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

Journal Article · · Nuclear Engineering and Design
ORCiD logo [1];  [2];  [2]
  1. Univ. of Idaho, Idaho Falls, ID (United States); Idaho National Lab. (INL), Idaho Falls, ID (United States)
  2. Univ. of Idaho, Idaho Falls, ID (United States)
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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

References (13)

UF4, ThF4 Solubility in LiF–NaF–KF Melt journal October 2013
Mathematical modelling of the stability characteristics of a natural circulation loop journal November 1995
Calculating the effective delayed neutron fraction in the Molten Salt Fast Reactor: Analytical, deterministic and Monte Carlo approaches journal March 2014
Two-dimensional numerical analysis of a rectangular closed-loop thermosiphon journal January 2013
Analytical and numerical investigation of the heat exchange effect on the dynamic behaviour of natural circulation with internally heated fluids journal May 2016
Stability analysis of a single phase rectangular coupled natural circulation loop system employing a Fourier series based 1-D model journal January 2022
Thermal–hydraulic characteristics of a single-phase natural circulation loop with water and Al2O3 nanofluids journal March 2009
Integral molten salt reactor neutron physics study using Monte Carlo N-particle code journal August 2020
Integral molten salt reactor temperature sensitivities using Serpent target motion sampling journal December 2020
Numerical study on the Welander oscillatory natural circulation problem using high-order numerical methods journal January 2017
On the oscillatory instability of a differentially heated fluid loop journal July 1967
Thermal Hydraulic Flow Oscillation Characteristics in Multiformed Channels under Natural Circulation and Low-Pressure Conditions journal February 2008
Natural Circulation and Linear Stability Analysis for Liquid-Metal Reactors with the Effect of Fluid Axial Conduction journal June 2012

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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
molten salt
natural circulation
transient power