Prospects for additive manufacturing of nuclear fuel forms

Nelson, Andrew T.

doi:10.1016/j.pnucene.2022.104493

Prospects for additive manufacturing of nuclear fuel forms

Journal Article · Fri Nov 18 00:00:00 EST 2022 · Progress in Nuclear Energy

DOI:https://doi.org/10.1016/j.pnucene.2022.104493· OSTI ID:1899016

^[1]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

Additive manufacturing (AM) is viewed as a critical enabling technology for achieving superior performance and improved economics across many sectors. Although the past decade has seen increased application of AM methods to nuclear reactor cladding and structural materials, exploration of AM as applied to the uranium-bearing nuclear fuel forms has been limited. The two major families of nuclear fuel forms (monolithic, particle/dispersion) are utilized with their own set of core objectives in mind, and their differences require distinct fabrication infrastructures. These reference fabrication methods impose many limitations on nuclear fuels. Further, both currently operating reactors and future concepts have the potential for improved performance if these accepted limitations are relaxed or removed entirely. The primary limitations of reference fabrication processes for the common nuclear fuel forms are outlined in this paper. This groundwork is then used to identify avenues of fuel performance specific to each of these fuel architectures that could be exploited if the restrictions of conventional fuel fabrication are removed. Moreover, multiple targets for AM studies are laid out for each of the major nuclear fuel variants. Finally, key strategic components to guide research activities in AM of nuclear fuels are outlined, with an emphasis on use of modeling and simulation to motivate research aims and embrace of an accelerated testing methodology to screen and quality new fuel forms.

View Accepted Manuscript (DOE)

Research Organization:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1899016

Journal Information:: Progress in Nuclear Energy, Journal Name: Progress in Nuclear Energy Journal Issue: 1 Vol. 155; ISSN 0149-1970

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (169)

Design of Optimal Organic Materials System for Ceramic Suspension‐Based Additive Manufacturing Chung, Kyeongwoon; Nenov, Nenko S.; Park, Sujin Advanced Engineering Materials, Vol. 21, Issue 10 https://doi.org/10.1002/adem.201900445	journal	August 2019
Recent Progress in Additive Manufacturing of Fiber Reinforced Polymer Composite Goh, Guo Dong; Yap, Yee Ling; Agarwala, Shweta Advanced Materials Technologies, Vol. 4, Issue 1 https://doi.org/10.1002/admt.201800271	journal	October 2018
Review of the microheterogeneous thoria‐urania fuel for micro‐sized high temperature reactors Rabir, Mohamad Hairie; Ismail, Aznan Fazli; Yahya, Mohd Syukri International Journal of Energy Research, Vol. 45, Issue 8 https://doi.org/10.1002/er.5923	journal	September 2020
Swelling behavior of U-Pu-Zr fuel Hofman, Gerard L.; Pahl, R. G.; Lahm, C. E. Metallurgical Transactions A, Vol. 21, Issue 2 https://doi.org/10.1007/BF02671924	journal	February 1990
On structural topology optimization using graded porosity control Schmidt, Martin-Pierre; Pedersen, Claus B. W.; Gout, Christian Structural and Multidisciplinary Optimization, Vol. 60, Issue 4 https://doi.org/10.1007/s00158-019-02275-x	journal	April 2019
The effect of scanning strategy on laser fusion of functionally graded H13/Cu materials Beal, V. E.; Erasenthiran, P.; Hopkinson, N. The International Journal of Advanced Manufacturing Technology, Vol. 30, Issue 9-10 https://doi.org/10.1007/s00170-005-0130-x	journal	May 2006
Economics of additive manufacturing for end-usable metal parts Atzeni, Eleonora; Salmi, Alessandro The International Journal of Advanced Manufacturing Technology, Vol. 62, Issue 9-12 https://doi.org/10.1007/s00170-011-3878-1	journal	February 2012
A fabrication methodology for dual-material engineering structures using ultrasonic additive manufacturing Obielodan, John; Stucker, Brent The International Journal of Advanced Manufacturing Technology, Vol. 70, Issue 1-4 https://doi.org/10.1007/s00170-013-5266-5	journal	September 2013
Characterization of direct selective laser sintering of alumina Fayed, E. M.; Elmesalamy, A. S.; Sobih, M. The International Journal of Advanced Manufacturing Technology, Vol. 94, Issue 5-8 https://doi.org/10.1007/s00170-017-0981-y	journal	September 2017
