Porth Ymchwil

Monte Carlo and nodal neutron physics calculations of the IAEA MTR benchmark using Serpent/DYN3D code system

Allbwn ymchwil: Cyfraniad at gyfnodolyn › Erthygl › adolygiad gan gymheiriaid

StandardStandard

Monte Carlo and nodal neutron physics calculations of the IAEA MTR benchmark using Serpent/DYN3D code system. / Margulis, Marat; Negev, Erez.
Yn: Progress in Nuclear Energy, Cyfrol 88, 04.2016, t. 118-133.

Allbwn ymchwil: Cyfraniad at gyfnodolyn › Erthygl › adolygiad gan gymheiriaid

HarvardHarvard

Margulis, M & Negev, E 2016, 'Monte Carlo and nodal neutron physics calculations of the IAEA MTR benchmark using Serpent/DYN3D code system', Progress in Nuclear Energy, cyfrol. 88, tt. 118-133. https://doi.org/10.1016/j.pnucene.2015.12.008

APA

Margulis, M., & Negev, E. (2016). Monte Carlo and nodal neutron physics calculations of the IAEA MTR benchmark using Serpent/DYN3D code system. Progress in Nuclear Energy, 88, 118-133. https://doi.org/10.1016/j.pnucene.2015.12.008

CBE

Margulis M, Negev E. 2016. Monte Carlo and nodal neutron physics calculations of the IAEA MTR benchmark using Serpent/DYN3D code system. Progress in Nuclear Energy. 88:118-133. https://doi.org/10.1016/j.pnucene.2015.12.008

MLA

Margulis, Marat a Erez Negev. "Monte Carlo and nodal neutron physics calculations of the IAEA MTR benchmark using Serpent/DYN3D code system". Progress in Nuclear Energy. 2016, 88. 118-133. https://doi.org/10.1016/j.pnucene.2015.12.008

VancouverVancouver

Margulis M, Negev E. Monte Carlo and nodal neutron physics calculations of the IAEA MTR benchmark using Serpent/DYN3D code system. Progress in Nuclear Energy. 2016 Ebr;88:118-133. Epub 2016 Ion 9. doi: 10.1016/j.pnucene.2015.12.008

Author

Margulis, Marat ; Negev, Erez. / Monte Carlo and nodal neutron physics calculations of the IAEA MTR benchmark using Serpent/DYN3D code system. Yn: Progress in Nuclear Energy. 2016 ; Cyfrol 88. tt. 118-133.

RIS

TY - JOUR

T1 - Monte Carlo and nodal neutron physics calculations of the IAEA MTR benchmark using Serpent/DYN3D code system

AU - Margulis, Marat

AU - Negev, Erez

PY - 2016/4

Y1 - 2016/4

N2 - As part of recent efforts to utilize NPPs computational methodologies to safety analysis of research reactors, the Serpent and DYN3D codes were extensively compared with a variety of static and burnup calculations as defined in the IAEA benchmark for 10 MW MTR pool-type reactor. These calculations include unit cell calculations and few group constants generation, unit cell and full core k-eigenvalue and burnup calculations, and full core 3D flux and power distributions. The Serpent code capabilities as a lattice code for MTR plate-type fuel assemblies were evaluated and compared with EPRI-CELL and WIMS-D4 results and reference solutions for full 3D core models were compared with MCNP5 and OpenMC results. The DYN3D nodal diffusion code capabilities in modeling full 3D MTR cores were also evaluated using few group cross sections and assembly discontinuity factors obtained by Serpent unit cell calculations. The DYN3D results were compared with Serpent, MCNP5 and OpenMC.

AB - As part of recent efforts to utilize NPPs computational methodologies to safety analysis of research reactors, the Serpent and DYN3D codes were extensively compared with a variety of static and burnup calculations as defined in the IAEA benchmark for 10 MW MTR pool-type reactor. These calculations include unit cell calculations and few group constants generation, unit cell and full core k-eigenvalue and burnup calculations, and full core 3D flux and power distributions. The Serpent code capabilities as a lattice code for MTR plate-type fuel assemblies were evaluated and compared with EPRI-CELL and WIMS-D4 results and reference solutions for full 3D core models were compared with MCNP5 and OpenMC results. The DYN3D nodal diffusion code capabilities in modeling full 3D MTR cores were also evaluated using few group cross sections and assembly discontinuity factors obtained by Serpent unit cell calculations. The DYN3D results were compared with Serpent, MCNP5 and OpenMC.

KW - Serpent

KW - DYN3D

KW - Monte Carlo

KW - Reactor physics

KW - Burnup

KW - Research reactor

U2 - 10.1016/j.pnucene.2015.12.008

DO - 10.1016/j.pnucene.2015.12.008

M3 - Article

VL - 88

SP - 118

EP - 133

JO - Progress in Nuclear Energy

JF - Progress in Nuclear Energy

SN - 0149-1970

ER -