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 language | English |
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| Title of host publication | Advances in Nuclear Analysis and Simulation |
| Subtitle of host publication | PHYSOR 2006 |
| Publisher | American Nuclear Society (ANS) |
| Pages | 1000-1009 |
| Volume | 2 |
| ISBN (Print) | 978-0-89448-697-5 |
| Publication status | Published - 2006 |
| MoE publication type | A4 Article in a conference publication |
| Event | American Nuclear Society's Topical Meeting on Reactor Physics - Advances in Nuclear Analysis and Simulation, PHYSOR-2006 - Vancouver, Canada Duration: 10 Sept 2006 → 14 Sept 2006 |
Conference
| Conference | American Nuclear Society's Topical Meeting on Reactor Physics - Advances in Nuclear Analysis and Simulation, PHYSOR-2006 |
|---|---|
| Country/Territory | Canada |
| City | Vancouver |
| Period | 10/09/06 → 14/09/06 |