Transient calculation on TRIGA 2000 of plate-type fuel element using RELAP5, EUREKA2/RR, and MTR-DYN codes

IF 0.9 4区工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Technology & Radiation Protection Pub Date : 2021-01-01 DOI:10.2298/ntrp2103211d

S. Dibyo, S. Pinem, S. Widodo

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引用次数: 0

Abstract

The TRIGA 2000 reactor Bandung is proposed to convert from rod-type fuel to plate-type fuel because there are no manufacturers in the world that still produce rod-type fuel. Calculating the safety parameters and their reliability related to reactor operation has become an important thing to do. The objective of this study was to perform the reactor transient calculation of TRIGA 2000 that uses plate-type fuel. The reactor core modification is based on the capability of the existing primary coolant system, without changing its flow rates. Thermal-hydraulics calculations related to reactivity insertion accident and loss of flow accident were analyzed using EUREKA2/RR, MTR-DYN, and RELAP5 codes. The chosen loss of flow accident scenario is a decrease in flow caused by a sudden stop of the pump power supply, while reactivity insertion accident is conducted by the withdrawal of control rods with maximum reactivity insertion of 32.33 ? 10?5 s?1. The calculated parameters are reactivity, reactor power, and temperature of the coolant, cladding, and fuel in the hottest channel position. In general, from a safety point of view, those computer codes were capable of performing the transient calculations with appropriate results. Based on the calculation results, during the transient condition of both reactivity insertion accident and loss of flow accident scenario, the reactor operation safety parameters do not exceed the allowable safety limit.

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用RELAP5、EUREKA2/RR和MTR-DYN软件在TRIGA 2000上对板式燃料元件进行瞬态计算

万隆TRIGA 2000反应堆被提议从棒型燃料转换为板型燃料，因为世界上没有制造商仍然生产棒型燃料。计算与反应堆运行有关的安全参数及其可靠性已成为一项重要的工作。本研究的目的是对使用板型燃料的TRIGA 2000进行反应堆瞬态计算。反应堆堆芯的改造是基于现有主冷却剂系统的能力，而不改变其流量。使用EUREKA2/RR、MTR-DYN和RELAP5代码分析与反应性插入事故和失流事故相关的热工力学计算。所选择的失流事故场景是由于泵的电源突然停止导致流量减少，而反应性插入事故是由于控制棒的拔出造成的，反应性插入的最大值为32.33 ?10？5 s ? 1。计算的参数包括反应性、反应堆功率、冷却剂、包层和最热通道位置燃料的温度。一般来说，从安全的角度来看，这些计算机代码能够进行瞬态计算并得到适当的结果。计算结果表明，在反应性插入事故和失流事故两种暂态工况下，反应堆运行安全参数均未超过允许的安全限值。

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

Nuclear Technology & Radiation Protection NUCLEAR SCIENCE & TECHNOLOGY-

CiteScore

2.00

自引率

41.70%

发文量

审稿时长

6-12 weeks

期刊介绍： Nuclear Technology & Radiation Protection is an international scientific journal covering the wide range of disciplines involved in nuclear science and technology as well as in the field of radiation protection. The journal is open for scientific papers, short papers, review articles, and technical papers dealing with nuclear power, research reactors, accelerators, nuclear materials, waste management, radiation measurements, and environmental problems. However, basic reactor physics and design, particle and radiation transport theory, and development of numerical methods and codes will also be important aspects of the editorial policy.