RELAP5/MOD3.2 validation using BETHSY test 6.9a
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RELAP5/MOD3.2 validation using BETHSY test 6.9a by S. Bouabdallah

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Published by Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission in Washington, DC .
Written in English

Subjects:

  • Pressurized water reactors -- Loss of coolant -- Computer programs -- Testing.

Book details:

Edition Notes

Other titlesRELAP5 MOD3.2 validation using BETHSY test 6.9a.
Statementprepared by S. Bouabdallah.
SeriesInternational agreement report -- NUREG/IA-0188.
ContributionsU.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research., National Nuclear Corporation.
The Physical Object
FormatMicroform
Paginationv, 9, 22 p.
Number of Pages22
ID Numbers
Open LibraryOL18157430M

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Genre/Form: Government publications: Additional Physical Format: Online version: Bouabdallah, S. RELAP5/MOD validation using BETHSY test a. (OCoLC) Get this from a library! RELAP5/MOD validation using BETHSY test a. [S Bouabdallah; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research,]. This report presents the results of the RELAP5/MOD3 Version 7j assessment on BETHSY TC. BETHSY TC test corresponding to a six inch cold leg break LOCA of the Pressurizer Water Reactor(PWR). The primary objective of the test was to provide reference data of two facilities of different scales (BETHSY and LSTF facility). On the other hand, the present calculation aims at analysis of Author: Young-Jong Chung, Jae-Jun Jeong, Won-Pyo Chang, Dong-Su Kim. RELAP5/MOD Validation Using BETHSY Test a: Aug ML NUREG/IA RELAP5/MOD3 Analysis of BETHSY Test c: Loss of RHRS: SG Manway Open: Aug ML NUREG V19 N1: NRC Regulatory Agenda: Semiannual Report January - June Aug ML NUREG/CR

In a common RELAP5/MOD input model was developed based on the model developed for Bethsy c test, which evolved from the large input model. The common input model for all available Bethsy tests consisted of volumes, junctions and heat structures [8]. This input model was adapted for the use with RELAP5/MOD, with no. In , a common RELAP5/MOD input model was developed based on the model developed for Bethsy c test, which evolved from the large input model. The common input model for all available Bethsy tests consisted of volumes, junctions, and heat structures [ 10 ] (see Table 2).Cited by: 1. Start studying Practice exam. Learn vocabulary, terms, and more with flashcards, games, and other study tools. d. It communicated over a telephone network using digital signals. e. It modulates digital data from a telephone network into analog data that a PC can use. f. It demodulates analog PC data into digital data that can be transmitted through a telephone network.

S. Petelin and B. Končar, " RELAP5/MOD assessment on the BETHSY TC SBLOCA test, " in Proceedings of the 4th Regional Meeting, Nuclear Energy in .   Bethsy was a French integral test facility, which was designed to simulate most pressurized water reactor accidents of interest. BETHSY TC test . USNRC () “RELAP5/Mod Validation Using BETHSY Test a” NURAG/IA 6. IAEA () INSAG-7, “The Chernobyl Accident: Updating of INSAG-1” SAFETY SERIES No. INSAG-7Cited by: 7. The reactor system has been analyzed using the best estimate code RELAP5/Mod The code has been successfully applied for simulation of passive systems of AHWR by comparing the code predictions and test data obtained from an integral test facility. For the purpose of this analysis, following assumptions are made: by: 7.