Steady-state thermal-hydraulic analysis of the Moroccan TRIGA MARK II reactor by using PARET/ANL and COOLOD-N2 codes

被引：19
|
作者：
Boulaich, Y. [1 ]
Nacir, B. [1 ]
El Bardouni, T.
Zoubair, M.
El Bakkari, B. [1 ]
Merroun, O.
El Younoussi, C. [1 ]
Htet, A. [1 ]
Boukhal, H.
Chakir, E. [2 ]
机构：
[1] CNESTEN, CEN Maamora, Rabat, Morocco
[2] LRM EPTN, Dept Phys, Fac Sci, Kenitra, Morocco
来源：
NUCLEAR ENGINEERING AND DESIGN | 2011年 / 241卷 / 01期
关键词：
D O I：
10.1016/j.nucengdes.2010.10.033
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
The COOLOD/N2 and PARET/ANL codes were used for a steady-state thermal-hydraulic and safety analysis of the 2 MW TRIGA MARK II reactor located at the Nuclear Studies Center of Maamora (CENM), Morocco. In order to validate our PARET/ANL and COOLOD-N2 models, the fuel center temperature as function of core power was calculated and compared with the corresponding experimental values. The comparison indicates that the calculated values are in satisfactory agreement with the measurement. The main objective of this study is to ensure the safety margins of different safety related parameters by steady-state calculations at full power level (2 MW). Therefore, we have calculated the departure from nucleate boiling ratio (DNBR), fuel center and surface temperature, cladding surface temperature and coolant temperature profiles across the hottest channel. The most important conclusion is that all obtained values are largely far to compromise safety of the reactor. (C) 2010 Elsevier B.V. All rights reserved.
引用
收藏
页码：270 / 273
页数：4
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