Analysis of the test OECD-PKL2 G7.1 with the thermal-hydraulic system code TRACE
By: prepared by: S. Belaïd, J. Freixa, O. Zerkak
Contributors: Freixa, J., author; Zerkak, O., author; U.S. Nuclear Regulatory Commission
Series: International agreement report -- NUREG/IA-0432
Publisher: U.S. Nuclear Regulatory Commission
Published: 2013
Place of publication: Washington, DC
Language: eng
Number of pages: 29
Subjects: Pressurized water reactors; Emergency core cooling systems; Testing; Equipment and supplies; Effect of temperature on; Measurement; Nuclear fuel claddings; Nuclear power plants; Safety measures
Other titles: Analysis of the test Organisation for Economic Co-operation and Development-Primary Coolant Loop Test Facility G7.1 with the thermal-hydraulic system code TRACE
Notes: Title from title screen (viewed Oct. 25, 2013).

"September 2013."

Includes bibliographical references (page 29).