Certification of MCNP version 4A for WHC computer platforms
MCNP is a general-purpose Monte Carlo code that can be used for neutron, photon, or coupled neutron/photon transport, including the capability to calculate eigenvalues for critical systems. The code treats an arbitrary three-dimensional configuration of materials in geometric cells bounded by first- and second-degree surfaces, and some special fourth-degree surfaces (elliptical tori).
- Research Organization:
- Westinghouse Hanford Co., Richland, WA (United States)
- Sponsoring Organization:
- USDOE Office of Environmental Restoration and Waste Management, Washington, DC (United States)
- DOE Contract Number:
- AC06-96RL13200
- OSTI ID:
- 658925
- Report Number(s):
- WHC-SD-MP-SWD-30001-Rev.8; ON: DE98053063; BR: EW3135040; TRN: 96000330
- Resource Relation:
- Other Information: PBD: 7 May 1996
- Country of Publication:
- United States
- Language:
- English
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