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.; Hanʼguk Chŏllyŏk Kisul Chusik Hoesa.; Hanʼguk 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
Place of publication: Washington, DC
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.