Overview of MCNP6 capabilities for criticality accident impact assessment and alarm system design - 6-01
Creators
- 1. Los Alamos National Laboratory, P.O. Box 1663 MS A143, Los Alamos, NM 87545 (United States)
Description
MCNP is designed to be a general-purpose Monte Carlo radiation transport software package. The package has a development history spanning decades and is still undergoing development. MCNP6 involves the merger of MCNP5 and MCNPX and new features found in neither. Many of these features are particularly useful for criticality accident alarm systems (CAAS) designers attempting to characterize a source, model radiation transport through a facility to measure dose, and to model detectors. The MCNP development team provides six verification and validation suites that are of particular interest to CAAS designers. The development team also gives advanced criticality courses that can, by request, feature lecture material to explain how MCNP6 can be used
Additional details
Publishing Information
- Imprint Title
- Proceedings of the Ninth International Conference on Nuclear Criticality Safety - ICNC 2011
- Imprint Pagination
- 1726 p.
- Journal Page Range
- 10 p.
- Report number
- INIS-XN--22-ICNC-2011
Conference
- Title
- International conference on nuclear criticality
- Acronym
- ICNC 2011
- Dates
- 19-22 Sep 2011
- Place
- Edinburgh (United Kingdom)
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- France
- INIS RN
- 53069855
- Subject category
- S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COMPUTERIZED SIMULATION; M CODES; RADIATION DETECTION; RADIATION TRANSPORT; TRAINING; VALIDATION
- Descriptors DEC
- COMPUTER CODES; DETECTION; EDUCATION; SIMULATION; TESTING
Optional Information
- Notes
- 42 refs.