Review of additive manufacturing methods for high-performance ceramic materials Wang, Jia-Chang; Dommati, Hitesh; Hsieh, Sheng-Jen The International Journal of Advanced Manufacturing Technology, Vol. 103, Issue 5-8 https://doi.org/10.1007/s00170-019-03669-3	journal	April 2019
Analytical modelling of in situ layer-wise defect detection in 3D-printed parts: additive manufacturing Bowoto, Oluwole K.; Oladapo, Bankole I.; Zahedi, S. A. The International Journal of Advanced Manufacturing Technology, Vol. 111, Issue 7-8 https://doi.org/10.1007/s00170-020-06241-6	journal	October 2020
Powder metallurgical fabrication of zirconium matrix cermet nuclear fuels Totemeier, Aaron R.; McDeavitt, Sean M. Journal of Materials Science, Vol. 44, Issue 20 https://doi.org/10.1007/s10853-009-3767-2	journal	August 2009
Nitride fuel for Gen IV nuclear power systems Ekberg, Christian; Ribeiro Costa, Diogo; Hedberg, Marcus Journal of Radioanalytical and Nuclear Chemistry, Vol. 318, Issue 3 https://doi.org/10.1007/s10967-018-6316-0	journal	November 2018
A Review of Finite Element Method Models for Nuclear Graphite Applications Arregui-Mena, José David; Worth, Robert N.; Hall, Graham Archives of Computational Methods in Engineering, Vol. 27, Issue 1 https://doi.org/10.1007/s11831-018-09310-y	journal	December 2018
Progress and challenges towards additive manufacturing of SiC ceramic He, Rujie; Zhou, Niping; Zhang, Keqiang Journal of Advanced Ceramics, Vol. 10, Issue 4 https://doi.org/10.1007/s40145-021-0484-z	journal	July 2021
The effect of additives on the irradiation behaviour of UO2 Killeen, J. C. Journal of Nuclear Materials, Vol. 58, Issue 1 https://doi.org/10.1016/0022-3115(75)90164-6	journal	October 1975
Sintering characterization of UO2 powders Timmermans, W.; van Heck-Hennen, A.; Gorle, F. Journal of Nuclear Materials, Vol. 71, Issue 2 https://doi.org/10.1016/0022-3115(78)90423-3	journal	January 1978
High burnup performance of annular UO2 fuel with inter-pellet graphite discs Hastings, I. J.; Macdonald, R. D. Journal of Nuclear Materials, Vol. 126, Issue 2 https://doi.org/10.1016/0022-3115(84)90088-6	journal	October 1984
Correlation between UO2 powder and pellet quality in PHWR fuel manufacturing Glodeanu, F.; Spinzi, M.; Bălan, V. Journal of Nuclear Materials, Vol. 153 https://doi.org/10.1016/0022-3115(88)90207-3	journal	April 1988
Irradiation behavior of metallic fast reactor fuels Pahl, R. G.; Porter, D. L.; Crawford, D. C. Journal of Nuclear Materials, Vol. 188 https://doi.org/10.1016/0022-3115(92)90447-S	journal	June 1992
History of fast reactor fuel development Kittel, J. H.; Frost, B. R. T.; Mustelier, J. P. Journal of Nuclear Materials, Vol. 204 https://doi.org/10.1016/0022-3115(93)90193-3	journal	September 1993
Casting of metallic fuel containing minor actinide additions Trybus, C. L.; Sanecki, J. E.; Henslee, S. P. Journal of Nuclear Materials, Vol. 204 https://doi.org/10.1016/0022-3115(93)90198-8	journal	September 1993
Criteria for selecting the components of composites Ashby, M. F. Acta Metallurgica et Materialia, Vol. 41, Issue 5 https://doi.org/10.1016/0956-7151(93)90242-K	journal	May 1993
Reduction of the open porosity of UO2 pellets through pore structure control Song, Kun Woo; Kim, Keon Sik; Kim, Young Min Journal of Nuclear Materials, Vol. 279, Issue 2-3 https://doi.org/10.1016/S0022-3115(00)00004-0	journal	June 2000
Grain size control of UO2 pellets by adding heat-treated U3O8 particles to UO2 powder Song, Kun Woo; Sik Kim, Keon; Won Kang, Ki Journal of Nuclear Materials, Vol. 317, Issue 2-3 https://doi.org/10.1016/S0022-3115(03)00080-1	journal	May 2003
Zirconium nitride as inert matrix for fast systems Streit, M.; Ingold, F.; Pouchon, M. Journal of Nuclear Materials, Vol. 319 https://doi.org/10.1016/S0022-3115(03)00133-8	journal	June 2003
Reaction layer growth and reaction heat of U–Mo/Al dispersion fuels using centrifugally atomized powders Ryu, Ho Jin; Han, Young Soo; Park, Jong Man Journal of Nuclear Materials, Vol. 321, Issue 2-3 https://doi.org/10.1016/S0022-3115(03)00251-4	journal	September 2003
Thermal compatibility studies of U3Si2 dispersion fuels prepared with centrifugally atomized powder Kim, Ki-Hwan; Park, Jong-Man; Kim, Chang-Kyu Journal of Nuclear Materials, Vol. 270, Issue 3 https://doi.org/10.1016/S0022-3115(99)00005-7	journal	April 1999
Building blocks for a digital twin of additive manufacturing Knapp, G. L.; Mukherjee, T.; Zuback, J. S. Acta Materialia, Vol. 135 https://doi.org/10.1016/j.actamat.2017.06.039	journal	August 2017
Selective laser melting enabled additive manufacturing of Ti–22Al–25Nb intermetallic: Excellent combination of strength and ductility, and unique microstructural features associated Zhou, Y. H.; Li, W. P.; Wang, D. W. Acta Materialia, Vol. 173 https://doi.org/10.1016/j.actamat.2019.05.008	journal	July 2019
