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Steady-State Thermal-Hydraulic Analysis of TRIGA Research Reactor

机译：TRIGA研究堆的稳态热工水力分析

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摘要

The COOLOD-N2 and PARET computer codes were used for a steady-state thermal hydraulic and safety analysis of the 3 MW TRIGA Mark-II research reactor located at Atomic Energy Research Establishment (AERE), Savar, Dhaka, Bangladesh. The objective of the present study is to ensure that all important safety related thermal hydraulic parameters uphold margins far below the safety limits by steady-state calculations at full power. We, therefore, have calculated the hot channel fuel centreline temperature, fuel surface temperature, cladding surface temperature, the departure from nucleate boiling (DNB) heat flux and DNB ratio, axial fuel centreline temperature and compared. The comparison indicates that the calculated values are in satisfactory agreement between the codes. The data obtained in this investigation are largely far to compromise safety of the reactor. The results can also be used to upgrade the current core configuration of the TRIGA reactor.
机译：COOLOD-N2和PARET计算机代码用于对位于孟加拉国达卡萨瓦尔的原子能研究机构（AERE）的3兆瓦TRIGA Mark-II研究反应堆进行稳态热力水力和安全性分析。本研究的目的是通过全功率下的稳态计算来确保所有重要的与安全相关的热工水力参数均保持远低于安全极限的裕度。因此，我们计算了热通道燃料中心线温度，燃料表面温度，包层表面温度，偏离核沸腾（DNB）热通量和DNB的比率，轴向燃料中心线温度并进行了比较。比较表明，计算值在代码之间令人满意地一致。在这项研究中获得的数据在很大程度上损害了反应堆的安全性。结果还可以用于升级TRIGA反应堆的当前堆芯配置。

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