MORSE Monte Carlo radiation transport code system
Description
For a number of years the MORSE user community has requested additional help in setting up problems using various options. The sample problems distributed with MORSE did not fully demonstrate the capability of the code. At Oak Ridge National Laboratory the code originators had a complete set of sample problems, but funds for documenting and distributing them were never available. Recently the number of requests for listings of input data and results for running some particular option the user was trying to implement has increased to the point where it is not feasible to handle them on an individual basis. Consequently it was decided to package a set of sample problems which illustrates more adequately how to run MORSE. This write-up may be added to Part III of the MORSE report. These sample problems include a combined neutron-gamma case, a neutron only case, a gamma only case, an adjoint case, a fission case, a time-dependent fission case, the collision density case, an XCHEKR run and a PICTUR run
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC E03/MF A01 as DE84017312.Files
16029296.pdf
Files
(2.4 MB)
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Additional details
Additional titles
- Augmented title (English)
- Sample problems
Publishing Information
- Imprint Pagination
- 48 p.
- Report number
- ORNL--4972/R2
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16029296
- Subject category
- S73: NUCLEAR PHYSICS AND RADIATION PHYSICS; S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- COMPUTER CALCULATIONS; COMPUTER CODES; FISSION; M CODES; MONTE CARLO METHOD; NEUTRON TRANSPORT; PHOTON TRANSPORT; RADIATION TRANSPORT
- Descriptors DEC
- NEUTRAL-PARTICLE TRANSPORT; NUCLEAR REACTIONS