An Assessment of TRAC-PF1/MOD1 using Strathclyde 1/10 scale model refill tests
By: prepared by W.M. Dempster ... [et al.]
Contributors: Dempster, W. M; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research; Central Electricity Research Laboratories
Series: International agreement report -- NUREG/IA-0055
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: 51
Subjects: Pressurized water reactors -- Loss of coolant -- Computer simulation
Notes: "University of Strathclyde/Central Electricity Research Laboratories."

"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.: 92-1555-M

"March 1992."

Includes bibliographical references (p. 18-19)

Technical

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

A4682