Numerical analysis of dynamic load following response in a natural circulation molten salt power reactor system

Carter, John P.; Christensen, Richard; Yoon, SuJong

doi:10.1016/j.nucengdes.2022.111818

Numerical analysis of dynamic load following response in a natural circulation molten salt power reactor system

Journal Article · Mon May 23 00:00:00 EDT 2022 · Nuclear Engineering and Design

DOI:https://doi.org/10.1016/j.nucengdes.2022.111818· OSTI ID:1959776

^[1]; Christensen, Richard ^[2]; Yoon, SuJong ^[2]

Univ. of Idaho, Idaho Falls, ID (United States); Idaho National Lab. (INL), Idaho Falls, ID (United States)
Univ. of Idaho, Idaho Falls, ID (United States)

The Molten Salt Reactor (MSR) concept is a rapidly evolving Generation IV design that has recently attracted favorable attention due to the potential for reducing waste generation, realizing passive safety features, and seizing on the opportunity for cost effective economics. An investigation into the power transient behavior of an autonomous load-following, closed-loop, natural circulation MSR system is important to quantifying operational and safety performance under dynamic conditions. This paper presents the results of a STAR-CCM+ and a comparatively simple asymmetric, one-dimensional, numerical model to solve the compound dynamic MSR power behavior subject to flow and temperature reactivity feedback only. Results show that reactor power is affected by fuel salt flow velocity (global) and temperatures (local bulk volume averages) in a coupled, time-delayed manner that results in a unique compound dynamic, closed-loop power feedback mechanism. The 1-D simulation approach opens the possibility of performing inexpensive computations to evaluate time-dependent reactor performance relative to thermo-physical fuel salt limitations. Results also potentially motivate a convincing conclusion that natural circulation MSRs provide a leap in safety and reliability.

Research Organization:: Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: AC07-05ID14517

OSTI ID:: 1959776

Report Number(s):: INL/JOU-21-64332-Rev001

Journal Information:: Nuclear Engineering and Design, Journal Name: Nuclear Engineering and Design Vol. 394; ISSN 0029-5493

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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