Pressurized water reactor core instrument tube ruptures: experimental simulation at the ROSA-IV lstf-Reference-Cited by-同舟云学术

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Pressurized water reactor core instrument tube ruptures: experimental simulation at the ROSA-IV lstf

Published:1990-06 Issue:2-3 Volume:120 Page:249-257
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Kukita Y.,Asaka H.,Nakamura H.,Tasaka K.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference15 articles.

1. Analysis of instrument tube rupture in Westinghouse 4-loop pressurized water reactor;Fletcher,1986

2. RELAP5/MOD2 Code Manual, USNRC Report;Ransom,1985

3. Simulation test of PWR instrument tube break LOCA in ROSA-IV program;Suzuki;J. Nucl. Sci. Tech.,1987

4. The effects of break location on PWR small-break LOCA;Tasaka,1988

5. ROSA-IV large scale test facility (LSTF) system description;Rosa-IV Group,1985

Cited by 3 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. RELAP5 Analyses of ROSA/LSTF Experiments on AM Measures during PWR Vessel Bottom Small-Break LOCAs with Gas Inflow;International Journal of Nuclear Energy;2014-09-01

2. Summary of ROSA-IV LSTF first-phase test program — Integral simulation of PWR small-break LOCAs and transients -;Nuclear Engineering and Design;1991-10

3. The effects of break location on PWR small break LOCA: Experimental study at the ROSA-IV LSTF;Nuclear Engineering and Design;1990-09

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