Modeling High Burnup RIA Tests with FRAPTRAN
Conference
·
OSTI ID:1489670
- BATTELLE (PACIFIC NW LAB)
The transient fuel performance code FRAPTRAN 1.4 has been successfully used to model reactivity-initiated accident (RIA) tests performed on three very similar high burnup pressurized water reactor (PWR) rod segments. These segments were taken from rods irradiated for 5 cycles in the Vandellos-2 reactor, and all were clad with ZIRLO™ cladding. Each RIA test was performed under different coolant conditions. The first test, CIP0-1, was performed in the CABRI reactor under 280°C flowing sodium. The second test, VA-1, was performed in the NSRR reactor in a stagnant water capsule at room temperature and atmospheric pressure. The third test, VA-3, was performed in NSRR reactor in a stagnant water capsule at 285°C and elevated pressure. Two of these tests, VA-1 and VA-3 failed and the other test, CIP0-1, did not fail.
- Research Organization:
- Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC05-76RL01830
- OSTI ID:
- 1489670
- Report Number(s):
- PNNL-SA-74451
- Country of Publication:
- United States
- Language:
- English
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· Nuclear Technology
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OSTI ID:20822233