Assessment of CCFL model of RELAP5/MOD3 against simple verticle tubes and rod bundle tests
By: prepared by S. Cho ... [et al.].
Contributors: Cho, Sungiae.; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.; Han ơguk Cho llyo k Kongsa. Research Center.; Han ơguk Wo njaryo k Anjo n Kisurwo n.
Series: International agreement report -- NUREG/IA-0100.
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: 66
Subjects: Pressurized water reactors -- Accidents -- Computer simulation.; Nuclear fuel rods -- Testing.
Notes: "Korea Electric Power Corporation, Research Center."

"Korea Institute of Nuclear Safety."

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

Distributed to depository libraries in microfiche.

Shipping list no.: 93-1101-M.

"June 1993."

Includes bibliographical references (p. 66).

Technical.

Microfiche. [Washington, D.C.?] : Supt. of Docs., U.S. G.P.O., [1993] 2 microfiches : negative.

L2245.