- Additional Authors
- Description
- v. : ill.; 28 cm.
- Subjects
- Note
- "Idaho National Engineering Laboratory."
- Distributed to depository libraries in microfiche.
- Vols. 1-3 no longer available for sale by the Supt. of Docs.
- "Date published: October 1989."
- "NUREG/CR-5406."
- "EGG-2569."
- Bibliography (note)
- Includes bibliographical references.
- Type of Report (note)
- Contents
- v. 1. Analysis and conclusions -- v. 2. Data report -- v. 3. Review of issues associated with BWR containment isolation valve closure.
- Call Number
- READEX Microfiche Y 3.N 88:25/5406/v. 1-
- OCLC
- marcive21129405
- Author
DeWall, Kevin G.
- Title
BWR reactor water cleanup system flexible wedge gate isolation value qualification and high energy flow interruption test / prepared by K.G. Dewall, R. Steele, Jr.
- Imprint
Washington, DC : Division of Engineering : Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989-
- Type Of Report
Technical.
- Bibliography
Includes bibliographical references.
- Funding
A6857 and B5529.
- Added Author
Steele, Robert.
U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering.
U.S. Nuclear Regulatory Commission. Division of Safety Issue Resolution.
Idaho National Engineering Laboratory.
- Gpo Item No.
1051-H-11 (MF)
- Sudoc No.
Y 3.N 88:25/5406/v.1-
- Research Call Number
READEX Microfiche Y 3.N 88:25/5406/v. 1-