Development and validation of PROTEUS-NODAL transient analyses capabilities for molten salt reactors

MK Jaradat, H Park, WS Yang, C Lee - Annals of Nuclear Energy, 2021 - Elsevier
This paper presents the PROTEUS-NODAL capabilities developed for modeling and
simulation of molten salt reactors (MSRs) with flowing fuel. Steady-state and transient …

[PDF][PDF] Benchmark of dynamic simulation tools for molten salt reactors

M Delpech, S Dulla, C Garzenne… - Proceedings of the …, 2003 - researchgate.net
A benchmark of some codes developed for the neutronic analysis of molten-salt reactors is
presented. The results of the calculations are compared to the experimental data reported …

Studies on the molten salt reactor: code development and neutronics analysis of MSRE-type design

K Zhuang, L Cao, Y Zheng, H Wu - Journal of Nuclear Science and …, 2015 - Taylor & Francis
The molten salt reactor is characterized by its use of the fluid-fuel, which serves both as a
fuel and as a coolant simultaneously. The position of delayed neutron precursors …

Development of Neutronics Analysis Capabilities for Application of Flowing Fuel Molten Salt Reactors

M Jaradat - 2021 - deepblue.lib.umich.edu
As one of generation IV reactor designs, molten salt reactors (MSRs) with fuel dissolved in
liquid salt are gaining increasing interest from the industry due to their excellent …

Improvements and validation of the transient analysis code MOREL for molten salt reactors

K Zhuang, Y Zheng, L Cao, T Hu… - Journal of Nuclear Science …, 2017 - Taylor & Francis
The liquid fuel salt used in the molten salt reactors (MSRs) serves as the fuel and coolant
simultaneously. On the one hand, the delayed neutron precursors circulate in the whole …

[HTML][HTML] 熔盐堆物理热工耦合程序开发及验证分析

魏泉, 郭威, 王海玲, 陈金根, 蔡翔舟 - 核技术, 2017 - xml-data.org
熔盐堆(Molten Salt Reactor, MSR) 是第四代反应堆6 种堆型中唯一的液态燃料反应堆,
与固态燃料-液体冷却剂反应堆相比, 原理上有较大不同. 在熔盐堆中, 流动的熔盐既是燃料又是 …

An Analysis of Transport Effects in Steady-State Simulation of the Molten Salt Reactor Experiment

AJ Reynolds, TS Palmer - Nuclear Science and Engineering, 2023 - Taylor & Francis
We use the deterministic neutron transport code QuasiMolto to simulate steady-state
operation of the Molten Salt Reactor Experiment (MSRE). Comparisons are made to similar …

Dynamics analysis of the graphite-moderated channel-type molten salt reactors based on Serpent/NTH3D-MSR

Z Li, J Cai - Annals of Nuclear Energy, 2018 - Elsevier
The special characteristic of the Molten Salt Reactors (MSR) is that the liquid molten salt
mixtures, acting like a coolant and fuel, are flowing through the core and the primary circuit …

[PDF][PDF] Computational modeling of a molten salt reactor

GJ Auwerda - Skripsi. TU Delft, Delft, 2007 - janleenkloosterman.nl
In this report the computational modeling of a molten salt reactor (MSR) is described and the
subsequent testing of that model. The testing was done by comparing computational results …

A Multilevel Nonlinear Projective Method for Circulating Fuel Reactor Kinetics

AJ Reynolds - 2020 - ir.library.oregonstate.edu
Circulating fuel reactor (CFR) kinetics are characterized by delayed neutron precursor
(DNP) drift in addition to the neutronic and thermal hydraulic phenomena typical of other …