Title

CFD Modeling of a Coolant Channel for Missouri S&T Reactor

Abstract

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.

Meeting Name

2013 ANS Annual Meeting - Next Generation Nuclear Energy: Prospects and Challenges

Department(s)

Mining and Nuclear Engineering

Document Type

Article - Conference proceedings

Document Version

Citation

File Type

text

Language(s)

English

Rights

© 2013 American Nuclear Society (ANS), All rights reserved.

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