Verification and validation of the MCNPX-PoliMi code for simulations of neutron multiplicity counting systems-Reference-Cited by-同舟云学术

Verification and validation of the MCNPX-PoliMi code for simulations of neutron multiplicity counting systems

Published:2013-02 Issue: Volume:700 Page:135-139
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:

Clarke S.D.,Miller E.C.,Flaska M.,Pozzi S.A.,Oberer R.B.,Chiang L.G.

Publisher

Elsevier BV

Subject

Instrumentation,Nuclear and High Energy Physics

Reference14 articles.

1. N. Ensslin, W.C. Harker, M.S. Krick, D.G. Langner, M.M. Pockrell, J.E. Stewart, Application Guide to Neutron Multiplicity Counting, Los Alamos National Laboratory, LA-13422-M, 1998.

2. Neutron Signal Multiplet Analysis for the Mass Determination of Spontaneous Fission Isotopes

3. Neutron multiplicity and multiplication measurements

4. Neutron multiplicity measurements on 220l waste drums containing Pu in the range 0.1–1g 240Pueff with the Time Interval Analysis method

5. S.A. Pozzi, R.B. Oberer, L.G. Chiang Monte Carlo simulation of measurements with an active well coincidence counter (AWCC), in: Proceedings of the Institute of Nuclear Materials Management 45th Annual Meeting, Orlando, Florida, July 18–22, 2004.

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