Production of small uranium dioxide microspheres for cermet nuclear fuel using the internal gelation process Hunt, R. D.; Hickman, R. R.; Ladd-Lively, J. L. Annals of Nuclear Energy, Vol. 69 https://doi.org/10.1016/j.anucene.2014.02.003	journal	July 2014
Reactor physics phenomena in additively manufactured control elements for the High Flux Isotope Reactor Burns, Joseph R.; Petrovic, Bojan; Chandler, David Annals of Nuclear Energy, Vol. 115 https://doi.org/10.1016/j.anucene.2018.02.003	journal	May 2018
Neutronic and thermal-hydraulic feasibility studies for High Flux Isotope Reactor conversion to low-enriched uranium silicide dispersion fuel Chandler, D.; Betzler, B.; Cook, D. Annals of Nuclear Energy, Vol. 130 https://doi.org/10.1016/j.anucene.2019.02.037	journal	August 2019
In-situ fabrication of dispersion nuclear fuel pellets with a core-shell structure Song, Tong; Wang, Yixiao; Chang, Zhenqi Annals of Nuclear Energy, Vol. 134 https://doi.org/10.1016/j.anucene.2019.06.028	journal	December 2019
The technology of micro heat pipe cooled reactor: A review Yan, B. H.; Wang, C.; Li, L. G. Annals of Nuclear Energy, Vol. 135 https://doi.org/10.1016/j.anucene.2019.106948	journal	January 2020
Assessment of swelling and constituent redistribution in uranium-zirconium fuel using phenomena identification and ranking tables (PIRT) Williams, W. J.; Wachs, D. M.; Okuniewski, M. A. Annals of Nuclear Energy, Vol. 136 https://doi.org/10.1016/j.anucene.2019.107016	journal	February 2020
Reactor and fuel cycle performance of light water reactor fuel with 235U enrichments above 5% Burns, Joseph R.; Hernandez, Richard; Terrani, Kurt A. Annals of Nuclear Energy, Vol. 142 https://doi.org/10.1016/j.anucene.2020.107423	journal	July 2020
Functionally graded materials: A review of fabrication and properties Naebe, Minoo; Shirvanimoghaddam, Kamyar Applied Materials Today, Vol. 5 https://doi.org/10.1016/j.apmt.2016.10.001	journal	December 2016
Characterization of ceramic components fabricated using binder jetting additive manufacturing technology Gonzalez, J. A.; Mireles, J.; Lin, Y. Ceramics International, Vol. 42, Issue 9 https://doi.org/10.1016/j.ceramint.2016.03.079	journal	July 2016
Microstructure and mechanical properties of functionally graded TiCp/Ti6Al4V composite fabricated by laser melting deposition Li, Liqun; Wang, Jiandong; Lin, Panpan Ceramics International, Vol. 43, Issue 18 https://doi.org/10.1016/j.ceramint.2017.09.054	journal	December 2017
Characterization of zirconia specimens fabricated by ceramic on-demand extrusion Li, Wenbin; Ghazanfari, Amir; McMillen, Devin Ceramics International, Vol. 44, Issue 11 https://doi.org/10.1016/j.ceramint.2018.04.008	journal	August 2018
Laser additive manufacturing and homogeneous densification of complicated shape SiC ceramic parts Liu, Kai; Wu, Tian; Bourell, David L. Ceramics International, Vol. 44, Issue 17 https://doi.org/10.1016/j.ceramint.2018.08.143	journal	December 2018
Binder jetting additive manufacturing of aluminum nitride components Díaz-Moreno, Carlos A.; Lin, Y.; Hurtado-Macías, A. Ceramics International, Vol. 45, Issue 11 https://doi.org/10.1016/j.ceramint.2019.03.187	journal	August 2019
SiC whisker strengthened UO2–Mo composite pellets with superior thermal-mechanical properties Cheng, Liang; Gao, Rui; Yan, Biaojie Ceramics International, Vol. 45, Issue 17 https://doi.org/10.1016/j.ceramint.2019.08.039	journal	December 2019
Freeze-form extrusion fabrication of functionally graded materials Leu, Ming C.; Deuser, Bradley K.; Tang, Lie CIRP Annals, Vol. 61, Issue 1 https://doi.org/10.1016/j.cirp.2012.03.050	journal	January 2012
Technologies in additive manufacturing for fiber reinforced composite materials: a review K., Palanikumar; M., Mudhukrishnan; P., Soorya Prabha Current Opinion in Chemical Engineering, Vol. 28 https://doi.org/10.1016/j.coche.2020.01.001	journal	June 2020
Multiscale modeling of solid propellants: From particle packing to failure Matous, K.; Inglis, H.; Gu, X. Composites Science and Technology, Vol. 67, Issue 7-8 https://doi.org/10.1016/j.compscitech.2006.06.017	journal	June 2007
Defects and anomalies in powder bed fusion metal additive manufacturing Mostafaei, Amir; Zhao, Cang; He, Yining Current Opinion in Solid State and Materials Science, Vol. 26, Issue 2 https://doi.org/10.1016/j.cossms.2021.100974	journal	April 2022
Engineering demonstration reactors: A stepping stone on the path to deployment of advanced nuclear energy in the United States Brown, Nicholas R. Energy, Vol. 238 https://doi.org/10.1016/j.energy.2021.121750	journal	January 2022
