Nuclear Science and Techniques

《核技术》(英文版) ISSN 1001-8042 CN 31-1559/TL     2019 Impact factor 1.556

Nuclear Science and Techniques ›› 2017, Vol. 28 ›› Issue (12): 171

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles     Next Articles

Effective point kinetic parameters calculation in Tehran research reactor using deterministic and probabilistic methods

M. Kheradmand Saadi 1, A. Abbaspour 1,2   

  1. 1 Department of Nuclear Engineering, Science and Research Branch, Islamic Azad University, Tehran, Iran
    2 Department of Electrical Engineering, Sharif University of Technology, Tehran, Iran
  • Contact: M. Kheradmand Saadi E-mail:Mohsen.Kheradmand@gmail.com
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M. Kheradmand Saadi, A. Abbaspour. Effective point kinetic parameters calculation in Tehran research reactor using deterministic and probabilistic methods.Nuclear Science and Techniques, 2017, 28(12): 171

Abstract:

The exact calculation of point kinetic parameters is very important in nuclear reactor safety assessment, and most sophisticated safety codes such as RELAP5, PARCS, DYN3D, and PARET are using these parameters in their dynamic models. These parameters include effective delayed neutron fractions as well as mean generation time. These parameters are adjoint-weighted, and adjoint flux is employed as a weighting function in their evaluation. Adjoint flux calculation is an easy task for most of deterministic codes, but its evaluation is cumbersome for Monte Carlo codes. However, in recent years, some sophisticated techniques have been proposed for Monte Carlo-based point kinetic parameters calculation without any need of adjoint flux. The most straightforward scheme is known as the “prompt method” and has been used widely in literature. The main objective of this article is dedicated to point kinetic parameters calculation in Tehran research reactor (TRR) using deterministic as well as probabilistic techniques. WIMS-D5B and CITATION codes have been used in deterministic calculation of forward and adjoint fluxes in the TRR core. On the other hand, the MCNP Monte Carlo code has been employed in the “prompt method” scheme for effective delayed neutron fraction evaluation. Deterministic results have been cross-checked with probabilistic ones and validated with SAR and experimental data. In comparison with experimental results, the relative differences of deterministic as well as probabilistic methods are 7.6 and 3.2%, respectively. These quantities are 10.7 and 6.4%, respectively, in comparison with SAR report.

Key words: Point kinetic parameters, Tehran research reactor, Adjoint flux, Prompt method, Deterministic method, Probabilistic method