Pages: 1-9

Authors: Duc-Tu Dau, Nhi-Dien Nguyen1, Kien-Cuong Nguyen, Quang-Huy Pham, Thoi-Nam Chu, Van-Khanh Hoang, Giang T. T. Phan, and Hoai-Nam Tran

Abstract

Kinetic parameters of a nuclear reactor are essential in reactor dynamic and safety related characteristics. Kinetic parameters of the Dalat nuclear research reactor were evaluated using the MCNP6.3 code and a new nuclear data library (JENDL-5). Numerical calculations were performed for the core configuration consisting of 92 low-enriched uranium fuel bundles for obtaining the effective delayed neutron fraction β_eff, the neutron generation time ᴧ and the prompt neutron lifetime l_p. Two methods were used to calculate the β_eff: the adjoint weighted method based on perturbation theory and adjoint flux, and the prompt method using the ratio of prompt and total fission neutrons. To calculate the ᴧ and the l_p, the adjoint weighted method and the l/_v absorber insertion method were used. The values of β_eff, ᴧ and l_p, at the beginning of cycle and the end of cycle obtained with the adjoint weighted method are 760 and 708 pcm, 86.99 and 82.41 µs, 79.01 and 82.76 µs, respectively. Comparing among the methods, the kinetic parameters were predicted with the discrepancy of about 1.0-1.6 %. The kinetic parameters will be utilized in the safety analysis report of the Dalat nuclear research reactor.

Key words: Dalat nuclear research reactor, low-enriched uranium fuel, kinetic parameter, MCNP6, JENDL-5

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