LBB for KWU-plants-Reference-Cited by-同舟云学术

LBB for KWU-plants

Published:1989-01 Issue:1 Volume:111 Page:3-10
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Bartholomé G.,Bieselt R.W.,Erve M.

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

Reference22 articles.

1. Final Report, Research Project BMFT RS 104, Krafwerk Union R 23/021/78,1978

2. Final Report, Research Project BMFT RS 320, Kraftwerk Union R 914/83/018,1983

3. Critical crack sizes in ductile piping;Kastner;Int. J. Press. Vess. & Piping,1981

4. Experimental and theoretical investigation on the behaviour of circumferential cracks in piping;Bartholomé;Circumferential Crack in Pressure Vessels and Piping,1984

5. Preclusion of failure of the pressure retaining coolant system, Part 2: Application on coolant pipe of the primary system;Bartholomé;IAEA - Vienna 1983: Reliability of Reactor Pressure Components, IAEA-SM-269/7,1983

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1. Evolution of the Leak-Before-Break Concept in Nuclear Plants: Issues and Resolutions in the Process of Regulatory Actions;Nuclear Technology;2011-12

2. Analysis of Leaks Through Microchannel Cracks Using RELAP5-3D;Nuclear Technology;2009-08

3. Investigations on shell–nozzle junction of steam generator for LBB justification;Fatigue & Fracture of Engineering Materials and Structures;2007-12

4. Leak rates through cracks and slits in PHT pipes for LBB;Nuclear Engineering and Design;2002-03