Progress of the DUPIC Fuel Compatibility Analysis - II: Thermal Hydraulics-Reference-Cited by-同舟云学术

Progress of the DUPIC Fuel Compatibility Analysis - II: Thermal Hydraulics

Published:2006-02 Issue:2 Volume:153 Page:164-174
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Park Joo Hwan¹,Park Jee-Won¹,Choi Hangbok¹,Yang Myung Seung¹

Affiliation:

1. Korea Atomic Energy Research Institute P.O. Box 105, Yusong, Daejon, 305-600, Korea

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/NT06-A3697

Reference15 articles.

1. M. F. LIGHTSTONE, “NUCIRC-MOD1.505 Users Manual,” TTR-516, Atomic Energy of Canada Limited (1993).

2. E. K. ZARIFFEH, G. M. WADDINGTON, N. HAMMOUDA, L. N. CARLUCCI, V. C. FRISINA, J. C. KITELEY, D. S. ROWE, and P. PFEIFFER, “ASSERT-PV V2R8 Users Manual,” FFC-FCT-133, COG-97-460, Atomic Energy of Canada Limited (1998).

3. 1986 AECL-UO Critical Heat Flux Lookup Table

4. I. E. OLDAKER, “Fuel Design Manual for CANDU-6 Reactors,” DM-XX-37000-001, Atomic Energy of Canada Limited (1989).

5. “Final Safety Analysis Report: Wolsong Nuclear Power Plant Units No. 2/3/4,” Korea Electric Power Corporation (1995).

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