Numerical analysis of mixing factors in the RPV of VVER-440 reactor using the TRACE code / prepared by: Petr Heralecky, Martin Blaha.

Format:

Book

Government document

Author/Creator:

Heralecky, P. (Petr)

Contributor:

Blaha, Martin

Calvo, A.

U.S. Nuclear Regulatory Commission

Series:

International agreement report ; NUREG/IA-0235.

International agreement report ; NUREG/IA-0235

Language:

English

Subjects (All):

Nuclear power plants--Safety measures.

Nuclear power plants.

Water cooled reactors--Loss of coolant--Safety measures.

Water cooled reactors.

Physical Description:

1 online resource (80 pages) : illustrations.

Place of Publication:

Washington, DC : U.S. Nuclear Regulatory Commission, [2010]

Notes:

Title from PDF title screen (viewed July 23, 2010).

"Prepared as part of The Agreement on Research Participation and Technical Exchange Under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)."

"Prepared for: Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Analysis."

"A. Calvo, NRC Project Manager."

"Manuscript completed: April 2010; Date published: May 2010."

"May 2010."

Includes bibliographical references (pages 9-1-9-2).

Other Format:

Heralecky, Petr. Numerical analysis of mixing factors in the RPV of VVER-440 reactor using the TRACE code

OCLC:

650084704