An analysis of semiscale Mod-2C S-FS-1 steam line break test using RELAP5/MOD2
By: prepared by J.M. Rogers.
Contributors: United Kingdom Atomic Energy Authority.; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.
Series: International agreement report -- NUREG/IA-0052.
Publisher: U.S. Nuclear Regulatory Commission; National Technical Information Service, [distributor
Published: 1992
Place of publication: Washington, DC; Springfield, Va
Language: eng
Format: Microform
Number of pages: 39
Subjects: Pressurized water reactors -- Emergency core cooling systems -- Testing.
Notes: "United Kingdom Atomic Energy Authority."

"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.: 92-1555-M.

No longer available for sale by the Supt. of Docs.

"March 1992."

"AEEW-R2476."

Includes bibliographical references (p. 12).

Technical report.

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

A4682.