Treatment of the thermal–hydraulic uncertainties in the pressurized thermal shock analysis-Reference-Cited by-同舟云学术

Treatment of the thermal–hydraulic uncertainties in the pressurized thermal shock analysis

Published:2007-01 Issue:2 Volume:237 Page:143-152
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Jang Changheui

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

Reference12 articles.

1. ASME, 1995. Boiler and Pressure Vessel Code, Section XI.

2. Dickson, T.L., 1994. FAVOR: A Fracture Analysis Code for Nuclear Reactor Pressure Vessels, Release 9401, ORNL/NRC/LTR/94/1.

3. Development of the Improved Probabilistic Fracture Mechanics Analysis Code: VINTIN;Jang,2001

4. Treatment of stainless steel cladding in pressurized thermal shock evaluation: deterministic analysis;Jang;J. Korean Nucl. Soc.,2001

5. The effects of the stainless steel cladding in pressurized thermal shock evaluation;Jang;Nucl. Eng. Des.,2003

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