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Hendricks, John S.

Publications and source records attributed to Hendricks, John S..

Effective use of DXTRAN in MCNP - 25480

The DXTRAN variance reduction method enables Monte Carlo radiation transport calculations to deterministically place particle tracks on spheres surrounding geo-metric regions of interest. For many problems DXTRAN is the best way to transport particles to small distant regions or to angle bias particles exiting collisions. We provide guidance for optimal selection of parameters when using both single and nested DXTRAN spheres in Monte Carlo N-Particle radiation transport code (MCNP) calculations. Our recommendations are based upon both the underlying mathematics of DXTRAN and two demonstration MCNP simulations. (authors)

61 RADIATION PROTECTION AND DOSIMETRY↗

A qualitative analysis of the neutron population in fresh and spent fuel assemblies during simulated interrogation using the differential die-away technique

In this study, Monte Carlo simulations were performed for the differential die-away (DDA) technique to analyse the time-dependent behaviour of the neutron population in fresh and spent nuclear fuel assemblies as part of the Next Generation Safeguards Initiative Spent Fuel (NGSI-SF) Project. Simulations were performed to investigate both a possibly portable as well as a permanent DDA instrument. Taking advantage of a custom made modification to the MCNPX code, the variation in the neutron population, simultaneously in time and space, was examined. The motivation for this research was to improve the design of the DDA instrument, as it is be ing considered for possible deployment at the Central Storage of Spent Nuclear Fuel and Encapsulation Plant in Sweden (Clab), as well as to assist in the interpretation of the both simulated and measured signals.

98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL P↗