Fast Reactor Calculations with MCNP, PSG/Serpent and ERANOS

Research output: Chapter in Book/Report/Conference proceedingChapter or book articleProfessional

Abstract

Evaluated reactor physics benchmark exercises were calculated with both stochastic Monte Carlo and deterministic codes over the period of the NETNUC project. The Monte Carlo codes MCNP and PSG (early version of Serpent) were used to calculate the benchmark of the Japanese sodium-cooled fast reactor JOYO, after which some features of the ZPR-6/7 (Zero Power Reactor at Argonne, USA) benchmark were calculated with the deterministic ERANOS code system. The JOYO calculations were performed to determine the keff for two separate core configurations, control rod reactivity curves for the two regular rods, sodium void reactivity for seven various fuel assembly locations and the isothermal temperature coefficient. The calculated results were compared between the codes and to the experimental results. The codes mostly yielded mutually pretty consistent results, but in some cases the discrepancy with the experimental observations was significant. Also the limitations of the Monte Carlo method due to its statistical uncertainty became obvious, when small reactivity differences were present. The steady-state fast reactor physics code package ERANOS was introduced to extend VTT's deterministic calculation capabilities to fast neutron spectrum device. It was employed to calculate parts of the ZPR-6/7 benchmark with objectives to determine how it behaves along with JEFF-3.1 and -3.1.1 nuclear data against the experimental values, and how the different functions and parameters of the code package perform against each other. The method and geometry choice proved to be a significant factor in some cases, meanwhile the minor parameters did not generally have any major effect.
Original languageEnglish
Title of host publicationNew Type Nuclear Reactors (NETNUC) 2008-2011 Final Report
EditorsHeikki Suikkanen
PublisherLappeenranta University of Technology
Pages92-102
ISBN (Print)978-952-265-251-5
Publication statusPublished - 2012
MoE publication typeD2 Article in professional manuals or guides or professional information systems or text book material

Publication series

NameLUT Energy Research report
PublisherLappeenranta University of Technology
Number23
ISSN (Print)1798-1328

Fingerprint

reactors
reactor physics
reactivity
zero power reactors
sodium
control rods
neutron spectra
physical exercise
fast neutrons
Monte Carlo method
voids
rods
assembly
curves
coefficients
geometry
configurations
temperature

Cite this

Juutilainen, P. (2012). Fast Reactor Calculations with MCNP, PSG/Serpent and ERANOS. In H. Suikkanen (Ed.), New Type Nuclear Reactors (NETNUC) 2008-2011 Final Report (pp. 92-102). Lappeenranta University of Technology. Lappeenranta University of Technology: Energy. Research report, No. 23
Juutilainen, Pauli. / Fast Reactor Calculations with MCNP, PSG/Serpent and ERANOS. New Type Nuclear Reactors (NETNUC) 2008-2011 Final Report. editor / Heikki Suikkanen. Lappeenranta University of Technology, 2012. pp. 92-102 (Lappeenranta University of Technology: Energy. Research report; No. 23).
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abstract = "Evaluated reactor physics benchmark exercises were calculated with both stochastic Monte Carlo and deterministic codes over the period of the NETNUC project. The Monte Carlo codes MCNP and PSG (early version of Serpent) were used to calculate the benchmark of the Japanese sodium-cooled fast reactor JOYO, after which some features of the ZPR-6/7 (Zero Power Reactor at Argonne, USA) benchmark were calculated with the deterministic ERANOS code system. The JOYO calculations were performed to determine the keff for two separate core configurations, control rod reactivity curves for the two regular rods, sodium void reactivity for seven various fuel assembly locations and the isothermal temperature coefficient. The calculated results were compared between the codes and to the experimental results. The codes mostly yielded mutually pretty consistent results, but in some cases the discrepancy with the experimental observations was significant. Also the limitations of the Monte Carlo method due to its statistical uncertainty became obvious, when small reactivity differences were present. The steady-state fast reactor physics code package ERANOS was introduced to extend VTT's deterministic calculation capabilities to fast neutron spectrum device. It was employed to calculate parts of the ZPR-6/7 benchmark with objectives to determine how it behaves along with JEFF-3.1 and -3.1.1 nuclear data against the experimental values, and how the different functions and parameters of the code package perform against each other. The method and geometry choice proved to be a significant factor in some cases, meanwhile the minor parameters did not generally have any major effect.",
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Juutilainen, P 2012, Fast Reactor Calculations with MCNP, PSG/Serpent and ERANOS. in H Suikkanen (ed.), New Type Nuclear Reactors (NETNUC) 2008-2011 Final Report. Lappeenranta University of Technology, Lappeenranta University of Technology: Energy. Research report, no. 23, pp. 92-102.

