Radiation Embrittlement of Pressure Vessels and Procedures for Limiting this Effect in Power Reactors-Reference-Cited by-同舟云学术

Radiation Embrittlement of Pressure Vessels and Procedures for Limiting this Effect in Power Reactors

Published:1968-04 Issue:4 Volume:4 Page:230-244
ISSN:0894-0401
Container-title:Nuclear Applications
language:en
Short-container-title:Nuclear Applications

Author:

Steele L. E.¹,Knighton G. W.²,Potapovs U.³

Affiliation:

1. Division of Reactor Development and Technology USAEC., Washington, D.C. 20545

2. Nuclear Power Field Office. U.S. Army Corps of Engineers, Fort Belvoir, Va. 22060

3. Reactor Materials Branch, Metallurgy Division, Naval Research Laboratory, Washington. D.C. 20390

Publisher

Informa UK Limited

Subject

General Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT68-A26321

Reference19 articles.

1. W. S. PELLINI and P. P. PUZAK, “Fracture Analysis Diagram Procedures for the Fracture-Safe Engineering Design of Steel Structures,” NRL-5920, U.S. Naval Research Laboratory (March 15, 1963).

2. J. M. MONAHAN and T. J. WALKER, “PM-2A Reactor Vessel Test—Description of Testing and Failure Conditions,” WAPD-TM-640, Westinghouse Electric Corporation (January 1967).

3. G. D. WHITMAN, G. C. ROBINSON, jr., and A. W. SAVOLAINEN, “Technology of Pressure Vessels for Water Reactors,” ORNL-NSIC-21, Oak Ridge National Laboratory (publication pending).

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1. Hardening and Recovery of Neutron-Irradiated Pressure Vessel Steel (ASTM A533B);Journal of Nuclear Science and Technology;1975-08

2. HARDENING AND RECOVERY OF NEUTRON-IRRADIATED PRESSURE-VESSEL STEEL (ASTM A533B);J NUCL SCI TECHNOL;1975

3. Fracture Safety Analysis Concepts for Nuclear Pressure Vessels, Considering the Effects of Irradiation;Journal of Basic Engineering;1971-06-01

4. FRACTURE MECHANISMS AND RADIATION EFFECTS;Engineering Fundamentals and Environmental Effects;1971

5. Steels for commercial nuclear power reactor pressure vessels;Nuclear Engineering and Design;1969-07