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MCNP–REN: a Monte Carlo tool for neutron detector design

  • Published:2002-06 Issue:3 Volume:485 Page:576-584
  • 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:

Abhold Mark E,Baker Michael C

Publisher

Elsevier BV

Subject

Instrumentation,Nuclear and High Energy Physics

Reference14 articles.

1. A Monte Carlo neutronic and electronic model for thermal neutron coincidence counting;McDonald;Trans. Am. Nucl. Soc.,1979

2. A hybrid Monte Carlo/analytical model of neutron coincidence counting;Stewart;Trans. Am. Nucl. Soc.,1986

3. MCNP–DSP;Valentine;Ann. Nucl. Energy,1996

4. Validation of the Monte Carlo code MCNP–DSP;Valentine;Ann. Nucl. Energy,1997

5. Passive neutron assay of plutonium materials;Dodaro;Nucl. Sci. Eng.,1998

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