A multiphysics model of the versatile test reactor based on the MOOSE framework

Author:

Martin Nicolas,Stewart Ryan,Bays Sam

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference44 articles.

1. Lee, C., Jung, Y.S., Yang, W.S., MC2-3, 2018: Multigroup cross section generation code for fast nuclear reactor analysis, doi:10.2172/1483949, URL: https://www.osti.gov/biblio/1483949.

2. Palmiotti, G., Carrico, C.B, Lewis, E.E., 1993. Variational nodal transport methods with anisotropic scattering. Nucl. Sci. Eng. 115 (3) 233–243, URL:https://doi.org/10.13182/NSE92-110.

3. Argonne reactor code software verification and validation plan for the versatile test reactor;Smith;Tech. rep., Argonne National Laboratory,2018

4. Slaughter, A.E., Prince, Z.M.. MOOSE Modules: stochastic tools user manual.

5. VARI3D & PERSENT: Perturbation and sensitivity analysis;Smith;Tech. rep., Argonne National Laboratory,2013

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