TRAC-BF1/MOD1 models and correlations
By: edited by J.A. Borkowski, N.L. Wade.
Contributors: Borkowski, J. A.; Wade, N. L.; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research.; Idaho National Engineering Laboratory.; EG & G Idaho.
Publisher: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission; [Supt. of Doc., U.S. G.P.O., distributor]
Published: 1992
Place of publication: Washington, DC
Language: eng
Format: Microform
Subjects: Boiling water reactors -- Safety measures -- Computer programs.; Water cooled reactors -- Loss of coolant -- Analysis.
Other titles: Transient reactor analysis code.
Notes: "Idaho National Engineering Laboratory."

"EG&G Idaho, Inc."

Distributed to depository libraries in microfiche.

Shipping list no.: 92-2745-M.

"Date published: August 1992."

"NUREG/CR-4391."

"EGG-2680."

Includes bibliographical references.

Technical.

Microfiche. [Washington, D.C.?] : Supt. of Docs., U.S. G.P.O., [1992] 5 microfiches : negative.

L2031.