Assessment of RELAP5/MOD 2 against critical flow data from Marviken tests JIT 11 and CFT 21
By: prepared by Ö. Rosdahl, D. Caraher ; prepared as part of the Agreement on Research Participation and Technical Exchange under the International Thermal-Hydraulic Code Assessment and Application Program (ICAP).
Contributors: Caraher, D.; U.S. Nuclear Regulatory Commission.
Series: International agreement report -- NUREG/IA-0007.
Publisher: U.S. Nuclear Regulatory Commission; Available from Supt. of Docs., U.S. G.P.O.; National Technical Information Service
Published: 1986
Place of publication: Washington, D.C; Springfield, VA
Language: eng
Subjects: Nuclear pressure vessels.; Light water reactors -- Data processing.; Nuclear power plants -- Thermodynamics.; Nuclear reactor kinetics.
Notes: Distributed to depository libraries in microfiche.

"September 1986."

Bibliography: p. 35 (2nd group).

Technical.

Division of Reactor System Safety, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission.