Concepedia

High fidelity simulation of conventional and innovative LWR with the coupled Monte-Carlo thermal-hydraulic system MCNP-SUBCHANFLOW

A. Ivanov, Robert Stieglitz, Kostadin Ivanov

Nuclear Engineering and Design · 2013 · 30 citations · 9 references

Concepts

EngineeringNuclear EngineeringPhysicsComputational Heat TransferComputational PhysicsHeat TransferHeat Transfer ModelingMonte Carlo SimulationThermal DesignThermal SimulationThermal-hydraulic Safety AnalysisHigh-fidelity Coupled SimulationThermal Hydraulic AnalysisThermal-hydraulic Code ValidationThermal-hydraulic CodesThermal-hydraulic CouplingThermal-hydraulic DesignThermal-hydraulics

References

9

MCNP-A General Monte Carlo N-Particle Transport Code

Judith F. Briesmeister · 1993 · 5.1K citations

Natural Sciences, Nuclear Engineering, Physics +13

International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (MC 2011)

Edward W. Larsen · Transport Theory and Statistical Physics · 2011 · 62 citations

Natural Sciences, Mathematics, Nuclear Engineering +14

Thermal Neutron Scattering Data for the Moderator Materials H2O, D2O and ZrHx in ENDF-6 Format and as ACE Library for MCNP(X) Codes

M. Mattes, J. Keinert · 2005 · 59 citations · Full text

Natural Sciences, Materials Science, Physics +17

BURNUP CALCULATION CAPABILITY IN THE PSG2 / SERPENT MONTE CARLO REACTOR PHYSICS CODE

Jaakko Lepp, Maria Pusa · 2009 · 34 citations

Engineering, Nuclear Engineering, Computational Physics +16

Development of a coupling scheme between MCNP and COBRA-TF for the prediction of the pin power of a PWR fuel assembly

Víctor Hugo Sánchez-Espinoza, Ammar Al‐Hamry · 2009 · 27 citations

Engineering, Nuclear Engineering, Nuclear Fuel Cycle +10