Transient Studies of Ghana Research Reactor-1 after Nineteen (19) Years of Operation Using PARET/ANL Code

B. M. Mweetwa, E. Ampomah-Amoako, E. Akaho
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引用次数: 2

Abstract

The Program for the Analysis of Reactor Transients/Argonne National Laboratory (PARET/ANL) code was used to predict the thermal hydraulic behaviour of the Ghana Research Reactor-1 after adding 9.0 mm of beryllium to the top shim tray of the core. The core was analysed for reactivity insertions 2.1 mk, 3.0 mk, 4.0 mk, 5.0 mk and 6.7 mk, respectively. The reactor is still safe to operate in the range 2.1 mk to 4.0 mk. However, 2.1 mk would be ideal since the reactor automatic shutdown (SCRAM) is set not to exceed 120% of reactor nominal power.
使用PARET/ANL代码对加纳研究堆1号运行十九(19)年后的瞬态研究
使用反应堆瞬态分析程序/阿贡国家实验室(PARET/ANL)代码来预测加纳研究堆-1在堆芯顶部垫片托盘中添加9.0 mm的铍后的热水力行为。分析核心的反应性插入分别为2.1 mk、3.0 mk、4.0 mk、5.0 mk和6.7 mk。反应堆在2.1 mk至4.0 mk范围内运行仍然是安全的。然而,2.1 mk将是理想的,因为反应堆自动关闭(SCRAM)被设置为不超过反应堆标称功率的120%。
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
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