References
- N. OECD, State-of-the-Art Report on Light Water Reactor Accident-Tolerant Fuels, 2018.
- S. J. Zinkle, K. A. Terrani, J. C. Gehin, L. J. Ott, L. L. Snead, Accident tolerant fuels for LWRs: a perspective 448 (1) 374-379. doi:10.1016/j.jnucmat.2013.12.005. URL//www.sciencedirect.com/science/article/pii/S0022311513012919
- K.A. Terrani, Accident tolerant fuel cladding development: promise, status, and challenges 501 13-30, URL, http://www.sciencedirect.com/science/article/pii/S0022311517316227. https://doi.org/10.1016/j.jnucmat.2017.12.043
- L. Braase, Enhanced accident tolerant LWR fuels national metrics workshop report, URL, https://www.osti.gov/biblio/1073785.
- IAEA, Accident tolerant fuel concepts for light water reactors, URL, http://www-pub.iaea.org/books/IAEABooks/10972/Accident-Tolerant-Fuel-Concepts-for-Light-Water-Reactors.
- J.-H. Park, H.-G. Kim, J.-y. Park, Y.-I. Jung, D.-J. Park, Y.-H. Koo, High temperature steam-oxidation behavior of arc ion plated cr coatings for accident tolerant fuel claddings 280 256-259. doi:10.1016/j.surfcoat.2015.09.022. URL//www.sciencedirect.com/science/article/pii/S0257897215302607
- C. Tang, M. Stueber, H.J. Seifert, M. Steinbrueck, Protective coatings on zirconium-based alloys as accident-tolerant fuel (ATF) claddings, 35 (3) 141-165, https://www.degruyter.com/view/j/corrrev.2017.35.issue-3/corrrev-2017-0010/corrrev-2017-0010.xml. https://doi.org/10.1515/corrrev-2017-0010
- I. Younker, M. Fratoni, Neutronic evaluation of coating and cladding materials for accident tolerant fuels 88 10-18, URL,//www.sciencedirect.com/science/article/pii/S0149197015301074. https://doi.org/10.1016/j.pnucene.2015.11.006
- F. Fejt, M. Sevecek, J. Frybort, O. Novak, Study on neutronics of VVER-1200 with accident tolerant fuel cladding 124 579-591, URL, http://www.sciencedirect.com/science/article/pii/S030645491830567X. https://doi.org/10.1016/j.anucene.2018.10.040
- M. Sevecek, A. Gurgen, A. Seshadri, Y. Che, M. Wagih, B. Phillips, V. Champagne, K. Shirvan, Development of cr cold sprayecoated fuel cladding with enhanced accident tolerance, 50 (2) 229-236, http://www.sciencedirect.com/science/article/pii/S1738573317307283. https://doi.org/10.1016/j.net.2017.12.011
- J. Krejci, M. Sevecek, L. Cvrcek, J. Kabatova, F. Manoch, Chromium and chromium nitride coated cladding for nuclear reactor fuel, in: Proceedings of the 20th International Corrosion Congress, EUROCORR, 2017.
- M. Sevecek, M. Valach, Evaluation metrics applied to accident tolerant fuel cladding concepts for VVER reactors 4 89, URL, https://ojs.cvut.cz/ojs/index.php/APP/article/view/3749. https://doi.org/10.14311/AP.2016.4.0089
- B. Y. Volkov, V. V. Yakovlev, E. P. Ryazantsev, V. V. Kalygin, A. V. Burukin, A. V. Ivanov, Y. V. Pimenov, Particulars of the In-Reactor Behavior of VVER and PWR Uranium Dioxide Fuel with Pellets of Different Geometry vol. 114 (3) 169-176. https://doi.org/10.1007/s10512-013-9691-1
- Z. Yang, Y. Niu, J. Xue, T. Liu, C. Chang, X. Zheng, Steam oxidation resistance of plasma sprayed chromium-containing coatings at 1200c 0 (0), URL, https://onlinelibrary.wiley.com/doi/abs/10.1002/maco.201810156.
