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학술저널
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한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제50권 제1호
발행연도
2018.1
수록면
35 - 42 (8page)

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This article presents clean core criticality calculations and control rod worth calculations for TRIGA(Training, Research, Isotope production-General Atomics) Mark II research reactor benchmark coresusing Winfrith Improved Multi-group Scheme-D/4 (WIMS-D/4) and Program for Reactor In-core Analysisusing Diffusion Equation (PRIDE) codes. Cores 133 and 134 were analyzed in 2-D (r, q) and 3-D (r, q, z),using WIMS-D/4 and PRIDE codes. Moreover, the influence of cross-section data was also studied usingvarious libraries based on Evaluated Nuclear Data File (ENDF/B-VI.8 and VII.0), Joint Evaluated Fission andFusion File (JEFF-3.1), Japanese Evaluated Nuclear Data Library (JENDL-3.2), and Joint Evaluated File (JEF-2.2) nuclear data. The simulation results showed that the multiplication factor calculated for all thesedata libraries is within 1% of the experimental results. The reactivity worth of the control rods of core 134was also calculated with different homogenization approaches. A comparison was made with experimentaland reported Monte Carlo results, and it was found that, using proper homogenization ofabsorber regions and surrounding fuel regions, the results obtained with PRIDE code are significantlyimproved.

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