Assessment of TRAC-PF1/MOD1 against an inadvertent feedwater line isolation transient in the Ringhals 4 power plant
By: prepared by A. Sjoberg.
Contributors: U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.
Series: International agreement report -- NUREG/IA-0038.
Publisher: U.S. Nuclear Regulatory Commission; Supt. of Docs., U.S. G.P.O. [distributor]; National Technical Information Service [distributor
Published: 1992
Place of publication: Washington, DC; Springfield, VA
Language: eng
Format: Microform
Number of pages: 55
Subjects: Pressurized water reactors -- Accidents -- Data processing.; Pressurized water reactors -- Loss of coolant -- Data processing.; Nuclear power plants -- Sweden.
Notes: "Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission.

"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.: 92-1725-M.

"March 1992."

"STUDSVIK/NP-88/101."

Includes bibliographical references (p. 27).

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

A4682.