- J.-C. Brachet, I. Idarraga-Trujillo, M.L. Flem, M.L. Saux, V. Vandenberghe, S. Urvoy, E. Rouesne, T. Guilbert, C. Toffolon-Masclet, M. Tupin, C. Phalippou, F. Lomello, F. Schuster, A. Billard, G. Velisa, C. Ducros, F. Sanchette, Early studies on cr-coated zircaloy-4 as enhanced accident tolerant nuclear fuel claddings for light water reactors 517 268-285, URL, https://linkinghub.elsevier.com/retrieve/pii/S0022311518316519. https://doi.org/10.1016/j.jnucmat.2019.02.018
- J.C. Brachet, C. Lorrette, A. Michaux, C. Sauder, I. Idarraga-Trujillo, M. Le Saux, A. Ambard, CEA studies on advanced nuclear fuel claddings for enhanced accident tolerant LWRs fuel (LOCA and beyond LOCA conditions), URL, http://www-ist.cea.fr/publicea/exl-doc/201400000359_s1.pdf.
- S. Kuprin, V. Belous, V.N. Voyevodin, V.V. Bryk, R.L. Vasilenko, V.D. Ovcharenko, E.N. Reshetnyak, G.N. Tolmachova, P.N. V'yugov, Vacuumarc chromium-based coatings for protection of zirconium alloys from the high-temperature oxidation in air 465 400-406, URL, //www.sciencedirect.com/science/article/pii/S002231151530043X. https://doi.org/10.1016/j.jnucmat.2015.06.016
- J. Bischoff, C. Delafoy, C. Vauglin, P. Barberis, C. Roubeyrie, D. Perche, D. Duthoo, F. Schuster, J.-C. Brachet, E.W. Schweitzer, K. Nimishakavi, AREVA NP's enhanced accident-tolerant fuel developments: focus on cr-coated m5 cladding, 50 (2) 223-228, http://www.sciencedirect.com/science/article/pii/S1738573317307945. https://doi.org/10.1016/j.net.2017.12.004
- Y.-H. Koo, J.-H. Yang, J.-Y. Park, K.-S. Kim, H.-G. Kim, D.-J. Kim, Y.-I. Jung, K.-W. Song, KAERI's Development of LWR Accident-Tolerant Fuel 186 (vol. 2) 295-304, bibtex: koo2014kaeri. https://doi.org/10.13182/NT13-89
- A. Michau, F. Maury, F. Schuster, F. Lomello, J.C. Brachet, E. Rouesne, M. Le Saux, R. Boichot, M. Pons, High-temperature oxidation resistance of chromium-based coatings deposited by DLI-MOCVD for enhanced protection of the inner surface of long tubes 349 1048-1057, URL, http://www.sciencedirect.com/science/article/pii/S0257897218306625. https://doi.org/10.1016/j.surfcoat.2018.05.088
- D.V. Sidelev, E.B. Kashkarov, M.S. Syrtanov, V.P. Krivobokov, Nickel-chromium (niecr) coatings deposited by magnetron sputtering for accident tolerant nuclear fuel claddings 369 69-78, URL, https://linkinghub.elsevier.com/retrieve/pii/S0257897219304281. https://doi.org/10.1016/j.surfcoat.2019.04.057
- B. Maier, H. Yeom, G. Johnson, T. Dabney, J. Walters, P. Xu, J. Romero, H. Shah, K. Sridharan, Development of cold spray chromium coatings for improved accident tolerant zirconium-alloy cladding 519 247-254, URL, https://linkinghub.elsevier.com/retrieve/pii/S0022311518309620. https://doi.org/10.1016/j.jnucmat.2019.03.039
- K. Daub, R. Van Nieuwenhove, H. Nordin, Investigation of the impact of coatings on corrosion and hydrogen uptake of zircaloy-4 467 260-270, URL, http://linkinghub.elsevier.com/retrieve/pii/S0022311515302300. https://doi.org/10.1016/j.jnucmat.2015.09.041
- J. Rabe, K. Daub, H. Nordin, R. Van Nieuwenhove, T. Karlsen, Marie, R. Szoke, Investigation of PVD Coatings for Nuclear Applications: Hight Temperature Steam Exposure testingBibtex: IFE_numat.
