SNAP - a three dimensional neutron diffusion code
Description
This report describes a one- two- three-dimensional multi-group diffusion code, SNAP, which is primarily intended for neutron diffusion calculations but can also carry out gamma calculations if the diffusion approximation is accurate enough. It is suitable for fast and thermal reactor core calculations and for shield calculations. SNAP can solve the multi-group neutron diffusion equations using finite difference methods. The one-dimensional slab, cylindrical and spherical geometries and the two-dimensional case are all treated as simple special cases of three-dimensional geometries. Numerous reflective and periodic symmetry options are available and may be used to reduce the number of mesh points necessary to represent the system. Extrapolation lengths can be specified at internal and external boundaries. (Author)
Availability note (English)
MF available from INIS under the Report Number.
Files
Additional details
Publishing Information
- Imprint Pagination
- [205 p.].
- Report number
- AEA-RS--1214
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 24059513
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- FAST NEUTRONS; FINITE DIFFERENCE METHOD; GAMMA TRANSPORT THEORY; GEOMETRY; MULTIGROUP THEORY; NEUTRON DIFFUSION EQUATION; NEUTRON TRANSPORT; ONE-DIMENSIONAL CALCULATIONS; REACTOR CORES; S CODES; THERMAL NEUTRONS; THERMAL SHIELDS; THREE-DIMENSIONAL CALCULATIONS; TWO-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- BARYONS; CALCULATION METHODS; COMPUTER CODES; ELEMENTARY PARTICLES; FERMIONS; HADRONS; ITERATIVE METHODS; MATHEMATICS; NEUTRAL-PARTICLE TRANSPORT; NEUTRONS; NUCLEONS; NUMERICAL SOLUTION; RADIATION TRANSPORT; REACTOR COMPONENTS; SHIELDS; TRANSPORT THEORY