References
- D. WACHS, “Transient Testing of Nuclear Fuels and Materials in the United States,” JOM, 64, 12, 1396 (2012); https://doi.org/10.1007/s11837-012-0482-2.
- B. K. HEATH and C. C. RACE, “TREAT Restart Project,” Nucl. Technol., 205, 1369 (2019); https://doi.org/10.1080/00295450.2019.1589853.
- A. W. LaPORTA, “Transient Reactor Test (TREAT) Facility Initial Approach to Restart Criticality Following Extended Standby Operation,” Nucl. Technol., 205, 1290 (2019); https://doi.org/10.1080/00295450.2019.1565471.
- D. M. GERSTNER et al., “Safety Strategy and Update of the TREAT Facility Safety Basis,” Nucl. Technol., 205, 1266 (2019); https://doi.org/10.1080/00295450.2018.1556993.
- B. M. CHASE, A. W. LaPORTA, and J. R. PARRY, “Analysis of Core Characterization Transients for TREAT Restart,” Nucl. Technol., 205, 1312 (2019); https://doi.org/10.1080/00295450.2019.1585162.
- T. HOLSCHUH, S. WATSON, and D. CHICHESTER, “Metrology for Transient Reactor Characterization Using Uranium Wires,” Nucl. Technol., 205, 1336 (2019); https://doi.org/10.1080/00295450.2019.1599613.
- N. E. WOOLSTENHULME and J. D. WEIST, “ATF Transient Testing Pre-Conceptual Design and Engineering Considerations Summary,” INL/EXT-13-29898, Idaho National Laboratory (2013).
- N. WOOLSTENHULME et al., “Development of Irradiation Test Devices for Transient Testing,” Nucl. Technol., 205, 1251 (2019); https://doi.org/10.1080/00295450.2019.1590072.
- S. R. JENSEN et al., “Restart of the Transient Reactor Test (TREAT) Facility Neutron Radiography Program,” Nucl. Technol., 205, 1325 (2019); https://doi.org/10.1080/00295450.2019.1605780.
- C. JENSEN and A. FLEMING, “Development of Advanced Instrumentation for Transient Testing,” Nucl. Technol., 205, 1354 (2019); https://doi.org/10.1080/00295450.2019.1627123.
- J. BUMGARDNER and D. M. WACHS, “Restarting the Transient Reactor Test (TREAT) Facility Reactor for Nuclear Transient Testing Science: A Special Issue of Nuclear Technology,” Nucl. Technol., 205, iv (2019); https://doi.org/10.1080/00295450.2019.1650605.
- T. HOLSCHUH et al., “Transient Reactor Test Facility Advanced Transient Shapes,” Nucl. Technol., 205, 1346 (2019); https://doi.org/10.1080/00295450.2018.1559712.
- C. L. POPE et al., “Transient Reactor Test (TREAT) Facility Design and Experiment Capability,” Nucl. Technol., 205, 1378 (2019); https://doi.org/10.1080/00295450.2019.1599615.
- Quality Assurance Requirements for Nuclear Facility Applications, Vol. NQA-1, American Society of Mechanical Engineering, Standard (2008).
- Quality Assurance Requirements for Nuclear Facility Applications Addenda, Vol. NQA-1A, American Society of Mechanical Engineering, Standard (2009).
- W. J. OBERKAMPF and D. P. AESCHLIMAN, “Issues in Computational Fluid Dynamics Code Verification and Validation,” Aiaa J., 36, 5, 733 (1998); https://doi.org/10.2514/2.456.
- INL/EXT-13-29898, N. E. WOOLSTENHULME and J. D. WIEST, Eds., p. 76, Idaho National Laboratory (2013).
- “Nuclear Technology Research and Development,” INL/EXT-19-55844, N. WOOLSTENHULME, Ed., Idaho National Laboratory (2019).
- J. CARMACK, “Future Transient Testing of Advanced Fuels,” INL/EXT-09-16392, pp. 1–48, Idaho National Laboratory (2009).
- D. L. LaBRIER and W. R. MARCUM, presented at the American Nuclear Society Annual Mtg., San Francisco, California, Vol. 116, p. 1397 (2017).
