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Improved shielding design with an accelerated Monte Carlo simulation for a neutron generator at Missouri S&T

  • Published:2017-05 Issue: Volume:97 Page:123-132
  • ISSN:0149-1970
  • Container-title:Progress in Nuclear Energy
  • language:en
  • Short-container-title:Progress in Nuclear Energy

Author:

Sahiner Huseyin,Norris Edward T.,Bugis Abdulaleem A.,Liu Xin

Funder

U.S. Nuclear Regulatory Commission

Publisher

Elsevier BV

Subject

Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference16 articles.

1. Radiation fields from neutron generators shielded with different materials;Chichester;Nucl. Instrum. Methods Phys. Res. Sect. B Beam Interact. Mater. Atoms,2007

2. Denovo: a new three-dimensional parallel discrete ordinates code in SCALE;Evans;Nucl. Technol.,2010

3. Initial MCNP6 release overview;Goorley;Nucl. Technol.,2012

4. Neutron Generators for Analytical Purposes;IAEA Radiation Technology Reports No. 1,2012

5. Conversion Coefficients for Radiological Protection Quantities for External Radiation Exposures;ICRP,2010

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1. Dose rate evaluation in a laboratory for prompt gamma neutron activation analysis by Monte Carlo simulation;Journal of Radioanalytical and Nuclear Chemistry;2020-11-21

2. Dose evaluation in a portable D–T neutron generator facility by Monte Carlo method;Journal of Radioanalytical and Nuclear Chemistry;2020-03-05

3. Study on background shielding for a compact photoneutron source;Progress in Nuclear Energy;2019-08

4. Evaluation of neutron and gamma dose in a new deuterium-deuterium fusion neutron generator facility using MCNP and experimental methods;Applied Radiation and Isotopes;2019-04

5. Impact of neutron flux anisotropy from DT generator on radiation shielding effectiveness;Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment;2018-12
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