A wicked heat pipe fabricated using metal additive manufacturing Robinson, A. J.; Colenbrander, J.; Deaville, T. International Journal of Thermofluids, Vol. 12 https://doi.org/10.1016/j.ijft.2021.100117	journal	November 2021
3D printing of ceramics: A review Chen, Zhangwei; Li, Ziyong; Li, Junjie Journal of the European Ceramic Society, Vol. 39, Issue 4 https://doi.org/10.1016/j.jeurceramsoc.2018.11.013	journal	April 2019
Extrusion-based additive manufacturing of functionally graded ceramics Li, Wenbin; Armani, Amir; Martin, Austin Journal of the European Ceramic Society, Vol. 41, Issue 3 https://doi.org/10.1016/j.jeurceramsoc.2020.10.029	journal	March 2021
Review of additive manufacturing and densification techniques for the net- and near net-shaping of geometrically complex silicon nitride components Aguirre, Trevor G.; Cramer, Corson L.; Mitchell, David J. Journal of the European Ceramic Society, Vol. 42, Issue 3 https://doi.org/10.1016/j.jeurceramsoc.2021.11.001	journal	March 2022
Promising characteristics of gradient porosity Ti-6Al-4V alloy prepared by SLM process Fousová, Michaela; Vojtěch, Dalibor; Kubásek, Jiří Journal of the Mechanical Behavior of Biomedical Materials, Vol. 69 https://doi.org/10.1016/j.jmbbm.2017.01.043	journal	May 2017
Sintering behaviour and microstructures of carbides and nitrides for the inert matrix fuel by spark plasma sintering Ryu, Ho Jin; Lee, Young Woo; Cha, Seung Il Journal of Nuclear Materials, Vol. 352, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2006.02.089	journal	June 2006
Estimation of maximum coated particle fuel compact packing fraction Morris, R. N.; Pappano, P. J. Journal of Nuclear Materials, Vol. 361, Issue 1 https://doi.org/10.1016/j.jnucmat.2006.10.017	journal	March 2007
Dispersion type zirconium matrix fuels fabricated by capillary impregnation method Savchenko, A.; Konovalov, I.; Vatulin, A. Journal of Nuclear Materials, Vol. 362, Issue 2-3 https://doi.org/10.1016/j.jnucmat.2007.01.211	journal	May 2007
An approach to fuel development and qualification Crawford, Douglas C.; Porter, Douglas L.; Hayes, Steven L. Journal of Nuclear Materials, Vol. 371, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2007.05.029	journal	September 2007
A novel approach to fabricating fuel compacts for the next generation nuclear plant (NGNP) Pappano, P. J.; Burchell, T. D.; Hunn, J. D. Journal of Nuclear Materials, Vol. 381, Issue 1-2 https://doi.org/10.1016/j.jnucmat.2008.07.032	journal	October 2008
A US perspective on fast reactor fuel fabrication technology and experience part I: metal fuels and assembly design Burkes, Douglas E.; Fielding, Randall S.; Porter, Douglas L. Journal of Nuclear Materials, Vol. 389, Issue 3 https://doi.org/10.1016/j.jnucmat.2009.02.035	journal	June 2009
Microstructural development in irradiated U-7Mo/6061 Al alloy matrix dispersion fuel Keiser, Dennis D.; Robinson, Adam B.; Jue, Jan-Fong Journal of Nuclear Materials, Vol. 393, Issue 2 https://doi.org/10.1016/j.jnucmat.2009.06.018	journal	September 2009
Main results of the development of dispersion type IMF at A.A. Bochvar Institute Savchenko, A. M.; Vatulin, A. V.; Glagovsky, E. M. Journal of Nuclear Materials, Vol. 396, Issue 1 https://doi.org/10.1016/j.jnucmat.2009.10.048	journal	January 2010
Interdiffusion in U3Si–Al, U3Si2–Al, and USi–Al dispersion fuels during irradiation Kim, Yeon Soo; Hofman, Gerard L. Journal of Nuclear Materials, Vol. 410, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2010.12.031	journal	March 2011
Fabrication and characterization of fully ceramic microencapsulated fuels Terrani, K. A.; Kiggans, J. O.; Katoh, Y. Journal of Nuclear Materials, Vol. 426, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.03.049	journal	July 2012
Fabrication and preliminary evaluation of metal matrix microencapsulated fuels Terrani, Kurt A.; Kiggans, Jim O.; Snead, Lance L. Journal of Nuclear Materials, Vol. 427, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.04.010	journal	August 2012
Microencapsulated fuel technology for commercial light water and advanced reactor application Terrani, Kurt A.; Snead, Lance L.; Gehin, Jess C. Journal of Nuclear Materials, Vol. 427, Issue 1-3, p. 209-224 https://doi.org/10.1016/j.jnucmat.2012.05.021	journal	August 2012
The influence of SiC particle size and volume fraction on the thermal conductivity of spark plasma sintered UO2–SiC composites Yeo, Sunghwan; Baney, Ronald; Subhash, Ghatu Journal of Nuclear Materials, Vol. 442, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.09.003	journal	November 2013
