Assessment of RELAP5/MOD2 critical flow model using Marviken test data 15 and 24
By: prepared by K. Kim, H.-J. Kim.
Contributors: Kim, H. J.; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.; Korea Institute of Nuclear Safety. Safety Analysis Dept.
Series: International agreement report -- NUREG/IA-0086.
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: 1992
Place of publication: Washington, DC; Springfield, VA
Language: eng
Format: Microform
Number of pages: 81
Subjects: Nuclear reactors -- Cooling -- Computer simulation.
Notes: "Korea Institute of Nuclear Safety, Safety Analysis Department."

"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.: 92-1814-M.

"April 1992."

Includes bibliographical references (p. 68).

Technical.

Microfiche. [Washington, D.C.?] : Supt. of Docs., U.S. G.P.O., [1992?] 1 microfiche : negative.

A4682.