Published September 2011 | Version v1
Miscellaneous

Overview of MCNP6 capabilities for criticality accident impact assessment and alarm system design - 6-01

  • 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

Part of:
Proceedings of the Ninth International Conference on Nuclear Criticality Safety - ICNC 2011

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.