Water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research. Quarterly technical progress report, July--September 1976

Technical Report · Sat Jan 01 04:00:00 EST 1977

OSTI ID:7306239

Dietz, K A ^[1]

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1. ed.

Light water reactor safety research performed July through September 1976 is discussed. A two part analysis of the thermal-hydraulics data was performed to determine the cause of early departure from nucleate boiling and rewet of certain core locations after departure from nucleate boiling. A series of tests was conducted to determine the reflood heat transfer characteristics. A study was undertaken to determine the nature and magnitude of one- and three-dimensional effects on core flow as a result of radial and axial power distribution during the blowdown phase of a PWR LOCA. A preliminary analysis of data from LOFT nonnuclear Loss-of-Coolant Experiment L1-3A and a preliminary investigation of means of improving the RELAP4 computer code model for LOCE L1-3A were completed. Nuclear Test PCM-3 was performed in the Power Burst Facility on four PWR fuel rods to obtain post-DNB fuel behavior data. Postirradiation examinations and analyses were performed on fuel rods subjected to Test IE-ST-2. Fuel model development continued with the preparation of models for steady state and transient FRAP-S and FRAP-T programs and debugging and checkout of new versions of these programs. Development of the BEACON code continued. Fuel behavior verification efforts were concentrated in program development, Halden fuel behavior research, postirradiation examinations, and fuel code behavior. As part of the computer code verification effort, RELAP4 code calculations were compared with data from other programs.

• Research Organization: SEE CODE- 9502158 EG and G Idaho, Inc., Idaho Falls (USA). Idaho National Engineering Lab.
• DOE Contract Number: EY-76-C-07-1570
• OSTI ID: 7306239
• Report Number(s): TREE-NUREG-1017
• Country of Publication: United States
• Language: English

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