Published 2017 | Version v1
Journal article

Second-Order Uncertainty Analysis for Radiation Shielding Problems Using MCNP

  • 1. Los Alamos National Laboratory, Los Alamos, NM 87545 (United States)

Description

Standard uncertainty propagation is based on a first-order Taylor expansion. This approximation is usually justified by assuming that 'uncertainties are very small numbers compared with the values of their corresponding quantities'. Furthermore, the second derivatives needed for a second-order analysis are not usually available, and a second-order analysis requires more knowledge regarding the distribution of the random variables. For radiation shielding problems, the MCNP6 Monte Carlo code computes first and second derivatives of a response with respect to nuclide density or reaction cross section. This paper explores the application of these derivatives to second-order uncertainty analysis

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
116
Journal Page Range
p. 595-598
ISSN
0003-018X

Conference

Title
2017 Annual Meeting of the American Nuclear Society
Dates
11-15 Jun 2017
Place
San Francisco, CA (United States)

INIS

Country of Publication
United States
Country of Input or Organization
France
INIS RN
52087876
Subject category
S97: MATHEMATICAL METHODS AND COMPUTING; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTERIZED SIMULATION; CROSS SECTIONS; DENSITY; ISOTOPES; MONTE CARLO METHOD; NEUTRON TRANSPORT; RANDOMNESS; SHIELDING
Descriptors DEC
CALCULATION METHODS; NEUTRAL-PARTICLE TRANSPORT; PHYSICAL PROPERTIES; RADIATION TRANSPORT; SIMULATION

Optional Information

Notes
7 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)