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 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
| Series | VTT Tiedotteita - Research Notes |
|---|---|
| Number | 2363 |
| ISSN | 1235-0605 |
Fingerprint Dive into the research topics of 'Development of Monte Carlo neutron transport methods for reactor physics applications'. Together they form a unique fingerprint.
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). VTT Technical Research Centre of Finland. VTT Tiedotteita - Research Notes, No. 2363 http://www.vtt.fi/inf/pdf/tiedotteet/2006/T2363.pdf