Development and validation of PROTEUS-NODAL transient analyses capabilities for molten salt reactors
Author:
Funder
US Department of Energy
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
Reference70 articles.
1. Handbook of Generation IV Nuclear Reactors: Molten Salt Fast Reactors;Allibert,2016
2. Preliminary design and analysis of Liquid Fuel Molten Salt Reactor using multi-physics code GeN-Foam;Ramzy Altahhan;Nucl. Eng. Des.,2020
3. Development of an OpenFOAM model for the Molten Salt Fast Reactor transient analysis;Aufiero;Chem. Eng. Sci.,2014
4. Calculating the effective delayed neutron fraction in the Molten Salt Fast Reactor: analytical, deterministic and Monte Carlo approaches;Aufiero;Ann. Nucl. Energy,2014
5. Development of Triangle-based Polynomial Expansion Nodal SP3 Method for Hexagonal Core Transport Calculation;Bae,2010
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