Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, October--December 1977

Technical Report · Sun Jan 01 04:00:00 EST 1978

OSTI ID:5124192

Water reactor research is summarized for the following programs: semiscale, LOFT, Thermal Fuels Behavior, Reactor Behavior, and 3-D Project. The Semiscale Program reports progress in modifying the Mod-1 facility to a new Mod-3 configuration scaled more directly to a PWR; influence of steam generator tube ruptures at start of core reflood in the Semiscale Mod-1 system is discussed. The LOFT Experimental Program presents analyses of small-scale pump coastdown during LOCA conditions; zircaloy rod cladding response to isothermal, isobaric high-temperature and high-pressure tests; and relative effects of rod cladding-mounted thermocouples on time-to-CHF for LOFT fuel rods under LOCA conditions. The Thermal Fuels Behavior Program reports on the various PBF test series (power-cooling-mismatch, gap conductance, reactivity initiated accident, irradiation effects, inlet flow blockage, loss-of-coolant accident, and the PBF-LOFT lead rod test program), on program development (including Halden fuel behavior research, postirradiation examination of commercial power reactor fuel, and a diffusion analysis of UO/sub 2/-zircaloy interaction), and on fuel model development (including a discussion of FRAP-S3 code verification). The Reactor Behavior Program describes containment analysis code development (BEACON/MOD2). The multinational 3-D Experiment Project reports completion of conceptual design for the slab core reflood experiment.

• Research Organization: Idaho National Engineering Lab., Idaho Falls (USA)
• DOE Contract Number: EY-76-C-07-1570
• OSTI ID: 5124192
• Report Number(s): TREE-NUREG-1205
• Country of Publication: United States
• Language: English

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