An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses: Criticality (keff) Predictions

Author:

Scaglione J. M.1,Mueller D. E.1,Wagner J. C.1

Affiliation:

1. Oak Ridge National Laboratory, Reactor and Nuclear Systems Division, P.O. Box 2008 Building 5700, Oak Ridge, Tennessee 37831-6170

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference29 articles.

1. “Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors”, ANSI/ANS-8.1-1998; R2007, American Nuclear Society, La Grange Park, Illinois (1998).

2. “Validation of Neutron Transport Methods for Nuclear Criticality Safety Calculations”, ANSI/ANS-8.24-2007; R2012, American Nuclear Society, La Grange Park, Illinois (2007).

3. “Burnup Credit for LWR Fuel”, ANSI/ANS-8.27-2008, American Nuclear Society, La Grange Park, Illinois (2008).

4. “Staff Guidance Regarding the Nuclear Criticality Safety Analysis for Spent Fuel Pools”, DSS-ISG-2010-01, Rev. 0, U.S. Nuclear Regulatory Commission, Division of Safety Systems (Oct. 13, 2011).

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