Search Results - "Journal of nuclear materials"

Accident tolerant fuel cladding development: Promise, status, and challenges by Terrani, Kurt A.

“…The motivation for transitioning away from zirconium-based fuel cladding in light water reactors to significantly more oxidation-resistant materials, thereby…”
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Primary radiation damage: A review of current understanding and models by Nordlund, Kai, Zinkle, Steven J., Sand, Andrea E., Granberg, Fredric, Averback, Robert S., Stoller, Roger E., Suzudo, Tomoaki, Malerba, Lorenzo, Banhart, Florian, Weber, William J., Willaime, Francois, Dudarev, Sergei L., Simeone, David

“…Scientific understanding of any kind of radiation effects starts from the primary damage, i.e. the defects that are produced right after an initial atomic…”
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Early studies on Cr-Coated Zircaloy-4 as enhanced accident tolerant nuclear fuel claddings for light water reactors by Brachet, Jean-Christophe, Idarraga-Trujillo, Isabel, Flem, Marion Le, Saux, Matthieu Le, Vandenberghe, Valérie, Urvoy, Stephane, Rouesne, Elodie, Guilbert, Thomas, Toffolon-Masclet, Caroline, Tupin, Marc, Phalippou, Christian, Lomello, Fernando, Schuster, Frédéric, Billard, Alain, Velisa, Gihan, Ducros, Cédric, Sanchette, Frédéric

“…Coatings with thicknesses between a few microns and ∼10  μm deposited on a Zircaloy-4 substrate have been studied with the objective to provide a significant…”
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Hydrogen in zirconium alloys: A review by Motta, Arthur T., Capolungo, Laurent, Chen, Long-Qing, Cinbiz, Mahmut Nedim, Daymond, Mark R., Koss, Donald A., Lacroix, Evrard, Pastore, Giovanni, Simon, Pierre-Clément A., Tonks, Michael R., Wirth, Brian D., Zikry, Mohammed A.

“…Hydrogen absorbed into zirconium alloy nuclear fuel cladding as a result of the waterside corrosion reaction can affect the properties of nuclear fuel,…”
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Materials for future nuclear energy systems by Was, G.S., Petti, D., Ukai, S., Zinkle, S.

“…Materials for future nuclear energy systems must operate under more extreme conditions than those in current Gen II or Gen III systems. These conditions…”
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Intragranular cellular segregation network structure strengthening 316L stainless steel prepared by selective laser melting by Zhong, Yuan, Liu, Leifeng, Wikman, Stefan, Cui, Daqing, Shen, Zhijian

“…A feasibility study was performed to fabricate ITER In-Vessel components by Selective Laser Melting (SLM) supported by Fusion for Energy (F4E). Almost fully…”
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High temperature oxidation and microstructural evolution of cold spray chromium coatings on Zircaloy-4 in steam environments by Yeom, Hwasung, Maier, Benjamin, Johnson, Greg, Dabney, Tyler, Lenling, Mia, Sridharan, Kumar

“…Oxidation kinetics and microstructural evolution of cold sprayed Cr coatings on Zircaloy-4 at 1130–1310 °C in flowing steam at atmospheric pressure have been…”
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The role of TeO2 insertion on the radiation shielding, structural and physical properties of borosilicate glasses by Aktas, Bulent, Acikgoz, Abuzer, Yilmaz, Demet, Yalcin, Serife, Dogru, Kaan, Yorulmaz, Nuri

“…•In this work, the effect of TeO2 insertion to borosilicate glasses is investigated.•The structural properties of BS-TeO2 glass systems are investigated by…”
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Materials and processes for the effective capture and immobilization of radioiodine: A review by Riley, Brian J., Vienna, John D., Strachan, Denis M., McCloy, John S., Jerden, James L.

“…The immobilization of radioiodine produced from reprocessing used nuclear fuel is a growing priority for research and development of nuclear waste forms. This…”
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Silicon carbide and its composites for nuclear applications – Historical overview by Katoh, Yutai, Snead, Lance L.

