Demonstration of pressurized thermal shock thermal-hydraulic analysis with uncertainty
Subtitle: RELAP5/MOD3 and TRAC-PF1/MOD2 calculations in support of regulatory guide 1.154 revisions
By: prepared by D. Palmrose (SCIENTECH, Inc.) ; prepared for Division of Systems Technology, Office of Nuclear Regulatory Commission, U.S. Nuclear Regulatory Commission.
Contributors: U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Technology.; SCIENTECH, Inc.
Publisher: Division of Systems Technology, Office of Nuclear Regulatory Commission, U.S. Nuclear Regulatory Commission; Supt. of Docs., U.S. G.P.O. [distributor]
Published: 1999
Place of publication: Washington, D.C
Language: eng
Format: Microform
Number of pages: 315
Subjects: Pressurized water reactors.; Thermal stresses.; Nuclear reactors -- Cooling.; Nuclear power plants -- Safety measures.
Other titles: RELAP5/MOD3 and TRAC-PF1/MOD2 calculations in support of regulatory guide 1.154 revisions.
Notes: "SCIENTECH, Inc."

Shipping list no.: 99-0489-M.

"Date published: March 1999."

"NUREG/CR-5452."

"SCIE-NRC-350."

Includes bibliographical references.

Technical.

Microfiche. [Washington, D.C.] : Supt. of Docs., U.S. G.P.O., [1999] 5 microfiches : negative.

W7630.