RELAP5-3D Validation Study Using MB-2 Prototypical Steam Generator Steady-State Data-Reference-Cited by-同舟云学术

RELAP5-3D Validation Study Using MB-2 Prototypical Steam Generator Steady-State Data

Published:2005-09 Issue:3 Volume:151 Page:272-280
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Sawyer A.¹,Williamson M.¹,Zhao K.¹,Ruggles A.¹

Affiliation:

1. University of Tennessee, Department of Nuclear Engineering Knoxville, Tennessee 37996-2300

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/NT05-A3649

Reference6 articles.

1. M. Y. YOUNG, K. TAKEUCHI, O. J. MENDLER, and G.W. HOPKINS, “Prototypical Steam Generator (MB-2) Transient Testing Program: Task Plan/Scaling Analysis Report,” NUREG0 CR-3661, EPRI NP-3494, and WCAP-10475, Electric Power Research Institute/Westinghouse Electric Corporation Nuclear Energy Systems (Mar. 1984).

2. O. J. MENDLER, K. TAKEUCHI, and M. Y. YOUNG, “Loss of Feed Flow, Steam Generator Tube Rupture, and Steam Line Break Thermohydraulic Experiments: MB-2 Steam Generator Transient Response Test Program,” NUREG0CR-4751, EPRI NP-4786, and WCAP-11206, Electric Power Research Institute/Westinghouse Electric Corporation Nuclear Energy Systems(Jan. 1987).

3. R. W. SHUMWAY, “Assessment of RELAP5/MOD3.2Steam Generator Heat Transfer,” INEEL0EXT-2000-01393, Idaho National Engineering and Environmental Laboratory.

4. “RELAP5-3D Code Manual,” INEEL-EXT-98-00834 Idaho National Engineering and Environmental Laboratory (July 2002).

5. “RELAP50MOD3.2 Code Manual,” INEL-9500174, NUREG0CR-5535, Idaho National Engineering Laboratory (Aug. 1995).