Safety analysis and optimization of the core fuel reloading for the Moroccan TRIGA Mark-II reactor

被引:10
作者
Nacir, B. [1 ,2 ]
Boulaich, Y. [2 ]
Chakir, E. [1 ]
El Bardouni, T. [3 ]
El Bakkari, B. [2 ]
El Younoussi, C. [2 ]
机构
[1] LHESIR, Dept Phys, Fac Sci, Kenitra, Morocco
[2] CEN Maamora, CNESTEN, Rabat, Morocco
[3] Univ Abdelmalek Essaadi, Fac Sci Tetuan, Radiat & Nucl Syst Lab, Tetouan, Morocco
关键词
TRIGA; PARET; MCNP; DNBR; Core reloading; Safety;
D O I
10.1016/j.anucene.2013.11.040
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 Moroccan TRIGA MARK II reactor core is loaded with 8.5% in weight of uranium standard fuel elements. Additional fresh fuel elements must periodically be added to the core in order to remedy the observed low power and to return to the initial reactivity excess at the End Of Cycle. 12%-uranium fuel elements are available to relatively improve the short fuel lifetime associated with standard TRIGA elements. These elements have the same dimensions as standards elements, but with different uranium weight. The objective in this study is to demonstrate that the Moroccan TRIGA reactor could safely operate, around 2 MW power, with new configurations containing these 12% fuel elements. For this purpose, different safety related thermal-hydraulic parameters have been calculated in order to ensure that the safety margins are largely respected. Therefore, the PARET model for this TRIGA reactor that was previously developed and combined with the MCNP transport code in order to calculate the 3-D temperature distribution in the core and all the most important parameters like the axial distribution of DNBR (Departure from Nucleate Boiling Ratio) across the hottest channel. The most important conclusion is that the 12% fuel elements utilization will have no influence on the safety of the reactor while working around 2 MW power especially for configurations based on insertions in C and D-rings. (C) 2013 Elsevier Ltd. All rights reserved.
引用
收藏
页码:312 / 316
页数:5
相关论文
共 7 条
  • [1] Determination of thermal hydraulic data of GHARR-1 under reactivity insertion transients using the PARET/ANL code
    Adoo, N. A.
    Nyarko, B. J. B.
    Akaho, E. H. K.
    Alhassan, E.
    Agbodemegbe, V. Y.
    Bansah, C. Y.
    Della, R.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2011, 241 (12) : 5203 - 5210
  • [2] Steady-state thermal-hydraulic analysis of the Moroccan TRIGA MARK II reactor by using PARET/ANL and COOLOD-N2 codes
    Boulaich, Y.
    Nacir, B.
    El Bardouni, T.
    Zoubair, M.
    El Bakkari, B.
    Merroun, O.
    El Younoussi, C.
    Htet, A.
    Boukhal, H.
    Chakir, E.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2011, 241 (01) : 270 - 273
  • [3] Candalino Robert Wilcox, 2006, Master's thesis
  • [4] Development of an MCNP-tally based burnup code and validation through PWR benchmark exercises
    El Bakkari, B.
    El Bardouni, T.
    Merroun, O.
    El Younoussi, Ch.
    Boulaich, Y.
    Chakir, E.
    [J]. ANNALS OF NUCLEAR ENERGY, 2009, 36 (05) : 626 - 633
  • [5] General Atomic, 1993, SAF AN REP MOR 2 MW
  • [6] Htet A, 2001, DEV NOUVEAU SCHEMA C
  • [7] Woodruff W.L., 2000, PARET CODE