Systems guide to MCNP (Monte Carlo Neutron and Photon Transport Code)
The subject of this report is the implementation of the Los Alamos National Laboratory Monte Carlo Neutron and Photon Transport Code - Version 3 (MCNP) on the different types of computer systems, especially the IBM MVS system. The report supplements the documentation of the RSIC computer code package CCC-200/MCNP. Details of the procedure to follow in executing MCNP on the IBM computers, either in batch mode or interactive mode, are provided.
- Publication Date:
- OSTI Identifier:
- Report Number(s):
- DOE Contract Number:
- Resource Type:
- Technical Report
- Resource Relation:
- Other Information: Portions are illegible in microfiche products. Original copy available until stock is exhausted
- Research Org:
- Oak Ridge National Lab., TN (USA)
- Country of Publication:
- United States
- 73 NUCLEAR PHYSICS AND RADIATION PHYSICS; COMPUTER CODES; M CODES; NEUTRON TRANSPORT; PHOTON TRANSPORT; IBM COMPUTERS; MANUALS; MONTE CARLO METHOD; COMPUTERS; DOCUMENT TYPES; NEUTRAL-PARTICLE TRANSPORT; RADIATION TRANSPORT 654003* -- Radiation & Shielding Physics-- Neutron Interactions with Matter
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