Abstract
| Original language | English |
|---|---|
| Title of host publication | SAFIR: The Finnish Research Programme on Nuclear Power Plant Safety 2003-2006 |
| Subtitle of host publication | Final Report |
| Place of Publication | Espoo |
| Publisher | VTT Technical Research Centre of Finland |
| Pages | 41-47 |
| ISBN (Electronic) | 951-38-6887-7 |
| ISBN (Print) | 951-38-6886-9 |
| Publication status | Published - 2006 |
| MoE publication type | Not Eligible |
Publication series
| Name | VTT Tiedotteita - Research Notes |
|---|---|
| Publisher | VTT |
| Number | 2363 |
| ISSN (Print) | 1235-0605 |
| ISSN (Electronic) | 1455-0865 |
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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 proceeding › Chapter or book article › Professional
TY - CHAP
T1 - Development of Monte Carlo neutron transport methods for reactor physics applications
AU - Leppänen, Jaakko
PY - 2006
Y1 - 2006
N2 - 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.
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.
M3 - Chapter or book article
SN - 951-38-6886-9
T3 - VTT Tiedotteita - Research Notes
SP - 41
EP - 47
BT - SAFIR: The Finnish Research Programme on Nuclear Power Plant Safety 2003-2006
PB - VTT Technical Research Centre of Finland
CY - Espoo
ER -