Assessment of RELAP5/MOD3.1 using LSTF ten-percent main steam-line-break test run SB-SL-01
By: prepared by J.G. Oh ... [et al.]
Contributors: Oh, J. G; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research; Hanʾguk Chŏllyŏk Kisul Chusik Hoesa; Hanʾguk Wŏnjaryŏk Anjŏn Kisurwŏn; Nihon Genshiryoku Kenkyūjo
Series: International agreement report -- NUREG/IA-0148
Publisher: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission; Supt. of Docs., U.S. G.P.O. [distributor
Published: 1998
Place of publication: Washington, DC
Language: eng
Format: Microform
Number of pages: 111
Subjects: Pressurized water reactors -- Loss of coolant -- Computer programs -- Testing
Notes: "Korea Power Engineering Company."

"Korea Institute of Nuclear Safety."

"Japan Atomic Energy Research Institute."

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

Shipping list no.: 99-0449-M

"September 1998."

Includes bibliographical references (p. 29)

Microfiche. [Washington, D.C.] : Supt. of Docs., U.S. G.P.O., [1999] 3 microfiches : negative

D6227