Accident tolerant fuels for LWRs: A perspective Zinkle, S. J.; Terrani, K. A.; Gehin, J. C. Journal of Nuclear Materials, Vol. 448, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.12.005	journal	May 2014
Rapidly solidified U–6wt%Nb powders for dispersion-type nuclear fuels McKeown, Joseph T.; Hsiung, Luke L.; Ryu, Ho Jin Journal of Nuclear Materials, Vol. 448, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2014.01.033	journal	May 2014
Manufacture of fully dense uranium nitride pellets using hydride derived powders with spark plasma sintering Malkki, Pertti; Jolkkonen, Mikael; Hollmer, Tobias Journal of Nuclear Materials, Vol. 452, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2014.06.012	journal	September 2014
Progress on matrix SiC processing and properties for fully ceramic microencapsulated fuel form Terrani, K. A.; Kiggans, J. O.; Silva, C. M. Journal of Nuclear Materials, Vol. 457 https://doi.org/10.1016/j.jnucmat.2014.10.034	journal	February 2015
Uranium silicide pellet fabrication by powder metallurgy for accident tolerant fuel evaluation and irradiation Harp, Jason M.; Lessing, Paul A.; Hoggan, Rita E. Journal of Nuclear Materials, Vol. 466 https://doi.org/10.1016/j.jnucmat.2015.06.027	journal	November 2015
A comparative study of nitride purity and Am fabrication losses in PuN materials by the powder and internal gelation production routes Hedberg, Marcus; Ekberg, Christian Journal of Nuclear Materials, Vol. 482 https://doi.org/10.1016/j.jnucmat.2016.10.025	journal	December 2016
High density, uniformly distributed W/UO2 for use in Nuclear Thermal Propulsion Tucker, Dennis S.; Barnes, Marvin W.; Hone, Lance Journal of Nuclear Materials, Vol. 486 https://doi.org/10.1016/j.jnucmat.2017.01.033	journal	April 2017
Early progress on additive manufacturing of nuclear fuel materials Bergeron, A.; Crigger, J. B. Journal of Nuclear Materials, Vol. 508 https://doi.org/10.1016/j.jnucmat.2018.05.058	journal	September 2018
Postirradiation examination results of several metallic fuel alloys and forms from low burnup AFC irradiations Harp, Jason M.; Chichester, Heather J. M.; Capriotti, Luca Journal of Nuclear Materials, Vol. 509 https://doi.org/10.1016/j.jnucmat.2018.07.003	journal	October 2018
Postirradiation examination on metallic fuel in the AFC-2 irradiation test series Harp, Jason M.; Capriotti, Luca; Chichester, Heather J. M. Journal of Nuclear Materials, Vol. 509 https://doi.org/10.1016/j.jnucmat.2018.07.019	journal	October 2018
Grain size and phase purity characterization of U3Si2 fuel pellets Hoggan, Rita E.; Tolman, Kevin R.; Cappia, Fabiola Journal of Nuclear Materials, Vol. 512 https://doi.org/10.1016/j.jnucmat.2018.10.011	journal	December 2018
Radiation damage and irradiation-assisted stress corrosion cracking of additively manufactured 316L stainless steels Song, Miao; Wang, Mi; Lou, Xiaoyuan Journal of Nuclear Materials, Vol. 513 https://doi.org/10.1016/j.jnucmat.2018.10.044	journal	January 2019
Production of more ideal uranium trioxide microspheres for the sol-gel microsphere pelletization process without the use of carbon Hunt, R. D.; Collins, J. L.; Lloyd, M. H. Journal of Nuclear Materials, Vol. 515 https://doi.org/10.1016/j.jnucmat.2018.12.029	journal	March 2019
Fabrication of UO2-Mo composite fuel with enhanced thermal conductivity from sol-gel feedstock Finkeldei, S. C.; Kiggans, J. O.; Hunt, R. D. Journal of Nuclear Materials, Vol. 520 https://doi.org/10.1016/j.jnucmat.2019.04.011	journal	July 2019
Performance of a ferritic/martensitic steel for nuclear reactor applications fabricated using additive manufacturing Sridharan, Niyanth; Gussev, Maxim N.; Field, Kevin G. Journal of Nuclear Materials, Vol. 521 https://doi.org/10.1016/j.jnucmat.2019.04.020	journal	August 2019
A study of constituent redistribution in U–Zr fuels using quantitative phase-field modeling and sensitivity analysis Hirschhorn, Jacob; Tonks, Michael R.; Aitkaliyeva, Assel Journal of Nuclear Materials, Vol. 523 https://doi.org/10.1016/j.jnucmat.2019.05.053	journal	September 2019
Separate effects irradiation testing of miniature fuel specimens Petrie, Christian M.; Burns, Joseph R.; Raftery, Alicia M. Journal of Nuclear Materials, Vol. 526 https://doi.org/10.1016/j.jnucmat.2019.151783	journal	December 2019
Production of 28 μm zirconium carbide kernels using the internal gelation process and microfluidics Hunt, R. D.; McMurray, J. W.; Helmreich, G. W. Journal of Nuclear Materials, Vol. 528 https://doi.org/10.1016/j.jnucmat.2019.151870	journal	January 2020
