Steady-State Thermal-Hydraulic Analysis of TRIGA Research Reactor

来源 :核科学与技术国际期刊(英文) | 被引量 : 0次 | 上传用户：identitymatrix

【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

【作者】

：

Mohammad Mizanur Rahman Mohamm

【机构】

：

NuclearEnergyDivision,RenewableEnergyDivision

【出处】

：

核科学与技术国际期刊(英文)

【发表日期】

：

2014年2期

【关键词】

：

COOLOD-N2 PARET TRIGA Mark-II DNB Safety COOLOD-N2PARETTRIGA Mark-IIDNBSafety

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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 pre

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Steady-State Thermal-Hydraulic Analysis of TRIGA Research Reactor

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