Title: A multiphysics simulation suite for liquid metal-cooled fast reactors

Journal Article · · Annals of Nuclear Energy

Not Available

Sponsoring Organization:
USDOE Office of Nuclear Energy (NE)
OSTI ID:
1815239
Journal Information:
Annals of Nuclear Energy, Journal Name: Annals of Nuclear Energy Journal Issue: C Vol. 159; ISSN 0306-4549
Publisher:
ElsevierCopyright Statement
Country of Publication:
United Kingdom
Language:
English

References (13)

Thermal conductivity and thermal expansion of stainless steels D9 and HT9 journal September 1988
Material property correlations for uranium mononitride journal May 1990
Material property correlations for uranium mononitride journal May 1990
Implications of the EBR-II inherent safety demonstration test journal April 1987
Metallic fast reactor fuels journal January 1997
An evaluation of the properties of As-cast U-rich U–Zr alloys journal July 2009
Thermal conductivities of actinides (U, Pu, Np, Cm, Am) and uranium-alloys (U–Zr, U–Pu–Zr and U–Pu–TRU–Zr) journal February 2014
A Multiphysics Simulation Suite for Sodium Cooled fast Reactors journal January 2021
MC 2 -3: Multigroup Cross Section Generation Code for Fast Reactor Analysis journal June 2017
Asymptotic Derivation of the Multigroup P 1 and Simplified P N Equations with Anisotropic Scattering journal July 1996
The Simplified P 3 Approximation journal January 2000
DIF3D: a code to solve one-, two-, and three-dimensional finite-difference diffusion theory problems. [LMFBR] report April 1984
Thermodynamic and transport properties of sodium liquid and vapor report January 1995

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