Sensitivity analysis of input parameters for pressure tube integrity evaluation-Reference-Cited by-同舟云学术

Sensitivity analysis of input parameters for pressure tube integrity evaluation

Published:2005-08 Issue:17-19 Volume:235 Page:1909-1918
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Kwak Sang-Log,Lee Joon-Seong,Kim Young-Jin,Park Youn-Won

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

Reference19 articles.

1. ASME, 1996. Rule for In Service Inspection of Nuclear Power Plant Components—ASME Boiler and Pressure Vessel Code, ASME Section XI.

2. Probabilistic fracture mechanics—a state of the art;Bloom,1984

3. CSA, 1994. Periodic Inspection of CANDU Nuclear Power Plant Components, Canadian Standard Association, CAN/CSA N285.4.

4. A probabilistic program implementing the SINTAP assessment procedure;Dillstrom;J. Eng. Fract. Mech.,2000

5. Developments in flaw evaluation for CANDU reactor Zr–Nb pressure tubes;Douglas,1999

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2. Probabilistic fracture mechanics applied for DHC assessment in the cool-down transients for CANDU pressure tubes;Nuclear Engineering and Design;2012-12

3. Probabilistic integrity assessment of pressure tubes in an operating pressurized heavy water reactor;International Journal of Pressure Vessels and Piping;2012-02

4. Sensitivity Analysis for the Cylindrical Pressure Vessel of 16MnR Steel with the Monte-Carlo Method;Materials Science Forum;2011-06

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