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Development of a PARCS/Serpent model for neutronics analysis of the Dalat nuclear research reactor

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Abstract

Cross-sectional homogenization for full-core calculations of small and complex reactor configurations, such as research reactors, has been recently recognized as an interesting and challenging topic. This paper presents the development of a PARCS/Serpent model for the neutronics analysis of a research reactor type TRIGA Mark-II loaded with Russian VVR-M2 fuel (known as the Dalat Nuclear Research Reactor or DNRR). The full-scale DNRR model and a supercell model for a shim/safety rod and its surrounding fuel bundles with the Monte Carlo code Serpent 2 were proposed to generate homogenized few-group cross sections for full-core diffusion calculations with PARCS. The full-scale DNRR model with Serpent 2 was also utilized as a reference to verify the PARCS/Serpent calculations. Comparison of the effective neutron multiplication factors, radial and axial core power distributions, and control rod worths showed a generally good agreement between PARCS and Serpent 2. In addition, the discrepancies between the PARCS and Serpent 2 results are also discussed. Consequently, the results indicate the applicability of the PARCS/Serpent model for further steady state and transient analyses of the DNRR.

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Authors and Affiliations

Authors

Contributions

All authors contributed to the study conception and design. Material preparation, data collection, model development and analysis were performed by Viet-Phu Tran, Kien-Cuong Nguyen and Pham Nhu Viet Ha. The first draft of the manuscript was written by Pham Nhu Viet Ha and all authors commented on previous versions of the manuscript. All authors read and approved the final manuscript.

Corresponding authors

Correspondence to Kien-Cuong Nguyen or Pham Nhu Viet Ha.

Additional information

This study was funded by the Ministry of Science and Technology of Vietnam (No. DTCB.06/18/VKHKTHN).

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Tran, VP., Nguyen, KC., Hartanto, D. et al. Development of a PARCS/Serpent model for neutronics analysis of the Dalat nuclear research reactor. NUCL SCI TECH 32, 15 (2021). https://doi.org/10.1007/s41365-021-00855-5

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  • DOI: https://doi.org/10.1007/s41365-021-00855-5

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