RELAP5 assessment using Semiscale SBLOCA test S-NH-1
By: prepared by Euy-Joon Lee, Bub-Dong Chung, Hho-Jung Kim.
Contributors: Chung, B. D.; Kim, H. J.; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.; Han ơguk Wo njaryo k Anjo n Kisurwo n. Safety Analysis Dept.
Series: International agreement report -- NUREG/IA-0099.
Publisher: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission; Available from Supt. of Docs., U.S. G.P.O.; National Technical Information Service [distributor
Published: 1993
Place of publication: Washington, DC; Springfield, VA
Language: eng
Format: Microform
Number of pages: 179
Subjects: Pressurized water reactors -- Loss of coolant -- Computer simulation.
Notes: "Safety Analysis Department, Korea Institute of Nuclear Safety."

"Prepared as part of the Agreement on Research Participation and Technology Exchange under the International Thermal-Hydraulic Code Agreement and Application Program (ICAP)."

Distributed to depository libraries in microfiche.

Shipping list no.: 93-1186-M.

"June 1993."

Includes bibliographical references (p. 22-23).

Technical.

Microfiche. [Washington, D.C.?] : Supt. of Docs., U.S. G.P.O., [1993] 3 microfiches : negative.

L2245.