Computational burnup analysis of the TRIGA Mark II research reactor fuel

被引：19

作者：

Pungercic, Anze ^{[1
,2
]}

Calic, Dusan ^{[1
]}

Snoj, Luka ^{[1
,2
]}

机构：

[1] Jozef Stefan Inst, Reactor Phys Dept, Jamova Cesta 39, Ljubljana 1000, Slovenia

[2] Univ Ljubljana, Fac Math & Phys, Jadranska Ul 19, Ljubljana 1000, Slovenia

来源：

PROGRESS IN NUCLEAR ENERGY | 2020年 / 130卷

关键词：

TRIGA research reactor and Fuel Burnup; Operational history analysis; Serpent-2; TRIGLAV; Excess reactivity measurements; MONTE-CARLO SIMULATION; BENCHMARK EXPERIMENT; KINETIC-PARAMETERS; THERMAL POWER; VALIDATION; FISSION; NEUTRON;

D O I：

10.1016/j.pnucene.2020.103536

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：

In this study, analysis of the complete operational history of the "Jozef Stefan" Institute (JSI) TRIGA reactor was performed. Reactor power changes, core configurations and weekly excess reactivity measurements were analysed to obtain the needed data for fuel burnup calculations. More than 50 years of reactor operation was simulated using deterministic code TRIGLAV and stochastic code Serpent-2. The calculated core reactivities are in good agreement compared with the excess reactivity measurements. Code-to-code comparison is presented. Clear agreement is observed when comparing changes in core excess reactivity, and discrepancies are observed in the comparison of individual fuel element burnup and its isotopic composition. The Serpent-2 results are in better agreement with the measurements compared to the TRIGLAV code; nevertheless, a conclusion can be made that the TRIGLAV code is viable for TRIGA fuel management and burnup analysis. A three-dimensional (3D) burnup study was conducted, where individual fuel elements were further divided into multiple angular and axial depletion zones. Notable burnup effects were observed, and an explanation using surrounding water distance is presented.

引用

页数：21

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