Coupling of Neutronics and Thermal-Hydraulic Codes for Simulation of the MNSR Reactor

被引：6

作者：

Al Zain, Jamal ^{[1
,2
]}

El Hajjaji, O. ^{[1
]}

El Bardouni, T. ^{[1
]}

Boulaich, Y. ^{[3
]}

机构：

[1] Abdelmalek Essaadi Univ, Fac Sci, Radiat & Nucl Syst Lab, Tetouan, Morocco

[2] Sanaa Univ, Phys Dept, Sanaa, Yemen

[3] Natl Ctr Sci Energy & Nucl Tech CNESTEN CENM, Nucl Installat Directorate, Rabat, Morocco

来源：

NUCLEAR SCIENCE AND ENGINEERING | 2019年 / 193卷 / 11期

关键词：

MNSR reactor; DRAGON5/DONJON5; PARET/ANL; temperature; departure from nucleate boiling ratio; REACTIVITY; CORE; TRANSIENTS; DESIGN; FUEL;

D O I：

10.1080/00295639.2019.1622927

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：

This study aims to evaluate a simplified one-dimensional thermal-hydraulic module (THM) established by the DRAGON5/DONJON5 codes that allow a multiphysics study of the Syrian Miniature Neutron Source Research (MNSR) reactor both in steady-state and transient conditions. The purpose of this paper is therefore to describe the THM, fully integrated and implanted in DONJON5 to allow coupling with neutronic modules existing in the same code and to perform steady-state thermal-hydraulic and safety analyses of the reactor. Then we compare the results given by the THM with the results obtained by the Program for the Analysis of REactor Transients (PARET)/Argonne National Laboratory (ANL) thermal-hydraulic code. In order to validate our PARET/ANL and the THM in DONJON5, the fuel center temperature as a function of core power was calculated and compared with the corresponding values of the PARET code. Moreover, we have calculated the departure from nucleate boiling ratio. The comparison of the results of this study showed a good correlation between the values obtained with the THM and the thermal-hydraulic PARET/ANL code.

引用

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页码：1276 / 1289

页数：14

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