RELAP5/MOD3.2 assessment using GERDA small break test, 1605AA / prepared by W. Teitsch.

Format:

Book

Government document

Author/Creator:

Tietsch, W., author.

Contributor:

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Technology, sponsoring body.

Series:

International agreement report ; NUREG/IA-0166.

International agreement report ; NUREG/IA-0166

Language:

English

Subjects (All):

Pressurized water reactors--Loss of coolant--Computer simulation.

Pressurized water reactors.

Genre:

Online resources.

Physical Description:

1 online resource (31, A49, B62 pages) : illustrations.

Place of Publication:

Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, July 1999.

Notes:

Online resource; title from PDF title page (viewed on July 28, 2017).

"ABB Reaktor GmbH."

"July 1999."

"Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Code Application and Maintenance Program (CAMP)."

"Sponsoring organization: Division of Systems Technology, Office of Nuclear Reactor Research, U.S. Nuclear Regulatory Commission"--Bibliographic data sheet.

Includes bibliographical references.

Other Format:

Microfiche version: Tietsch, W. RELAP5/MOD3.2 assessment using GERDA small break test, 1605AA

OCLC:

999350910