Nuclear Engineering and Technology

  • 제54권11호
  • /
  • Pages.4084-4094
  • /
  • 2022
  • /
  • 1738-5733(pISSN)
  • /
  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
권호 표지
DOI QR코드

DOI QR Code

FAST irradiations and initial post irradiation examinations - Part I

  • G. Beausoleil (Idaho National Laboratory) ;
  • L. Capriotti (Idaho National Laboratory) ;
  • B. Curnutt (Idaho National Laboratory) ;
  • R. Fielding (Idaho National Laboratory) ;
  • S. Hayes (Idaho National Laboratory) ;
  • D. Wachs (Idaho National Laboratory)
  • 투고 : 2022.03.04
  • 심사 : 2022.07.14
  • 발행 : 2022.11.25
PDF 다운로드
⟨ 이전 논문 다음 논문 ⟩

초록

The Advanced Fuels Campaign Fission Accelerated Steady-state Test (FAST) at Idaho National Laboratory (INL) completed its first irradiation cycle within the Advanced Test Reactor (ATR). The test focused on the irradiation of alloy fuel forms for use in sodium fast reactors. The first cycle of FAST testing was completed and four rodlets were removed for the initial post irradiation examination (PIE). The rodlet design and irradiation conditions were evaluated using Monte Carlo N-Particle (MCNP) for as-run power history and COMSOL for temperature analysis. These rodlets include a set of low burnups (~2.5 % fissions per initial metal atoms [%FIMA]), control rodlets, and a helium-bonded annular rodlet (4.7 %FIMA). Nondestructive PIE has been completed and includes visual inspection, neutron radiography and gamma scanning of the FAST capsules and rodlets. Radiography confirmed the integrity of the experiments, revealed that the annulus in the annular fuel was filled at a modest burnup (4.7 %FIMA), and indicated potential slumping of the cooler rodlets at lower burnup. Precision gamma scanning indicated mostly usual fission product behavior, except for cesium in the He-bonded annular fuel. Future destructive PIE will be necessary to fully interpret the effects of accelerated irradiation on U-Zr metallic fuel behavior.

키워드

과제정보

This manuscript has been authored by Battelle Energy Alliance, LLC under Contract No. DE-AC07-05ID14517 with the U.S. Department of Energy. The United States Government retains and the publisher, by accepting the article for publication, acknowledges that the U.S. Government retains a nonexclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for U.S. Government purposes. The authors express sincere gratitude to Doug Porter, Andrea Jokisaari, and Alexandria Madden for peer review and editing support. The authors express sincere gratitude to Gary Povirk, Christopher Murdock, Ian Chestnut, HFEF operators, Nate Oldham, and many others for their continued support and input to the FAST project.

