Research reactor 'MARIA' primary cooling loop transient analysis using RELAP5 Mod 3.3
By: prepared by M. Dabrowski, E. Staron
Contributors: Staron, E., author; U.S. Nuclear Regulatory Commission; U.S. Nuclear Regulatory Commission. Division of Systems Analysis
Series: International agreement report -- NUREG/IA-0443; International agreement report -- NUREG/IA-0443.
Publisher: United States Nuclear Regulatory Commission
Published: 2014
Place of publication: Washington, DC
Language: eng
Number of pages: 215
Subjects: Nuclear reactors; Cooling; Safety measures
Notes: Title from title screen (viewed on Aug. 28, 2014).

"June 2014."

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

Sponsored by Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission