CFD Modeling of a Coolant Channel for Missouri S&T Reactor
Simulations were carried out to determine the need for temperature corrections to accurately model the MSTR core. This preliminary study using uniform heat flux had obtained temperature and velocity profiles of the coolant flow into a narrow channel that arises from convective heating from two curved fuel plates. The result of the simulations indicated that there is no need for neutron cross section correction for MCNP simulations. Less than 50K temperature is sufficiently small to ignore any impact on the neutronics. The water density change of approximately 2% may require some correction in the model.
S. Sipaun et al., "CFD Modeling of a Coolant Channel for Missouri S&T Reactor," Transactions of the American Nuclear Society, American Nuclear Society (ANS), Jun 2013.
2013 ANS Annual Meeting - Next Generation Nuclear Energy: Prospects and Challenges (2013: Jun. 16-20, Atlanta, GA)
Mining and Nuclear Engineering
International Standard Serial Number (ISSN)
Article - Conference proceedings
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