Assessment of pressurized water reactor control rod drive mechanism nozzle cracking
By: prepared by V.N. Shah ... [et  al.] ; prepared for Safety Programs Division, Office for Analysis and Evaluation of Operational Data, U.S. Nuclear Regulatory Commission.
Contributors: Shah, V. N.; Idaho National Engineering Laboratory.; EG & G Idaho.; U.S. Nuclear Regulatory Commission. Office for Analysis and Evaluation of Operational Data. Division of Safety Programs.
Publisher: U.S. Nuclear Regulatory Commission
Published: 1994
Place of publication: Washington, DC
Language: eng
Format: Microform
Number of pages: 50
Subjects: Pressurized water reactors -- Equipment and supplies -- Reliability; Nozzles -- Testing
Notes: "Idaho National Engineering Laboratory."

"EG&G Idaho, Inc."

"Date published: October 1994".

Includes bibliographical references.

Microfiche. [Washington, D.C.] : U.S. G.P.O., [1994]. 1 microfiche.