Review of ASME code criteria for control of primary loads on nuclear piping system branch connections and recommendations for additional development work
By: prepared by E.C. Rodabaugh, R.C. Gwaltney, S.E. Moore.
Contributors: Gwaltney, R. C.; Moore, S. E. 1933-; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering.; Oak Ridge National Laboratory.
Publisher: Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission; Supt. of Docs., U.S. G.P.O., [distributor]
Published: 1993
Place of publication: Washington, DC
Language: eng
Format: Microform
Number of pages: 41
Subjects: Nuclear power plants -- Piping -- Stress corrosion; Nuclear power plants -- Piping -- Fatigue
Notes: "Oak Ridge National Laboratory."

Distributed to depository libraries in microfiche.

"Date published: November 1993."

"NUREG/CR-5358."

"ORNL/TM-11572."

Includes bibliographical references (p. 23).

Technical.

Microfiche. [Washington, D.C.?] : Supt. of Docs., U.S. G.P.O., [1994] 1 microfiche : negative.

B0474.