Potential for low fracture toughness and lamellar tearing on PWR steam generator and reactor coolant pump supports :
resolution of generic technical activity A-12 /
R.P. Snaider, J.M. Hodge, H.A. Levin, J.J. Zudans.

Description

Related Names

Zudans, J. J.
Levin, H. A.
Hodge, J. M.
Snaider, R. P.
U.S. Nuclear Regulatory Commission. Division of Operating Reactors.

Language(s)

English

Published

Springfield, Va. : National Technical Information Service
Washington, D.C. : GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commissioin
Washington, D.C. : Division of Operating Reactors, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1979.

Subjects

Pressurized water reactors > Pressurized water reactors / Safety measures.
Pressurized water reactors.
Nuclear reactors > Nuclear reactors / Materials > Nuclear reactors / Materials / Testing.
Nuclear reactors > Nuclear reactors / Cooling.
Nuclear reactors > Nuclear reactors / Materials > Nuclear reactors / Materials / Testing.
Nuclear reactors > Nuclear reactors / Cooling.
Pressurized water reactors > Pressurized water reactors / Safety measures.
Pressurized water reactors.

Note

"Manuscript completed: August 1979; Date published: October 1979."
"NUREG-0577, For comment."

Physical Description

v, 15, A-12/5, B-1, C-221, D-3 leaves : illustrations ; 28 cm

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