참고문헌

  1. G.L. Beausoleil, G.L. Povirk, B.J. Curnutt, A revised capsule design for the accelerated testing of advanced reactor fuels, Nucl. Technol. (2019) 1-14.
  2. K.A. Terrani, et al., Accelerating nuclear fuel development and qualification: modeling and simulation integrated with separate-effects testing, J. Nucl. Mater. (2020), 152267.
  3. C.M. Petrie, et al., Accelerated irradiation testing of miniature nuclear fuel and cladding specimens, in: Top Fuel 2018, 2018. Prague, Czech Republic.
  4. G.L. Beausoleil, et al., Integrating advanced modeling and accelerated testing for a modernized fuel qualification paradigm, Nucl. Technol. (2021) 1-20.
  5. J.M. Harp, et al., Testing Fast Reactor Fuels in a Thermal Reactor: a Comparison Report, Idaho National Lab. (INL), Idaho Falls, ID (United States), 2017.
  6. J.M. Harp, L. Capriotti, F. Cappia, Baseline Postirradiation Examination of the AFC-3C, AFC-3D, and AFC-4A Experiments, Idaho National Laboratory (INL), Idaho Falls, ID (United States), 2018.
  7. G.L. Beausoleil, G.L. Povirk, B.J. Curnutt, A Revised Capsule Design for the Accelerated Testing of Advanced Reactor Fuels, Idaho National Laboratory (INL), Idaho Falls, ID (United States), 2018.
  8. A.M. Oaks, Walid, Kun Mo, Abdellatif Yacout, Tanju Sofu, Paul Froehle, FIPD: EBR-II Fuels Irradiation & Physics Database, Argonne National Laboratory, Chicago, IL, USA, 2021.
  9. B. Curnutt, G.L. Beausoleil, The Fission Accelerated Steady State Test (FAST) e a revised capsule design for the accelerated testing of advanced reactor fuels, Trans. Am. Nucl. Soc. 120 (1) (2019) 293-296.
  10. W.J. Carmack, et al., Metallic fuels for advanced reactors, J. Nucl. Mater. 392 (2) (2009) 139-150. https://doi.org/10.1016/j.jnucmat.2009.03.007
  11. M.T. Benson, et al., SEM characterization of two advanced fuel alloys: U-10Zr4.3Sn and U-10Zr-4.3Sn-4.7Ln, J. Nucl. Mater. 494 (2017) 334-341. https://doi.org/10.1016/j.jnucmat.2017.07.057
  12. M.T. Benson, et al., Microstructural characterization of annealed U-12Zr-4Pd and U-12Zr-4Pd-5Ln: investigating Pd as a metallic fuel additive, J. Nucl. Mater. 502 (2018) 106-112. https://doi.org/10.1016/j.jnucmat.2018.02.012
  13. R.D. Mariani, et al., Lanthanides in metallic nuclear fuels: their behavior and methods for their control, J. Nucl. Mater. 419 (1e3) (2011) 263-271. https://doi.org/10.1016/j.jnucmat.2011.08.036
  14. J. Isler, et al., Experimental solubility measurements of lanthanides in liquid alkalis, J. Nucl. Mater. 495 (2017) 438-441. https://doi.org/10.1016/j.jnucmat.2017.08.039
  15. J.M. Harp, H.J.M. Chichester, L. Capriotti, Postirradiation examination results of several metallic fuel alloys and forms from low burnup AFC irradiations, J. Nucl. Mater. 509 (2018) 377-391. https://doi.org/10.1016/j.jnucmat.2018.07.003
  16. J.D. Hales, et al., BISON Theory Manual the Equations Behind Nuclear Fuel Analysis, Idaho National Lab (INL), Idaho Falls, ID (United States), 2016, p. 156.
  17. A.G. Croff, ORIGEN2: a versatile computer code for calculating the nuclide compositions and characteristics of nuclear materials, Nucl. Technol. 62 (3) (1983) 335-352. https://doi.org/10.13182/NT83-1
  18. J.E. Sweezy, MCNP - A General Purpose Monte Carlo N-Particle Transport Code, Los Alamos National Laboratory, New Mexico, United States, 2003.
  19. M.B. Chadwick, et al., ENDF/B-VII.0: next generation evaluated Nuclear data library for Nuclear Science and Technology, Nucl. Data Sheets 107 (12) (2006) 2931-3060. https://doi.org/10.1016/j.nds.2006.11.001
  20. M.A. Plummer, N. Johnson, L. Hull, NDMAS System and Process Description, 2020 (United States).
  21. A.E. Craft, et al., Neutron radiography of irradiated nuclear fuel at Idaho National Laboratory, Phys. Procedia 69 (2015) 483-490. https://doi.org/10.1016/j.phpro.2015.07.068
  22. W.J. Williams, et al., Assessment of swelling and constituent redistribution in uranium-zirconium fuel using phenomena identification and ranking tables (PIRT), Annals Nucl. Energy 136 (2020), 107016.
  23. G.L. Hofman, L.C. Walters, T.H. Bauer, Metallic fast reactor fuels, Prog. Nucl. Energy 31 (1) (1997) 83-110. https://doi.org/10.1016/0149-1970(96)00005-4
  24. W.J. Williams, et al., In situ neutron diffraction study of crystallographic evolution and thermal expansion coefficients in U-22.5 at.%Zr during annealing, JOM 72 (5) (2020) 2042-2050. https://doi.org/10.1007/s11837-020-04086-8
  25. W.J. Carmack, et al., Examination of Legacy Metallic Fuel Pins (U-10Zr) Tested in FFTF, Idaho National Laboratory (INL), Idaho Falls, ID (United States), 2020.
  26. W.J. Carmack, et al., Metallography and fuel cladding chemical interaction in fast flux test facility irradiated metallic U-10Zr MFF-3 and MFF-5 fuel pins, J. Nucl. Mater. 473 (2016) 167-177.  https://doi.org/10.1016/j.jnucmat.2016.02.019