TREAT neutronics analysis of water-loop concept accommodating LWR 9-rod bundle
- Idaho National Laboratory, Idaho Falls, ID 83415 (United States)
The Transient Reactor Test (TREAT) facility that was commissioned in 1959 and that was put in stand-by in 1994, is now facing an upgrade to provide irradiation services to a variety of experimental programs. The neutronic studies presented in this paper show that the TREAT facility is capable of performing transient tests on fresh 9-rod PWR bundles in a water loop design constructed from Inconel piping using only fuel assemblies from the original core. High burnup rods in the same proposed design configuration approach, but do not meet, energy deposition targets for narrow-pulse reactivity insertion accident testing. The option to use a Zircaloy-based water loop was evaluated and found to increase the power coupling factor (PCF) adequately, but several engineering considerations show that the Inconel loop should be considered the baseline design option until detailed design work is performed. TREAT's capabilities for steam-based LOCA testing were also evaluated and found to allow for higher specimen energy deposition than RIA tests primarily because the reactor can release more energy over longer shaped transients. The same test configurations were evaluated in the presence of a partial TREAT-upgrade (TU) core with the notable observation that TU elements can enable high burnup rods to achieve RIA energy targets with the Inconel water loop. Further observations show that the partial TU core can help recover excess reactivity as needed and flatten pin-to-pin power profiles for more prototypic test conditions. These studies demonstrate that a simple U/C atom ratio gradient implementation results in more energy deposition into the test specimen and works to flatten the rod-to-rod power profile. It is expected that the actual, specially designed TREAT upgrade core will be much more effective than this study of a modified version demonstrates and deserves a comprehensive investigation to identify true capability. Overall, the complex interplay between fuel, geometry, neutron absorbers, and moderators emphasize that the facility's capabilities are flexible and further enabled by the ability to use TU elements.
- Research Organization:
- American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
- OSTI ID:
- 22764058
- Resource Relation:
- Conference: TOP FUEL 2016: LWR fuels with enhanced safety and performance, Boise, ID (United States), 11-15 Sep 2016; Other Information: Country of input: France; 15 refs.; Related Information: In: TOP FUEL 2016 Proceedings| 1670 p.
- Country of Publication:
- United States
- Language:
- English
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