Neutronic Analysis of an Advanced Fuel Design Concept for the High Flux Isotope Reactor-Reference-Cited by-同舟云学术

Neutronic Analysis of an Advanced Fuel Design Concept for the High Flux Isotope Reactor

Published:2009-05 Issue:1 Volume:162 Page:87-97
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Xoubi Ned¹,Primm R. T.²,Maldonado G. Ivan³

Affiliation:

1. University of Cincinnati, P.O. Box 210072, Cincinnati, Ohio 45221-0072

2. Oak Ridge National Laboratory, Research Reactors Division, P.O. Box 2008, Oak Ridge, Tennessee 37831-6399

3. The University of Tennessee, Department of Nuclear Engineering, 311 Pasqua Engineering, Knoxville, Tennessee 37996-2300

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/NSE162-87

Reference11 articles.

1. R. D. CHEVERTON and T. M. SIMS, “HFIR Core Nuclear Design,” ORNL-4621, Oak Ridge National Laboratory (1971).

2. N. XOUBI and R. T. PRIMM III, “Investigation of Beryllium Internal Reflector Installation on the Fuel Cycle Length of the High Flux Isotope Reactor,” ORNL/TM-2004-252, Oak Ridge National Laboratory (2004).

3. N. XOUBI and R. T. PRIMM III, “Modeling of the High Flux Isotope Reactor Cycle-400,” ORNL/TM-2004-251, Oak Ridge National Laboratory (2004).

4. Loading beryllium targets to extend the high flux isotope reactor’s cycle length

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