Materials Test-2 LOCA Simulation in the NRU Reactor
A simulated loss-of-coolant accident was performed with a full-length test bundle of pressurized water reactor fuel rods. This third experiment of the program produced fuel cladding temperatures exceeding 1033 K (1400°F) for 155 s and resulted in eight ruptured fuel rods. Experiment data and initial results are presented in the form of photographs and graphical summaries.
- Research Organization:
- Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
- Sponsoring Organization:
- Office of Nuclear Regulatory Research
- DOE Contract Number:
- DE-AC06-76RL01830
- OSTI ID:
- 1084042
- Report Number(s):
- PNL-4155; NUREG/CR-2509
- Country of Publication:
- United States
- Language:
- English
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