Simulation of Mixed-Oxide and Low-Enriched Uranium Fuel Burnup in a Pressurized Water Reactor and Validation Against Destructive Analysis Results-Reference-Cited by-同舟云学术

Simulation of Mixed-Oxide and Low-Enriched Uranium Fuel Burnup in a Pressurized Water Reactor and Validation Against Destructive Analysis Results

Published:2002-11 Issue:3 Volume:142 Page:258-269
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Murphy B. D.¹,Primm R. T.¹

Affiliation:

1. Oak Ridge National Laboratory P.O. Box 2008, Oak Ridge, Tennessee 37831-6370

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/NSE02-A2306

Reference7 articles.

1. B. D. MURPHY, “Characteristics of Spent Fuel from Plutonium Disposition Reactors, Vol. 3: A Westinghouse Pressurized-Water Reactor Design,” ORNL/TM-13170, Oak Ridge National Laboratory (July 1997).

2. M. D. DeHART, “Sensitivity and Parametric Evaluations of Significant Aspects of Burnup Credit for PWR Spent Fuel Packages,” ORNL/TM-12973, Oak Ridge National Laboratory (May 1996).

3. “SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation,” NUREG/CR-0200, Rev. 6 (ORNL/NUREG/CSD-2/R6), Vols. I, II, and III, Oak Ridge National Laboratory (May 2000); see also CCC-545, Radiation Safety Information Computational Center, Oak Ridge National Laboratory.

4. S. E. FISHER and F. C. DIFILIPPO, “Neutronics Benchmark for the Quad Cities-1 (Cycle 2) Mixed-Oxide Assembly Irradiation,” ORNL/TM-13567, Oak Ridge National Laboratory (Apr. 1998).

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