TRAC-PF1/MOD1 post-test calculations of the OECD LOFT experiment LP-SB-3
By: prepared by E.J. Allen, A.P. Neill
Contributors: Neill, A. P; U.S. Nuclear Regulatory Commission
Series: International agreement report -- NUREG/IA-0022; International agreement report -- NUREG/IA-0022
Publisher: U.S. Nuclear Regulatory Commission; Available from Supt. of Docs., U.S. G.P.O.; National Technical Information Service
Published: 1990
Place of publication: Washington, D.C; Springfield, VA
Language: eng
Subjects: LOFT (Nuclear reactor safety test facility) -- Experiments; Pressurized water reactors -- Loss of coolant -- Computer programs; Hydraulic transients -- Simulation methods
Notes: "Prepared as part of the Agreement on research participation and technical exchange under the International Thermal-Hydraulic Code Assessment and Application Program (ICAP)."

Shipping list no.: 90-408-P

"April 1990."

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Includes bibliographical references (p. 14-15)

Technical