Fast Reactor Calculations with MCNP, PSG/Serpent and ERANOS. / Juutilainen, Pauli.

New Type Nuclear Reactors (NETNUC) 2008-2011 Final Report. ed. / Heikki Suikkanen. Lappeenranta University of Technology, 2012. p. 92-102 (Lappeenranta University of Technology: Energy. Research report; No. 23).

Research output: Chapter in Book/Report/Conference proceedingChapter or book articleProfessional

TY - CHAP

T1 - Fast Reactor Calculations with MCNP, PSG/Serpent and ERANOS

AU - Juutilainen, Pauli

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N2 - Evaluated reactor physics benchmark exercises were calculated with both stochastic Monte Carlo and deterministic codes over the period of the NETNUC project. The Monte Carlo codes MCNP and PSG (early version of Serpent) were used to calculate the benchmark of the Japanese sodium-cooled fast reactor JOYO, after which some features of the ZPR-6/7 (Zero Power Reactor at Argonne, USA) benchmark were calculated with the deterministic ERANOS code system. The JOYO calculations were performed to determine the keff for two separate core configurations, control rod reactivity curves for the two regular rods, sodium void reactivity for seven various fuel assembly locations and the isothermal temperature coefficient. The calculated results were compared between the codes and to the experimental results. The codes mostly yielded mutually pretty consistent results, but in some cases the discrepancy with the experimental observations was significant. Also the limitations of the Monte Carlo method due to its statistical uncertainty became obvious, when small reactivity differences were present. The steady-state fast reactor physics code package ERANOS was introduced to extend VTT's deterministic calculation capabilities to fast neutron spectrum device. It was employed to calculate parts of the ZPR-6/7 benchmark with objectives to determine how it behaves along with JEFF-3.1 and -3.1.1 nuclear data against the experimental values, and how the different functions and parameters of the code package perform against each other. The method and geometry choice proved to be a significant factor in some cases, meanwhile the minor parameters did not generally have any major effect.

AB - Evaluated reactor physics benchmark exercises were calculated with both stochastic Monte Carlo and deterministic codes over the period of the NETNUC project. The Monte Carlo codes MCNP and PSG (early version of Serpent) were used to calculate the benchmark of the Japanese sodium-cooled fast reactor JOYO, after which some features of the ZPR-6/7 (Zero Power Reactor at Argonne, USA) benchmark were calculated with the deterministic ERANOS code system. The JOYO calculations were performed to determine the keff for two separate core configurations, control rod reactivity curves for the two regular rods, sodium void reactivity for seven various fuel assembly locations and the isothermal temperature coefficient. The calculated results were compared between the codes and to the experimental results. The codes mostly yielded mutually pretty consistent results, but in some cases the discrepancy with the experimental observations was significant. Also the limitations of the Monte Carlo method due to its statistical uncertainty became obvious, when small reactivity differences were present. The steady-state fast reactor physics code package ERANOS was introduced to extend VTT's deterministic calculation capabilities to fast neutron spectrum device. It was employed to calculate parts of the ZPR-6/7 benchmark with objectives to determine how it behaves along with JEFF-3.1 and -3.1.1 nuclear data against the experimental values, and how the different functions and parameters of the code package perform against each other. The method and geometry choice proved to be a significant factor in some cases, meanwhile the minor parameters did not generally have any major effect.

M3 - Chapter or book article

SN - 978-952-265-251-5

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BT - New Type Nuclear Reactors (NETNUC) 2008-2011 Final Report

A2 - Suikkanen, Heikki

PB - Lappeenranta University of Technology

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Juutilainen P. Fast Reactor Calculations with MCNP, PSG/Serpent and ERANOS. In Suikkanen H, editor, New Type Nuclear Reactors (NETNUC) 2008-2011 Final Report. Lappeenranta University of Technology. 2012. p. 92-102. (Lappeenranta University of Technology: Energy. Research report; No. 23).