- R. Van Nieuwenhove, V. Andersson, J. Balak, B. Oberlander, In-pile testing of CrN, TiAlN, and AlCrN coatings on zircaloy cladding in the halden reactor, in: Zirconium in the Nuclear Industry: 18th International Symposium, ASTM International.
- C. Meng, L. Yang, Y. Wu, J. Tan, W. Dang, X. He, X. Ma, Study of the oxidation behavior of CrN coating on zr alloy in air 515 354-369, URL, http://www.sciencedirect.com/science/article/pii/S0022311518310274. https://doi.org/10.1016/j.jnucmat.2019.01.006
- J. Krejci, M. Sevecek, L. Cvrcek, Development of Chromium and Chromium Nitride Coated Cladding for VVER Reactors.
- I. Safi, Recent aspects concerning DC reactive magnetron sputtering of thin films: a review, 127 (2) 203-218, http://www.sciencedirect.com/science/article/pii/S0257897200005661. https://doi.org/10.1016/S0257-8972(00)00566-1
- G. Brauer, B. Szyszka, M. Vergohl, R. Bandorf, Magnetron sputtering - milestones of 30 years, 84 (12) 1354-1359, http://www.sciencedirect.com/science/article/pii/S0042207X10000163. https://doi.org/10.1016/j.vacuum.2009.12.014
- P.J. Kelly, R.D. Arnell, Magnetron sputtering: a review of recent developments and applications, 56 (3) 159-172, http://www.sciencedirect.com/science/article/pii/S0042207X9900189X. https://doi.org/10.1016/S0042-207X(99)00189-X
- J.A. Thornton, The microstructure of sputteredeposited coatings, 4 (6) 3059-3065, http://avs.scitation.org/doi/abs/10.1116/1.573628.
- J. Bischoff, P. Blanpain, J. Brachet, C. Lorrette, A. Ambard, J. Strumpel, K. McKoy, Development of Fuels with Enhanced Accident Tolerance 22Bibtex: Bischoff2016development.
- Y.-H. Koo, J.-H. Yang, J.-Y. Park, Y.-S. Yang, H.-K. Kim, W.-K. In, K.-W. Song, Status of Dual Cooled Annular Fuel Development in KAERI.
- A. Krausova, L. Tuma, M. Novak, L. Cvrcek, J. Krejci, J. Macak, Chromium coating as a surface protection of zirconium alloys, 61 (5) 169-172, https://content.sciendo.com/view/journals/kom/61/5/article-p169.xml. https://doi.org/10.1515/kom-2017-0021
- R.E. Pawel, J.V. Cathcart, R.A. McKee, The kinetics of oxidation of zircaloy-4 in steam at high temperatures, 126 (7) 1105-1111, http://jes.ecsdl.org/content/126/7/1105. https://doi.org/10.1149/1.2129227
- R.E. Williford, Safety margins in zircaloy oxidation and embrittlement criteria for emergency core cooling system acceptance, 74 (3) 333-345, https://doi. org/10.13182/NT86-A33836.
- Y. Yan, B. E. Garrison, T. S. Smith, M. Howell, J. R. Keiser, G. L. Bell, Investigation of high-temperature oxidation kinetics and residual ductility of oxidized samples of sponge-based -110 alloy cladding tubes vol. 2 (21) 1203-1208. https://doi.org/10.1557/adv.2016.641
- C. GRANDJEAN, G. HACHE, Cladding Oxidation. Resistance to Quench and Post-quench Loads. 239.
