Published January 2004 | Version v1
Journal article

Verification of the pulse height tally in MCNP 5

Description

Pulse height tallies are commonly used in Monte Carlo codes to predict detailed measured photon spectra for spectrometry purposes. The pulse height tally is unique among the various tallies in MCNP. Unlike flux or current tallies, which are calculated as soon as the particle exits or collides in the cell, the entire set of tracks for a history must be completed before the pulse height tally can be made. The objective of this work was to verify the pulse height tally and prepare to verify the new MCNP 5 variance reduction features with the pulse height tally. In this paper, we give details to the analytic solution of the pulse height distribution using a modification to Shuttleworth's fictitious elements, report MCNP 5 results for the pulse height tally, energy deposited and current tallies for the problem

Additional details

Identifiers

DOI
10.1016/S0168-583X(03)01598-2;
arXiv
arXiv:0808.1402v5;
PII
S0168583X03015982;

Publishing Information

Journal Title
Nuclear Instruments and Methods in Physics Research. Section B, Beam Interactions with Materials and Atoms
Journal Volume
213
Journal Issue
1
Journal Page Range
p. 167-171
ISSN
0168-583X
CODEN
NIMBEU

Conference

Title
5. topical meeting on industrial radiation and radioisotope measurement applications
Dates
9-14 Jun 2002
Place
Bologna (Italy)

INIS

Country of Publication
Netherlands
Country of Input or Organization
Kazakhstan
INIS RN
35039115
Subject category
S46: INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BENCHMARKS; GAMMA SPECTRA; M CODES; MONTE CARLO METHOD; PULSE CIRCUITS; RADIATION DETECTORS; VERIFICATION
Descriptors DEC
CALCULATION METHODS; COMPUTER CODES; ELECTRONIC CIRCUITS; MEASURING INSTRUMENTS; SPECTRA

Optional Information

Copyright
Copyright (c) 2003 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.