Assessment of RELAP5/MOD3.1 using LSTF ten-percent main steam-line-break test run SB-SL-01 / prepared by J.G. Oh [and seven others].

Format:

Book

Government document

Author/Creator:

Oh, J. G., author.

Contributor:

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Technology, sponsoring body.

Series:

International agreement report ; NUREG/IA-0148.

International agreement report ; NUREG/IA-0148

Language:

English

Subjects (All):

Pressurized water reactors--Loss of coolant--Computer programs--Testing.

Pressurized water reactors.

Genre:

Online resources.

Physical Description:

1 online resource (viii, 111 pages) : illustrations.

Place of Publication:

Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, September 1998.

Notes:

Online resource; title from PDF title page (viewed on July 28, 2017).

"Korea Power Engineering Company."

"Korea Institute of Nuclear Safety."

"Japan Atomic Energy Research Institute."

"September 1998."

"Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Thermal-Hydraulic Code Assessment and Maintenance Program (CAMP)."

"G. Rhee, NRC project manager"--Bibliographic data sheet.

Includes bibliographical references (page 29).

Other Format:

Microfiche version: Oh, J.G. Assessment of RELAP5/MOD3.1 using LSTF ten-percent main steam-line-break test run SB-SL-01

OCLC:

999350634