结果。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
ASSESSMENT OF THE SYSTEM CHARACTERISTICS OF A REACTOR WITH SUPERCRITICAL COOLANT PARAMETERS FOR VARIOUS FUEL CYCLES
Nowadays nuclear energy operates in an open fuel cycle. One of the most important directions in the development of nuclear energy is the closure of the nuclear fuel cycle. The solution to this problem is possible with the use of fast neutron reactors. To achieve this goal, the possibility of using a reactor with a fast-resonance neutron spectrum cooled by supercritical water (SCWR) was considered. The SCWR reactor can be effectively used in a closed nuclear fuel cycle, since it makes it possible to use spent fuel and dump uranium with a small amount of plutonium added. The layout options of the core with a change in the size of the core and reproduction zones are considered. The possibility of placing reproduction zones from various materials inside the active zone was evaluated. Based on the studies, an acceptable version of the core is selected in terms of system characteristics. For the considered arrangement of the reactor core, the possibility of shorting the uranium-plutonium and uranium-thorium fuel cycles has been investigated. The system characteristics of the reactor installation were studied for the following fuel load options: 1. Loading MOX fuel into the core, depleted uranium in the lateral zone of reproduction. 2. Loading of uranium-thorium fuel into the core and side screens. The results of the assessments of the system characteristics of the reactor are considered in the article.
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