Modification of SCWR Assembly Designs with Coupled MCNP5/SCA Methods to Promote Safer Operation

Author:

Hughes Christopher R.1,Pelaez Oswaldo2,Schubring Duwayne1,Jordan Kelly A.2

Affiliation:

1. University of Florida, Department of Mechanical and Aerospace Engineering, 221 MAE-B P.O. Box 116300, Gainesville, Florida 32611-6300

2. University of Florida, Department of Materials Science and Engineering, Nuclear Engineering Program, 100 Rhines Hall, P.O. Box 116400, Gainesville, Florida 32611-6400

Publisher

Informa UK Limited

Subject

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

Reference5 articles.

1. J. BUONGIORNO and P. E. MACDONALD, “Progress Report for the FY-03 Generation-IV R&D Activites for the Development of the SCWR in the U.S.” INEEL/EXT-03-01210, Idaho National Engineering and Environmental Laboratory (Sep. 2003).

2. X-5 MONTE CARLO TEAM, “MCNP—A General N-Particle Transport Code, Version 5,” Los Alamos National Laboratory (2003).

3. K. H. PRESSER, “Wärmeübergang und Druckverlust an Reaktorbrennelementen in Form langsdurchstromter Rundstabbündel,” Kernforschungszentrum Jülich (1967).

4. C. R. HANN, C. E. BEYER, and L. J. PARCHEN, “GAPCON-Thermal-1: A Computer Program for Calculating the Gap Conductance in Oxide Fuel Pins,” Battelle Pacific Northwest Laboratories (Sep. 1973).

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