Assessment of CCFL model of RELAP5/MOD3 against simple verticle tubes and rod bundle tests /

Assessment of CCFL model of RELAP5/MOD3 against simple verticle tubes and rod bundle tests /

Bibliographic Details
Corporate Authors: U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research, Hanʼguk Chŏllyŏk Kongsa. Research Center, Han'guk Wŏnjaryŏk Anjŏn Kisurwŏn
Other Authors: Cho, Sungiae
Format: Government Document Microform Book
Language:English
Published: Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Available from Supt. of Docs., U.S. G.P.O. ; [1993]
Series:International agreement report ; NUREG/IA-0100.
Subjects:
Pressurized water reactors > Accidents > Computer simulation.
Nuclear fuel rods > Testing.

Evans: US Documents Microfiche (3rd floor)

Holdings details from Evans: US Documents Microfiche (3rd floor)
Call Number: Y 3.N 88:53/0100
 
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Y 3.N 88:53/0100 Available