Development of Monte Carlo neutron transport methods for reactor physics applications

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

Abstract

PSG (Probabilistic Scattering Game) is a new Monte Carlo neutron transport code, developed at the VTT Technical Research Centre of Finland. The code is specifically designed for reactor physics applications, particularly at the fuel assembly level. Group constant generation for deterministic reactor simulator codes is considered as one of the main motivations for PSG development. This paper presents an overview of the main features of PSG, together with some typical results.
Original languageEnglish
Title of host publicationSAFIR: The Finnish Research Programme on Nuclear Power Plant Safety 2003-2006
Subtitle of host publicationFinal Report
Place of PublicationEspoo
PublisherVTT Technical Research Centre of Finland
Pages41-47
ISBN (Electronic)951-38-6887-7
ISBN (Print)951-38-6886-9
Publication statusPublished - 2006
MoE publication typeNot Eligible

Publication series

NameVTT Tiedotteita - Research Notes
PublisherVTT
Number2363
ISSN (Print)1235-0605
ISSN (Electronic)1455-0865

Fingerprint

Neutrons
Physics
Scattering
Simulators

Cite this

Leppänen, J. (2006). Development of Monte Carlo neutron transport methods for reactor physics applications. In SAFIR: The Finnish Research Programme on Nuclear Power Plant Safety 2003-2006: Final Report (pp. 41-47). Espoo: VTT Technical Research Centre of Finland. VTT Tiedotteita - Research Notes, No. 2363
Leppänen, Jaakko. / Development of Monte Carlo neutron transport methods for reactor physics applications. SAFIR: The Finnish Research Programme on Nuclear Power Plant Safety 2003-2006: Final Report. Espoo : VTT Technical Research Centre of Finland, 2006. pp. 41-47 (VTT Tiedotteita - Research Notes; No. 2363).
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Leppänen, J 2006, Development of Monte Carlo neutron transport methods for reactor physics applications. in SAFIR: The Finnish Research Programme on Nuclear Power Plant Safety 2003-2006: Final Report. VTT Technical Research Centre of Finland, Espoo, VTT Tiedotteita - Research Notes, no. 2363, pp. 41-47.

Development of Monte Carlo neutron transport methods for reactor physics applications. / Leppänen, Jaakko.

SAFIR: The Finnish Research Programme on Nuclear Power Plant Safety 2003-2006: Final Report. Espoo : VTT Technical Research Centre of Finland, 2006. p. 41-47 (VTT Tiedotteita - Research Notes; No. 2363).

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

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AB - PSG (Probabilistic Scattering Game) is a new Monte Carlo neutron transport code, developed at the VTT Technical Research Centre of Finland. The code is specifically designed for reactor physics applications, particularly at the fuel assembly level. Group constant generation for deterministic reactor simulator codes is considered as one of the main motivations for PSG development. This paper presents an overview of the main features of PSG, together with some typical results.

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Leppänen J. Development of Monte Carlo neutron transport methods for reactor physics applications. In SAFIR: The Finnish Research Programme on Nuclear Power Plant Safety 2003-2006: Final Report. Espoo: VTT Technical Research Centre of Finland. 2006. p. 41-47. (VTT Tiedotteita - Research Notes; No. 2363).