Direct-coupled-ray method for three-dimensional shielding analysis
Description
A fast, three-dimensional design-oriented transport method has been developed for the solution of both neutron and gamma shielding problems. It combines a nodal approach with analytic integral transport to achieve relative speed and accuracy. An analytic solution is obtained for each of 14 angular fluxes in each mesh block of a three-dimensional assembly. The directions are such that the outgoing angular flux components in one mesh block become the incoming angular flux components in the adjacent mesh blocks. The approach is therefore described as the Direct-Coupled-Ray (DCR) method. The DCR method with full anisotropic scattering capability, variable mesh capability, and generalized boundary conditions, has been implemented in the TRANS3 code. Several benchmark calculations and numerous scoping calculations were performed using problems representative of LMFBR shielding configurations. These included a 1-D deep penetration configuration and one-, two-, and three-dimensional representations of the lower axial shield of the Clinch River Breeder Reactor
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.
Files
Additional details
Publishing Information
- Imprint Pagination
- 9 p.
- Report number
- CONF-770401--9
Conference
- Title
- 5. international conference on reactor shielding.
- Dates
- 18 - 22 Apr 1977.
- Place
- Knoxville, Tennessee, United States of America (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 8330814
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CLINCH RIVER BREEDER REACTOR; COMPUTER CODES; MATHEMATICAL MODELS; NEUTRON TRANSPORT THEORY; SHIELDING; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- BREEDER REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; POWER REACTORS; REACTORS; SODIUM COOLED REACTORS; TRANSPORT THEORY