On the use of the Serpent Monte Carlo code for few-group cross section generation

E. Fridman (Corresponding Author), Jaakko Leppänen

Research output: Contribution to journalArticleScientificpeer-review

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Abstract

Serpent is a recently developed 3D continuous-energy Monte Carlo (MC) reactor physics burnup calculation code. Serpent is specifically designed for lattice physics applications including generation of homogenized few-group constants for full-core core simulators.

Currently in Serpent, the few-group constants are obtained from the infinite-lattice calculations with zero neutron current at the outer boundary. In this study, in order to account for the non-physical infinite-lattice approximation, B1 methodology, routinely used by deterministic lattice transport codes, was considered for generation of leakage-corrected few-group cross sections in the Serpent code. A preliminary assessment of the applicability of the B1 methodology for generation of few-group constants in the Serpent code was carried out according to the following steps. Initially, the two-group constants generated by Serpent were compared with those calculated by Helios deterministic lattice transport code. Then, a 3D analysis of a Pressurized Water Reactor (PWR) core was performed by the nodal diffusion code DYN3D employing two-group cross section sets generated by Serpent and Helios. At this stage thermal–hydraulic (T-H) feedback was neglected. The DYN3D results were compared with those obtained from the 3D full core Serpent MC calculations. Finally, the full core DYN3D calculations were repeated taking into account T-H feedback and assuming Hot Full Power (HFP) conditions.

The B1 two-group cross sections and diffusion coefficients generated by the Serpent and Helios codes agree within less than 2.5%. The results of the DYN3D calculations with the Serpent B1 cross section sets agree very well with those of the Serpent full core MC calculations. The relative difference in keff is below 300 pcm. The maximum and root mean square (RMS) difference in the radial power distribution is 2.7% and 1.1% respectively. The results of the DYN3D full core calculations with T-H feedback obtained with Helios and Serpent generated cross section libraries show an excellent agreement as well. The estimated critical boron concentration agrees within 5 ppm. The maximum and RMS difference in the core radial power peaking factors is 0.8% and 0.4% respectively.

In this study, a Matlab script was used for calculation of the leakage-corrected few-group cross sections, however, the B1 methodology has recently been implemented directly in the Serpent code.
Original languageEnglish
Pages (from-to)1399-1405
Number of pages7
JournalAnnals of Nuclear Energy
Volume38
Issue number6
DOIs
Publication statusPublished - 2011
MoE publication typeA1 Journal article-refereed

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Physics
Reactor cores
Pressurized water reactors
Boron
Neutrons
Simulators

Keywords

  • Monte Carlo
  • Lattice physics
  • Few-group cross section generation
  • Critical spectrum
  • 3D core analysis

Cite this

@article{1377e7ff9db74e5eb5941d63fb3f09d8,
title = "On the use of the Serpent Monte Carlo code for few-group cross section generation",
abstract = "Serpent is a recently developed 3D continuous-energy Monte Carlo (MC) reactor physics burnup calculation code. Serpent is specifically designed for lattice physics applications including generation of homogenized few-group constants for full-core core simulators.Currently in Serpent, the few-group constants are obtained from the infinite-lattice calculations with zero neutron current at the outer boundary. In this study, in order to account for the non-physical infinite-lattice approximation, B1 methodology, routinely used by deterministic lattice transport codes, was considered for generation of leakage-corrected few-group cross sections in the Serpent code. A preliminary assessment of the applicability of the B1 methodology for generation of few-group constants in the Serpent code was carried out according to the following steps. Initially, the two-group constants generated by Serpent were compared with those calculated by Helios deterministic lattice transport code. Then, a 3D analysis of a Pressurized Water Reactor (PWR) core was performed by the nodal diffusion code DYN3D employing two-group cross section sets generated by Serpent and Helios. At this stage thermal–hydraulic (T-H) feedback was neglected. The DYN3D results were compared with those obtained from the 3D full core Serpent MC calculations. Finally, the full core DYN3D calculations were repeated taking into account T-H feedback and assuming Hot Full Power (HFP) conditions.The B1 two-group cross sections and diffusion coefficients generated by the Serpent and Helios codes agree within less than 2.5{\%}. The results of the DYN3D calculations with the Serpent B1 cross section sets agree very well with those of the Serpent full core MC calculations. The relative difference in keff is below 300 pcm. The maximum and root mean square (RMS) difference in the radial power distribution is 2.7{\%} and 1.1{\%} respectively. The results of the DYN3D full core calculations with T-H feedback obtained with Helios and Serpent generated cross section libraries show an excellent agreement as well. The estimated critical boron concentration agrees within 5 ppm. The maximum and RMS difference in the core radial power peaking factors is 0.8{\%} and 0.4{\%} respectively.In this study, a Matlab script was used for calculation of the leakage-corrected few-group cross sections, however, the B1 methodology has recently been implemented directly in the Serpent code.",
keywords = "Monte Carlo, Lattice physics, Few-group cross section generation, Critical spectrum, 3D core analysis",
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On the use of the Serpent Monte Carlo code for few-group cross section generation. / Fridman, E. (Corresponding Author); Leppänen, Jaakko.