- D. L. LaBRIER, W. R. MARCUM, and J. NYLANDER, presented at the American Nuclear Society Annual Mtg., Philadelphia, Pennsylvania, Vol. 116, p. 1113 (2018).
- D. L. LaBRIER et al., “On the Performance of the Transient Reactor Test Loop (TRTL),” Proc. American Nuclear Society Annual Mtg., Philadelphia, Pennsylvania, Vol. 118, p. 1130, American Nuclear Society (2018).
- D. L. LaBRIER et al., Proc. 18th Int. Topl. Mtg. on Nuclear Reactor Thermal Hydraulics, Vol. 18, pp. 4983–4993, American Nuclear Society, (2019).
- “Status Report on Development of TREAT Water Loop,” INL/EXT-19-55730, N. WOOLSTENHULME, Ed. pp. 1–43, Idaho National Laboratory (2019).
- J. LEUNG, “Transient Critical Heat Flux and Blowdown Heat-Transfer Studies,” NUREG/CR-1559, Argonne National Lab (1980).
- Y. SIBAMOTO et al., “In-Pile Experiment in JMTR on the Radiation Induced Surface Activation (RISA) Effect on Flow-Boiling Heat Transfer,” J. Nucl. Sci. Technol., 44, 2, 183 (2007); https://doi.org/10.1080/18811248.2007.9711272.
- L. O. JERNKVIST and A. R. MASSIH, Eds., “Nuclear Fuel Behaviour Under Reactivity-Initiated Accident (RIA) Conditions,” Nuclear Energy Agency-Organisation for Economic Co-operation and Development (2010).
- N. ZUBER, “Hydrodynamic Aspects of Boiling Heat Transfer,” PhD Thesis, University of California (1959).
- K. PASAMEHMETOGLU, “Transient Critical Heat Flux,” PhD Thesis, University of Central Florida (1986).
- V. BESSIRON, T. SUGIYAMA, and T. FUKETA, “Clad-to-Coolant Heat Transfer in NSRR Experiments,” J. Nucl. Sci. Technol., 44, 723 (2007); https://doi.org/10.1080/18811248.2007.9711861.
- A. SAKURAI, “Mechanisms of Transitions to Film Boiling at CHFs in Subcooled and Pressurized Liquids due to Steady and Increasing Heat Inputs,” Nucl. Eng. Des., 197, 3, 301 (2000); https://doi.org/10.1016/S0029-5493(99)00314-3.
- S. S. KUTATELADZE, “Mechanisms of Transitions to Film Boiling at CHFs in Subcooled and Pressurized Liquids Due to Steady and Increasing Heat Inputs,” J. Tech. Phys., 20, 11, 1389 (1950).
- S. SAITO et al., “Development of In-Reactor Fuel Behavior Observation System,” J. Nucl. Sci. Technol., 18, 6, 427 (1981); https://doi.org/10.1080/18811248.1981.9733275.
- S. LEE et al., “Comparison of Steady and Transient Flow Boiling Critical Heat Flux for FeCrAl Accident Tolerant Fuel Cladding Alloy, Zircaloy, and Inconel,” Int. J. Heat Mass Transfer, 132, 643 (2019); https://doi.org/10.1016/j.ijheatmasstransfer.2018.11.141.
- “Fuel Cycle Research & Development Advanced Fuels Campaign,” INL/LTD-15-36768, A. BEASLEY et al., Eds., Idaho National Laboratory (2015).
- N. TODREAS and M. KAZIMI, Nuclear Systems Volume I: Thermal Hydraulic Fundamentals, CRC Press (2011).
- H. W. COLEMAN and W. G. STEELE, Experimentation, Validation, and Uncertainty Analysis for Engineers, 3rd ed.,John Wiley & Sons, Inc., Hoboken, New Jersey (2009).
- A. Z. MESQUITA and R. R. RODRIGUES, “Detection of the Departure from Nucleate Boiling in Nuclear Fuel Rod Simulators,” Int. J. Nucl. Energy, 2013, 1 (2013); https://doi.org/10.1155/2013/950129.