Reliability of Monte Carlo simulations in modeling neutron yields from a shielded fission source-Reference-Cited by-同舟云学术

Reliability of Monte Carlo simulations in modeling neutron yields from a shielded fission source

Published:2016-08 Issue: Volume:827 Page:46-51
ISSN:0168-9002
Container-title:Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment
language:en
Short-container-title:Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment

Author:

McArthur Matthew S.,Rees Lawrence B.,Czirr J. Bart

Funder

NNSA

DHS

Publisher

Elsevier BV

Subject

Instrumentation,Nuclear and High Energy Physics

Reference13 articles.

1. Passive neutron detection for interdiction of nuclear material at borders

2. MCNP X-5 Monte Carlo Team. MCNP-a general purpose Monte Carlo N-particle transport code. Los Alamos National Laboratory, LA-UR-03-1987, version 5 edition. April 2003 (the MCNP code can be obtained from the Radiation Safety Information Computational Center (RSICC), Oak Ridge, TN).

3. Optimizing moderation of He-3 neutron detectors for shielded fission sources

4. On the optimisation of the use of 3He in radiation portal monitors

5. Optimising the neutron environment of Radiation Portal Monitors: A computational study

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