Assessment of TRAC-PF1/MOD1 against an inadvertent steam line isolation valve closure in the Ringhals 2 power plant
By: prepared by F. Pelayo, A. Sjoberg.
Contributors: Sjöberg, Anders, 1935-; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.; Consejo de Seguridad Nuclear (Spain); Studsvik energiteknik AB.
Series: International agreement report -- NUREG/IA-0041.
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: 48
Subjects: Pressurized water reactors -- Accidents -- Computer simulation.; Nuclear power plants -- Piping -- Valves -- Sweden -- Accidents -- Computer simulation.
Notes: "Prepared as part of the Agreement on Research Participation and Technical Exchange and the International Thermal-Hydraulic Code Assessment and Application Program (ICAP)."

"Consejo de Seguridad Nuclear."

"Studsvik Energiteknik A.B."

Distributed to depository libraries in microfiche.

Shipping list no.: 92-1601-M.

"March 1992."

"ICSP-R2MSIV-T."

Technical.

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

A4682.