Measurement and calculation of the void reactivity coefficient of the Jordan research and training reactor (JRTR)

• Core Design Characteristics of the JRTR. • Evaluation Method of the Void Reactivity Coefficient. • Measurement and Calculation Results. The void reactivity coefficient for the JRTR was evaluated experimentally, and the voids in the reactor core were simulated using the specially designed tools of aluminium. These simulators were inserted vertically into the coolant channel between the fuel plates, in the central area of the fuel assembly. The experiments were performed for the scenarios with 4.74 %, 2.37 %, 0 % of void fractions within the reactor core, and a series of calculations for these experiments were performed by using McCARD code with the ENDF/B-VII nuclear library. The results of the calculations for the CARs critical position show good agreement with the corresponding measurement results within 1.8 mm. Also, the void reactivity coefficient in all experiments had negative values, and the coefficient for the JRTR was experimentally evaluated to be −0.237 $/% void.

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Publication Details

Journal
Annals of Nuclear Energy
Published
2024-12-04
DOI
https://doi.org/10.1016/j.anucene.2024.111089
Citations
1
Primary Topic
Nuclear reactor physics and engineering
Type
article
Field-Weighted Citation Impact
1.30
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article

Measurement and calculation of the void reactivity coefficient of the Jordan research and training reactor (JRTR)

Byungchul Lee, Beom Woo Park, Kyung-O Kim, Han Jong Yoo et al.
1 citations
Annals of Nuclear Energy
Nuclear reactor physics and engineering
1.30
article

Measurement and calculation of the void reactivity coefficient of the Jordan research and training reactor (JRTR)

Byungchul Lee, Beom Woo Park, Kyung-O Kim, Han Jong Yoo, Gyuhong Roh
article en
1 citations

Abstract

• Core Design Characteristics of the JRTR. • Evaluation Method of the Void Reactivity Coefficient. • Measurement and Calculation Results. The void reactivity coefficient for the JRTR was evaluated experimentally, and the voids in the reactor core were simulated using the specially designed tools of aluminium. These simulators were inserted vertically into the coolant channel between the fuel plates, in the central area of the fuel assembly. The experiments were performed for the scenarios with 4.74 %, 2.37 %, 0 % of void fractions within the reactor core, and a series of calculations for these experiments were performed by using McCARD code with the ENDF/B-VII nuclear library. The results of the calculations for the CARs critical position show good agreement with the corresponding measurement results within 1.8 mm. Also, the void reactivity coefficient in all experiments had negative values, and the coefficient for the JRTR was experimentally evaluated to be −0.237 $/% void.

Annals of Nuclear EnergyVol. 213
Korea Atomic Energy Research Institute (KR)
Openalex Percentile: Top 12%
Nuclear reactor physics and engineering
1.30
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