Published May 1999
| Version v1
Report
MCNP-calculations at the Department of Reactor Physics
Description
The MCNP-code is a general Monte Carlo code for arbitrary three-dimensional geometries. The detection can be made in many different ways, of which we have tested a few. We have made tests of the MCNP-code using simple geometries. The code is very suitable for testing experimental setups. We also give an example of such a calculation
Additional details
Publishing Information
- Imprint Title
- Reactor physics calculations in the Nordic countries
- Imprint Pagination
- 307 p.
- Journal Page Range
- p. 30.1-30.9
- Report number
- NEI-SE--290
Conference
- Title
- Reactor physics calculations in the Nordic countries
- Dates
- 6-7 May 1999
- Place
- Goeteborg (Sweden)
INIS
- Country of Publication
- Sweden
- Country of Input or Organization
- Sweden
- INIS RN
- 30029839
- Subject category
- S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- MONTE CARLO METHOD; NEUTRON FLUENCE; NEUTRON TRANSPORT THEORY; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- CALCULATION METHODS; TRANSPORT THEORY
Optional Information
- Notes
- 8 figs