Uranium nitride tristructural-isotropic fuel particle Terrani, Kurt A.; Jolly, Brian C.; Harp, Jason M. Journal of Nuclear Materials, Vol. 531 https://doi.org/10.1016/j.jnucmat.2020.152034	journal	April 2020
Accelerating nuclear fuel development and qualification: Modeling and simulation integrated with separate-effects testing Terrani, Kurt A.; Capps, Nathan A.; Kerr, Matthew J. Journal of Nuclear Materials, Vol. 539 https://doi.org/10.1016/j.jnucmat.2020.152267	journal	October 2020
Investigation of the microstructure evolution of alpha uranium after in pile transient Di Lemma, Fidelma G.; Liu, Xiang; Holschuh, Tommy V. Journal of Nuclear Materials, Vol. 542 https://doi.org/10.1016/j.jnucmat.2020.152467	journal	December 2020
Impact of uranium oxide (UO2) fuel with molybdenum (Mo) inserts on pressurized water reactor performance and safety Gorton, Jacob P.; Schappel, Daniel; Nelson, Andrew T. Journal of Nuclear Materials, Vol. 542 https://doi.org/10.1016/j.jnucmat.2020.152492	journal	December 2020
Additive manufacturing of silicon carbide for nuclear applications Koyanagi, Takaaki; Terrani, Kurt; Harrison, Shay Journal of Nuclear Materials, Vol. 543 https://doi.org/10.1016/j.jnucmat.2020.152577	journal	January 2021
Graphite flakes/UO2 fuel pellets with excellent thermal conductivity in radial direction Li, Bingqing; Yang, Zhenliang; Wang, Zhiyi Journal of Nuclear Materials, Vol. 545 https://doi.org/10.1016/j.jnucmat.2020.152639	journal	March 2021
Regulatory Research Perspective on Additive Manufacturing for Nuclear Component Applications Hiser, Matthew; Schneider, Alyssa; Audrain, Margaret Journal of Nuclear Materials, Vol. 546 https://doi.org/10.1016/j.jnucmat.2020.152726	journal	April 2021
Qualification pathways for additively manufactured components for nuclear applications Hensley, C.; Sisco, K.; Beauchamp, S. Journal of Nuclear Materials, Vol. 548 https://doi.org/10.1016/j.jnucmat.2021.152846	journal	May 2021
Influence of neutron irradiation on Al-6061 alloy produced via ultrasonic additive manufacturing Gussev, M. N.; Sridharan, N.; Babu, S. S. Journal of Nuclear Materials, Vol. 550 https://doi.org/10.1016/j.jnucmat.2021.152939	journal	July 2021
Irradiation stability and thermomechanical properties of 3D-printed SiC Terrani, K. A.; Lach, T.; Wang, H. Journal of Nuclear Materials, Vol. 551 https://doi.org/10.1016/j.jnucmat.2021.152980	journal	August 2021
Embedded sensors in additively manufactured silicon carbide Petrie, Christian M.; Schrell, Adrian M.; Leonard, Donovan N. Journal of Nuclear Materials, Vol. 552 https://doi.org/10.1016/j.jnucmat.2021.153012	journal	August 2021
Numerical investigation of the thermal conductivity of UO2 – Mo microplate fuel pellets to realize enhanced heat transfer in the fuel radial direction Lee, Heung Soo; Kim, Dong Seok; Kim, Dong-Joo Journal of Nuclear Materials, Vol. 554 https://doi.org/10.1016/j.jnucmat.2021.153075	journal	October 2021
High-burnup fuel stress analysis prior to and during a LOCA transient Capps, Nathan; Sweet, Ryan; Harp, Jason Journal of Nuclear Materials, Vol. 556 https://doi.org/10.1016/j.jnucmat.2021.153194	journal	December 2021
Modelling of thermal conductivity and melting behaviour of minor actinide-MOX fuels and assessment against experimental and molecular dynamics data Magni, A.; Luzzi, L.; Pizzocri, D. Journal of Nuclear Materials, Vol. 557 https://doi.org/10.1016/j.jnucmat.2021.153312	journal	December 2021
Characterization of radiation damage in 3D printed SiC Lach, Timothy G.; Le Coq, Annabelle G.; Linton, Kory D. Journal of Nuclear Materials, Vol. 559 https://doi.org/10.1016/j.jnucmat.2021.153459	journal	February 2022
Fully ceramic microencapsulated fuels fabricated by tape casting Liu, Chaohua; Huang, Rongxia; Tan, Jinhui Journal of Nuclear Materials, Vol. 564 https://doi.org/10.1016/j.jnucmat.2022.153675	journal	June 2022
Synthesis of U3O8 and UO2 microspheres using microfluidics Kurley, J. Matthew; Hunt, Rodney D.; McMurray, Jake W. Journal of Nuclear Materials, Vol. 566 https://doi.org/10.1016/j.jnucmat.2022.153784	journal	August 2022
Review of in-situ process monitoring and in-situ metrology for metal additive manufacturing Everton, Sarah K.; Hirsch, Matthias; Stravroulakis, Petros Materials & Design, Vol. 95 https://doi.org/10.1016/j.matdes.2016.01.099	journal	April 2016
Compressive properties of functionally graded lattice structures manufactured by selective laser melting Choy, Sing Ying; Sun, Chen-Nan; Leong, Kah Fai Materials & Design, Vol. 131 https://doi.org/10.1016/j.matdes.2017.06.006	journal	October 2017