In: Annals of Nuclear Energy, Vol. 38, No. 6, 2011, p. 1399-1405.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

T1 - On the use of the Serpent Monte Carlo code for few-group cross section generation

AU - Fridman, E.

AU - Leppänen, Jaakko

PY - 2011

Y1 - 2011

N2 - Serpent is a recently developed 3D continuous-energy Monte Carlo (MC) reactor physics burnup calculation code. Serpent is specifically designed for lattice physics applications including generation of homogenized few-group constants for full-core core simulators.Currently in Serpent, the few-group constants are obtained from the infinite-lattice calculations with zero neutron current at the outer boundary. In this study, in order to account for the non-physical infinite-lattice approximation, B1 methodology, routinely used by deterministic lattice transport codes, was considered for generation of leakage-corrected few-group cross sections in the Serpent code. A preliminary assessment of the applicability of the B1 methodology for generation of few-group constants in the Serpent code was carried out according to the following steps. Initially, the two-group constants generated by Serpent were compared with those calculated by Helios deterministic lattice transport code. Then, a 3D analysis of a Pressurized Water Reactor (PWR) core was performed by the nodal diffusion code DYN3D employing two-group cross section sets generated by Serpent and Helios. At this stage thermal–hydraulic (T-H) feedback was neglected. The DYN3D results were compared with those obtained from the 3D full core Serpent MC calculations. Finally, the full core DYN3D calculations were repeated taking into account T-H feedback and assuming Hot Full Power (HFP) conditions.The B1 two-group cross sections and diffusion coefficients generated by the Serpent and Helios codes agree within less than 2.5%. The results of the DYN3D calculations with the Serpent B1 cross section sets agree very well with those of the Serpent full core MC calculations. The relative difference in keff is below 300 pcm. The maximum and root mean square (RMS) difference in the radial power distribution is 2.7% and 1.1% respectively. The results of the DYN3D full core calculations with T-H feedback obtained with Helios and Serpent generated cross section libraries show an excellent agreement as well. The estimated critical boron concentration agrees within 5 ppm. The maximum and RMS difference in the core radial power peaking factors is 0.8% and 0.4% respectively.In this study, a Matlab script was used for calculation of the leakage-corrected few-group cross sections, however, the B1 methodology has recently been implemented directly in the Serpent code.

AB - Serpent is a recently developed 3D continuous-energy Monte Carlo (MC) reactor physics burnup calculation code. Serpent is specifically designed for lattice physics applications including generation of homogenized few-group constants for full-core core simulators.Currently in Serpent, the few-group constants are obtained from the infinite-lattice calculations with zero neutron current at the outer boundary. In this study, in order to account for the non-physical infinite-lattice approximation, B1 methodology, routinely used by deterministic lattice transport codes, was considered for generation of leakage-corrected few-group cross sections in the Serpent code. A preliminary assessment of the applicability of the B1 methodology for generation of few-group constants in the Serpent code was carried out according to the following steps. Initially, the two-group constants generated by Serpent were compared with those calculated by Helios deterministic lattice transport code. Then, a 3D analysis of a Pressurized Water Reactor (PWR) core was performed by the nodal diffusion code DYN3D employing two-group cross section sets generated by Serpent and Helios. At this stage thermal–hydraulic (T-H) feedback was neglected. The DYN3D results were compared with those obtained from the 3D full core Serpent MC calculations. Finally, the full core DYN3D calculations were repeated taking into account T-H feedback and assuming Hot Full Power (HFP) conditions.The B1 two-group cross sections and diffusion coefficients generated by the Serpent and Helios codes agree within less than 2.5%. The results of the DYN3D calculations with the Serpent B1 cross section sets agree very well with those of the Serpent full core MC calculations. The relative difference in keff is below 300 pcm. The maximum and root mean square (RMS) difference in the radial power distribution is 2.7% and 1.1% respectively. The results of the DYN3D full core calculations with T-H feedback obtained with Helios and Serpent generated cross section libraries show an excellent agreement as well. The estimated critical boron concentration agrees within 5 ppm. The maximum and RMS difference in the core radial power peaking factors is 0.8% and 0.4% respectively.In this study, a Matlab script was used for calculation of the leakage-corrected few-group cross sections, however, the B1 methodology has recently been implemented directly in the Serpent code.

KW - Monte Carlo

KW - Lattice physics

KW - Few-group cross section generation

KW - Critical spectrum

KW - 3D core analysis

U2 - 10.1016/j.anucene.2011.01.032

DO - 10.1016/j.anucene.2011.01.032

M3 - Article

VL - 38

SP - 1399

EP - 1405

JO - Annals of Nuclear Energy

JF - Annals of Nuclear Energy

SN - 0306-4549

IS - 6

ER -