COBRA/RELAP5: A Merged Version of the COBRA-TF and RELAP5/MOD3 Codes-Reference-Cited by-同舟云学术

COBRA/RELAP5: A Merged Version of the COBRA-TF and RELAP5/MOD3 Codes

Published:1992-08 Issue:2 Volume:99 Page:177-187
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Lee Sang Yong¹,Jeong Jae Jun¹,Kim Si-Hwan¹,Chang Soon Heung²

Affiliation:

1. Korea Atomic Energy Research Institute P.O. Box 7, Daeduk-Danji, Taejon, Korea

2. Korea Advanced Institute of Science and Technology Department of Nuclear Engineering Daeduk-Danji, Taejon, 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/NT99-177

Reference16 articles.

1. “Compendium of ECCS Research for Realistic LOCA Analysis,” Draft Report for Comment, NUREG-1230, U.S. Nuclear Regulatory Commission (Apr. 1987).

2. Quantifying reactor safety margins part 1: An overview of the code scaling, applicability, and uncertainty evaluation methodology

3. “RELAP5 Input Data Requirements,” 83415, EG&G Idaho Inc. (Jan. 1990).

4. “TRAC-PF1/MOD1: An Advanced Best-Estimate Computer Program for Pressurized Water Reactor Thermal-Hydraulic Analysis,” LA-10157-MS, NUREG/CR-3858, Los Alamos National Laboratory (July 1986).

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