Thermal design, optimization and additive manufacturing of ceramic regular structures to maximize the radiative heat transfer Pelanconi, M.; Barbato, M.; Zavattoni, S. Materials & Design, Vol. 163 https://doi.org/10.1016/j.matdes.2018.107539	journal	February 2019
A Critical Review on Recent Research Methodologies in Additive Manufacturing Srinivas, M.; Babu, B. Sridhar Materials Today: Proceedings, Vol. 4, Issue 8 https://doi.org/10.1016/j.matpr.2017.07.258	journal	January 2017
A scalable digital platform for the use of digital twins in additive manufacturing Scime, Luke; Singh, Alka; Paquit, Vincent Manufacturing Letters, Vol. 31 https://doi.org/10.1016/j.mfglet.2021.05.007	journal	January 2022
Additive manufacturing of functionally graded materials: A review Zhang, Chi; Chen, Fei; Huang, Zhifeng Materials Science and Engineering: A, Vol. 764 https://doi.org/10.1016/j.msea.2019.138209	journal	September 2019
Ceramic tape casting: A review of current methods and trends with emphasis on rheological behaviour and flow analysis Jabbari, M.; Bulatova, R.; Tok, A. I. Y. Materials Science and Engineering: B, Vol. 212 https://doi.org/10.1016/j.mseb.2016.07.011	journal	October 2016
Porous zinc scaffolds for bone tissue engineering applications: A novel additive manufacturing and casting approach Cockerill, Irsalan; Su, Yingchao; Sinha, Subhasis Materials Science and Engineering: C, Vol. 110 https://doi.org/10.1016/j.msec.2020.110738	journal	May 2020
Investigation of bounds on particle packing in pebble-bed high temperature reactors Ougouag, Abderrafi M.; Kloosterman, Jan Leen; van Rooijen, Wilfred F. G. Nuclear Engineering and Design, Vol. 236, Issue 5-6 https://doi.org/10.1016/j.nucengdes.2005.12.006	journal	March 2006
Development of the hot isostatic press manufacturing process for monolithic nuclear fuel Crapps, Justin; Clarke, Kester; Katz, Joel Nuclear Engineering and Design, Vol. 254 https://doi.org/10.1016/j.nucengdes.2012.09.002	journal	January 2013
Fabrication and characterization of driver-fuel particles, designed-to-fail fuel particles, and fuel compacts for the US AGR-3/4 irradiation test Hunn, John D.; Lowden, Richard A.; Miller, James H. Nuclear Engineering and Design, Vol. 271 https://doi.org/10.1016/j.nucengdes.2013.11.020	journal	May 2014
Modeling constituent redistribution in U–Pu–Zr metallic fuel using the advanced fuel performance code BISON Galloway, J.; Unal, C.; Carlson, N. Nuclear Engineering and Design, Vol. 286 https://doi.org/10.1016/j.nucengdes.2015.01.014	journal	May 2015
Evaluation of missing pellet surface geometry on cladding stress distribution and magnitude Capps, Nathan; Montgomery, Robert; Sunderland, Dion Nuclear Engineering and Design, Vol. 305 https://doi.org/10.1016/j.nucengdes.2016.04.039	journal	August 2016
A model to predict failure of irradiated U–Mo dispersion fuel Burkes, Douglas E.; Senor, David J.; Casella, Andrew M. Nuclear Engineering and Design, Vol. 310 https://doi.org/10.1016/j.nucengdes.2016.09.032	journal	December 2016
Modeling of Cr2O3-doped UO2 as a near-term accident tolerant fuel for LWRs using the BISON code Che, Yifeng; Pastore, Giovanni; Hales, Jason Nuclear Engineering and Design, Vol. 337 https://doi.org/10.1016/j.nucengdes.2018.07.015	journal	October 2018
Science-based nuclear design and safety in the emerging age of data based analytics Martin, R. P. Nuclear Engineering and Design, Vol. 354 https://doi.org/10.1016/j.nucengdes.2019.110155	journal	December 2019
Fuel performance evaluation of annular metallic fuels for an advanced fast reactor concept Miao, Yinbin; Stauff, Nicolas; Oaks, Aaron Nuclear Engineering and Design, Vol. 352 https://doi.org/10.1016/j.nucengdes.2019.110157	journal	October 2019
New method for analysis of X-ray computed tomography scans of TRISO fuel forms Helmreich, Grant W.; Hunn, John D.; Brown, Daniel R. Nuclear Engineering and Design, Vol. 357 https://doi.org/10.1016/j.nucengdes.2019.110418	journal	February 2020
Development and demonstration of a methodology to evaluate high burnup fuel susceptibility to pulverization under a loss of coolant transient Capps, Nathan; Sweet, Ryan; Wirth, Brian D. Nuclear Engineering and Design, Vol. 366 https://doi.org/10.1016/j.nucengdes.2020.110744	journal	September 2020
Transformational Challenge Reactor preconceptual core design studies Betzler, B. R.; Ade, B. J.; Wysocki, A. J. Nuclear Engineering and Design, Vol. 367 https://doi.org/10.1016/j.nucengdes.2020.110781	journal	October 2020