- OECD, Nuclear Fuel Safety Criteria Technical Review (second ed.), Nuclear Safety, OECD Publishing. doi:10.1787/9789264991781-en. URL http://www.oecd-ilibrary.org/nuclear-energy/nuclear-fuel-safety-criteria-technicalreview-second-edition_9789264991781-en.
- M. Negyesi, V. Kloucek, J. Lorincik, L. Novotny, J. Kabatova, S. Linhart, J. Adamek, J. Siegl, V. Vrtilkova, Proposal of new o-beta oxidation criterion for new types of the zr1nb alloy of fuel claddings 261 260-268, URL, http://www.sciencedirect.com/science/article/pii/S0029549312005353. https://doi.org/10.1016/j.nucengdes.2012.09.033
- J. Brachet, V. Vandenberghe-Maillot, L. Portier, D. Gilbon, A. Lesbros, N. Waeckel, J. Mardon, Hydrogen content, preoxidation, and cooling scenario effects on post-quench microstructure and mechanical properties of zircaloy-4 and m5(R) alloys in LOCA conditions doi:10.1520/STP48132S, URL, http://www.astm.org/DIGITAL_LIBRARY/STP/PAGES/STP48132S.htm.
- X. Wenxin, Y. Shihao, Reaction diffusion in chromium-zircaloy-2 system, URL, http://inis.iaea.org/Search/search.aspx?orig_q=RN:33019170.
- K. KENG, M. Hamalainen, R. Luoma, A Thermodynamic Assessment of the Cr-Zr System 84 (1) 23-28, (bibtex*[publisher=Hanser]).
-
M. Steinbruck, M. Bottcher, Air oxidation of zircaloy-4, m5(R) and
$ZIRLO^{TM}$ cladding alloys at high temperatures, 414 (2) 276-285, https://www.sciencedirect.com/science/article/pii/S0022311511003631. https://doi.org/10.1016/j.jnucmat.2011.04.012 - E.J. Lahoda, P. Xu, Z. Karoutas, S. Ray, K. Sridharan, B. Maier, G. Johnson, Cold spray chromium coating for nuclear fuel rods, URL, http://patents.google.com/patent/US20180025793A1/en.
Cited by
- Chromium coatings deposited by cooled and hot target magnetron sputtering for accident tolerant nuclear fuel claddings vol.389, 2020, https://doi.org/10.1016/j.surfcoat.2020.125618
- Application and Development Progress of Cr-Based Surface Coating in Nuclear Fuel Elements: II. Current Status and Shortcomings of Performance Studies vol.10, pp.9, 2020, https://doi.org/10.3390/coatings10090835
- Protection of Zr Alloy under High-Temperature Air Oxidation: A Multilayer Coating Approach vol.11, pp.2, 2020, https://doi.org/10.3390/coatings11020227
- High-Temperature Oxidation of Cr-Coated Resistance Upset Welds Made from E110 Alloy vol.11, pp.5, 2021, https://doi.org/10.3390/coatings11050577
- Temelin Irradiated Cladding Project - TIRCLAD vol.1178, 2020, https://doi.org/10.1088/1757-899x/1178/1/012041
- The oxidation behaviors of Cr2N and Cr/Cr2N multilayer coatings on Zircaloy-4 tubes in high temperature environment vol.9, pp.3, 2020, https://doi.org/10.1088/2051-672x/ac2564
- Corrosion Behavior of Chromium Coated Zy-4 Cladding under CANDU Primary Circuit Conditions vol.11, pp.11, 2020, https://doi.org/10.3390/coatings11111417
- Unveiling damage mechanisms of chromium-coated zirconium-based fuel claddings at LWR operating temperature by in-situ digital image correlation vol.429, 2022, https://doi.org/10.1016/j.surfcoat.2021.127909
- High-temperature oxidation of Cr-coated laser beam welds made from E110 zirconium alloy vol.195, 2020, https://doi.org/10.1016/j.corsci.2021.110018
- Review on chromium coated zirconium alloy accident tolerant fuel cladding vol.895, pp.p1, 2020, https://doi.org/10.1016/j.jallcom.2021.162450