Current Status of the PSG Monte Carlo Neutron Transport Code

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

4 Citations (Scopus)

Abstract

PSG is a new Monte Carlo neutron transport code, developed at the Technical Research Centre of Finland (VTT). The code is mainly intended for fuel assembly-level reactor physics calculations, such as group constant generation for deterministic reactor simulator codes. This paper presents the current status of the project and the essential capabilities of the code. Although the main application of PSG is in lattice calculations, the geometry is not restricted in two dimensions. This paper presents the validation of PSG against the experimental results of the three-dimensional MOX fuelled VENUS-2 reactor dosimetry benchmark.
Original languageEnglish
Title of host publicationPHYSOR 2006: American Nuclear Society's Topical Meeting on Reactor Physics
Subtitle of host publicationAdvances in Nuclear Analysis and Simulation
PublisherAmerican Nuclear Society ANS
Number of pages10
ISBN (Electronic)978-0-89448-697-5
ISBN (Print)0-89448-697-7
Publication statusPublished - 2006
MoE publication typeA4 Article in a conference publication
EventAmerican Nuclear Society's Topical Meeting on Reactor Physics - Advances in Nuclear Analysis and Simulation, PHYSOR-2006 - Vancouver, Canada
Duration: 10 Sep 200614 Sep 2006

Conference

ConferenceAmerican Nuclear Society's Topical Meeting on Reactor Physics - Advances in Nuclear Analysis and Simulation, PHYSOR-2006
CountryCanada
CityVancouver
Period10/09/0614/09/06

Fingerprint

neutrons
reactor physics
reactors
Finland
simulators
dosimeters
assembly
geometry

Cite this

Leppänen, J. (2006). Current Status of the PSG Monte Carlo Neutron Transport Code. In PHYSOR 2006: American Nuclear Society's Topical Meeting on Reactor Physics: Advances in Nuclear Analysis and Simulation American Nuclear Society ANS.
Leppänen, Jaakko. / Current Status of the PSG Monte Carlo Neutron Transport Code. PHYSOR 2006: American Nuclear Society's Topical Meeting on Reactor Physics: Advances in Nuclear Analysis and Simulation. American Nuclear Society ANS, 2006.
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title = "Current Status of the PSG Monte Carlo Neutron Transport Code",
abstract = "PSG is a new Monte Carlo neutron transport code, developed at the Technical Research Centre of Finland (VTT). The code is mainly intended for fuel assembly-level reactor physics calculations, such as group constant generation for deterministic reactor simulator codes. This paper presents the current status of the project and the essential capabilities of the code. Although the main application of PSG is in lattice calculations, the geometry is not restricted in two dimensions. This paper presents the validation of PSG against the experimental results of the three-dimensional MOX fuelled VENUS-2 reactor dosimetry benchmark.",
author = "Jaakko Lepp{\"a}nen",
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isbn = "0-89448-697-7",
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}

Leppänen, J 2006, Current Status of the PSG Monte Carlo Neutron Transport Code. in PHYSOR 2006: American Nuclear Society's Topical Meeting on Reactor Physics: Advances in Nuclear Analysis and Simulation. American Nuclear Society ANS, American Nuclear Society's Topical Meeting on Reactor Physics - Advances in Nuclear Analysis and Simulation, PHYSOR-2006, Vancouver, Canada, 10/09/06.

Current Status of the PSG Monte Carlo Neutron Transport Code. / Leppänen, Jaakko.

PHYSOR 2006: American Nuclear Society's Topical Meeting on Reactor Physics: Advances in Nuclear Analysis and Simulation. American Nuclear Society ANS, 2006.

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

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N2 - PSG is a new Monte Carlo neutron transport code, developed at the Technical Research Centre of Finland (VTT). The code is mainly intended for fuel assembly-level reactor physics calculations, such as group constant generation for deterministic reactor simulator codes. This paper presents the current status of the project and the essential capabilities of the code. Although the main application of PSG is in lattice calculations, the geometry is not restricted in two dimensions. This paper presents the validation of PSG against the experimental results of the three-dimensional MOX fuelled VENUS-2 reactor dosimetry benchmark.

AB - PSG is a new Monte Carlo neutron transport code, developed at the Technical Research Centre of Finland (VTT). The code is mainly intended for fuel assembly-level reactor physics calculations, such as group constant generation for deterministic reactor simulator codes. This paper presents the current status of the project and the essential capabilities of the code. Although the main application of PSG is in lattice calculations, the geometry is not restricted in two dimensions. This paper presents the validation of PSG against the experimental results of the three-dimensional MOX fuelled VENUS-2 reactor dosimetry benchmark.

M3 - Conference article in proceedings

SN - 0-89448-697-7

BT - PHYSOR 2006: American Nuclear Society's Topical Meeting on Reactor Physics

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Leppänen J. Current Status of the PSG Monte Carlo Neutron Transport Code. In PHYSOR 2006: American Nuclear Society's Topical Meeting on Reactor Physics: Advances in Nuclear Analysis and Simulation. American Nuclear Society ANS. 2006