Determination of the plutonium content in a spent fuel assembly by passive and active interrogation using a differential die-away instrument-Reference-Cited by-同舟云学术

Determination of the plutonium content in a spent fuel assembly by passive and active interrogation using a differential die-away instrument

Published:2013-06 Issue: Volume:712 Page:83-92
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:

Henzl V.,Croft S.,Richard J.,Swinhoe M.T.,Tobin S.J.

Publisher

Elsevier BV

Subject

Instrumentation,Nuclear and High Energy Physics

Reference9 articles.

1. D. Reilly, N. Ensslin, H. Smith S. Kreiner, Passive Nondestructive Assay of Nuclear Materials, Los Alamos National Laboratory Report, LA-UR-90-732, 1993, p. 544.

2. G. Bignan, L. Martin-Deidier, Evaluation of the U-Pu residual mass from spent fuel assemblies with passive and active neutronic methods, in: Proceedings of the 13th Annual ESARDA Meeting, Avignon, France, 1991, p. 311.

3. J.F., Pelowitz (Ed.). 2005. MCNPX™ Users's Manual Version 2.5.0, Report LA-CP-05-0369, Los Alamos National Laboratory.

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