Validation of the U.S. NRC Coupled Code System TRITON/TRACE/PARCS Using the Special Power Excursion Reactor Test III-Reference-Cited by-同舟云学术

Validation of the U.S. NRC Coupled Code System TRITON/TRACE/PARCS Using the Special Power Excursion Reactor Test III

Published:2013-09 Issue:3 Volume:183 Page:504-514
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Wang Raymond C.¹,Xu Yunlin¹,Hudson Nathanael²,Downar Thomas J.¹

Affiliation:

1. University of Michigan, Department of Nuclear Engineering and Radiological Sciences 2355 Bonisteel Boulevard, Ann Arbor, Michigan 48109

2. U.S. Nuclear Regulatory Commission, RES Division, Washington, D.C. 20555-0001

Publisher

Informa UK Limited

Subject

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

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT13-A19437

Reference10 articles.

1. Analysis of the SPERT-III E-Core Using ANCK Code with the Chord Weighting Method

2. R. K. McCardell, D. I. Herborn, and J. E. Houghtaling, “Reactivity Accident Test Results and Analysis for the SPERT III E-Core—A Small Oxide-Fueled, Pressurized-Water Reactor,” AEC Research and Development Report IDO-17281, U.S. Nrc ADAMS accession number ML080320431, U.S. Atomic Energy Commission (Mar. 1969).

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