“…The goal of achieving higher thermal efficiency in nuclear power systems, whether fission or fusion based, has invariably led to the study and development of…”
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Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors by Yamamoto, Y., Pint, B.A., Terrani, K.A., Field, K.G., Yang, Y., Snead, L.L.

“…Development of nuclear grade, iron-based wrought FeCrAl alloys has been initiated for light water reactor (LWR) fuel cladding to serve as a substitute for…”
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Accident tolerant fuels for LWRs: A perspective by Zinkle, S.J., Terrani, K.A., Gehin, J.C., Ott, L.J., Snead, L.L.

“…The motivation for exploring the potential development of accident tolerant fuels in light water reactors to replace existing Zr alloy clad monolithic (U, Pu)…”
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Ferritic-martensitic steels for fission and fusion applications by Cabet, C., Dalle, F., Gaganidze, E., Henry, J., Tanigawa, H.

“…Compared to austenitic stainless steels, largely employed in the early fission reactors, high chromium Ferritic/Martenstic (FM) steels, developed since the…”
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Oxide inclusions in laser additive manufactured stainless steel and their effects on impact toughness and stress corrosion cracking behavior by Lou, Xiaoyuan, Andresen, Peter L., Rebak, Raul B.

“…Intergranular and intragranular Si and Mn rich oxide inclusions are present in laser additive manufactured austenitic stainless steel. The uniform oxide…”
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The new SOLPS-ITER code package by Wiesen, S., Reiter, D., Kotov, V., Baelmans, M., Dekeyser, W., Kukushkin, A.S., Lisgo, S.W., Pitts, R.A., Rozhansky, V., Saibene, G., Veselova, I., Voskoboynikov, S.

“…The SOLPS-ITER package represents a renewed coupling of the up-to-date parallelized EIRENE Monte-Carlo code and the B2.5 edge plasma solver. Each part of the…”
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High temperature Cr-Zr interaction of two types of Cr-coated Zr alloys in inert gas environment by Yang, Jianqiao, Stegmaier, Ulrike, Tang, Chongchong, Steinbrück, Martin, Große, Mirco, Wang, Shuzhong, Seifert, Hans Jürgen

“…The Cr-Zr interaction of two types of Cr coated Zr alloy accident tolerant fuel (ATF) claddings, deposited by cold spraying and magnetron sputtering, was…”
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Irradiation creep and growth of zirconium alloys: A critical review by Adamson, Ronald B., Coleman, Christopher E., Griffiths, Malcolm

“…The fuel channels and fuel assemblies of all conventional nuclear reactors that generate power from the fission of uranium by thermal neutrons are made from…”
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Disruptions in ITER and strategies for their control and mitigation by Lehnen, M., Aleynikova, K., Aleynikov, P.B., Campbell, D.J., Drewelow, P., Eidietis, N.W., Gasparyan, Yu, Granetz, R.S., Gribov, Y., Hartmann, N., Hollmann, E.M., Izzo, V.A., Jachmich, S., Kim, S.-H., Kočan, M., Koslowski, H.R., Kovalenko, D., Kruezi, U., Loarte, A., Maruyama, S., Matthews, G.F., Parks, P.B., Pautasso, G., Pitts, R.A., Reux, C., Riccardo, V., Roccella, R., Snipes, J.A., Thornton, A.J., de Vries, P.C.

“…The thermal and electromagnetic loads related to disruptions in ITER are substantial and require careful design of tokamak components to ensure they reach the…”
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Coated particle fuel: Historical perspectives and current progress by Demkowicz, Paul A., Liu, Bing, Hunn, John D.

“…Coated particle fuel concepts date back some 60 years, and have evolved significantly from the relatively primitive pyrocarbon-coated kernels envisioned by the…”
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Recent progress in the development of SiC composites for nuclear fusion applications by Koyanagi, T., Katoh, Y., Nozawa, T., Snead, L.L., Kondo, S., Henager, C.H., Ferraris, M., Hinoki, T., Huang, Q.

“…Silicon carbide (SiC) fiber reinforced SiC matrix composites continue to undergo development for fusion applications worldwide because of inherent advantages…”
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