Integral LOCA fragmentation test on high-burnup fuel Capps, Nathan; Yan, Yong; Raftery, Alicia Nuclear Engineering and Design, Vol. 367 https://doi.org/10.1016/j.nucengdes.2020.110811	journal	October 2020
Additive manufacturing of aluminum nitride ceramics with high thermal conductivity via digital light processing Rauchenecker, Johannes; Rabitsch, Julia; Schwentenwein, Martin Open Ceramics, Vol. 9 https://doi.org/10.1016/j.oceram.2021.100215	journal	March 2022
Neutronics modeling and analysis of the TMSR-SF1 fuel lattice and full core with explicit fuel particle distribution and random pebble loadings Sun, Kaichao; Wilson, Jarod; Hauptman, Sara Progress in Nuclear Energy, Vol. 109 https://doi.org/10.1016/j.pnucene.2018.08.005	journal	November 2018
Assembly-level analyses of accident-tolerant cladding concepts for a long-life civil marine SMR core using micro-heterogeneous duplex fuel Alam, Syed Bahauddin; Goodwin, Cameron S.; Parks, Geoffrey T. Progress in Nuclear Energy, Vol. 111 https://doi.org/10.1016/j.pnucene.2018.10.011	journal	March 2019
A comparison of traditional manufacturing vs additive manufacturing, the best method for the job Pereira, Tanisha; Kennedy, John V.; Potgieter, Johan Procedia Manufacturing, Vol. 30 https://doi.org/10.1016/j.promfg.2019.02.003	journal	January 2019
The effect of soluble boron and gadolinium distribution on neutronic parameters of small modular reactor assembly Mustafa, Sayed Saeed; Amin, E. A. Radiation Physics and Chemistry, Vol. 171 https://doi.org/10.1016/j.radphyschem.2020.108724	journal	June 2020
The influence of impurities on the crystal structure and mechanical properties of additive manufactured U–14 at.% Nb Wu, Amanda S.; Brown, Donald W.; Clausen, Bjørn Scripta Materialia, Vol. 130 https://doi.org/10.1016/j.scriptamat.2016.11.010	journal	March 2017
Metal-embedded fiber optic sensor packaging and signal demodulation scheme towards high-frequency dynamic measurements in harsh environments Sweeney, Daniel C.; Schrell, Adrian M.; Liu, Yun Sensors and Actuators A: Physical, Vol. 312 https://doi.org/10.1016/j.sna.2020.112075	journal	September 2020
Evaluation of Tellurium as a Fuel Additive in Neodymium-Containing U-Zr Metallic Fuel Jerred, Nathan D.; Khanal, Rabi; Benson, Michael T. Scientific Reports, Vol. 9, Issue 1 https://doi.org/10.1038/s41598-019-51852-z	journal	November 2019
AI-based design of a nuclear reactor core Sobes, Vladimir; Hiscox, Briana; Popov, Emilian Scientific Reports, Vol. 11, Issue 1 https://doi.org/10.1038/s41598-021-98037-1	journal	October 2021
Fabrication of UN-Mo CERMET Nuclear Fuel Using Advanced Manufacturing Techniques Raftery, Alicia M.; Seibert, Rachel L.; Brown, Daniel R. Nuclear Technology https://doi.org/10.1080/00295450.2020.1823187	journal	December 2020
Thermal Conductivity of UO ₂ -BeO Pellet Ishimoto, Shinji; Hirai, Mutsumi; Ito, Kenichi Journal of Nuclear Science and Technology, Vol. 33, Issue 2 https://doi.org/10.1080/18811248.1996.9731875	journal	February 1996
Irradiation Behavior of Large Grain UO₂ Fuel Rod by Active Powder Harada, Yuhei; Doi, Soichi Journal of Nuclear Science and Technology, Vol. 35, Issue 6 https://doi.org/10.1080/18811248.1998.9733883	journal	June 1998
High-temperature strain monitoring of stainless steel using fiber optics embedded in ultrasonically consolidated nickel layers Petrie, Christian M.; Sridharan, Niyanth; Hehr, Adam Smart Materials and Structures, Vol. 28, Issue 8 https://doi.org/10.1088/1361-665X/ab2a27	journal	July 2019
A comprehensive review of ultrasonic additive manufacturing Hehr, Adam; Norfolk, Mark Rapid Prototyping Journal, Vol. 26, Issue 3 https://doi.org/10.1108/RPJ-03-2019-0056	journal	November 2019
Towards a sustainable and economic selection of part candidates for additive manufacturing Lindemann, Christian; Reiher, Thomas; Jahnke, Ulrich Rapid Prototyping Journal, Vol. 21, Issue 2 https://doi.org/10.1108/RPJ-12-2014-0179	journal	March 2015
Additive Manufacturing of Dense Alumina Ceramics Schwentenwein, Martin; Homa, Johannes International Journal of Applied Ceramic Technology, Vol. 12, Issue 1 https://doi.org/10.1111/ijac.12319	journal	September 2014
Mechanical Packing of Spherical Particles McGEARY, R. K. Journal of the American Ceramic Society, Vol. 44, Issue 10 https://doi.org/10.1111/j.1151-2916.1961.tb13716.x	journal	October 1961
Alumina and Alumina/Zirconia Multilayer Composites Obtained by Slip Casting Requena, Joaquin; Moreno, Rodrigo; Moya, Jose S. Journal of the American Ceramic Society, Vol. 72, Issue 8 https://doi.org/10.1111/j.1151-2916.1989.tb07692.x	journal	August 1989
An Evaluation of the Thermophysical Properties of Stoichiometric CeO ₂ in Comparison to UO ₂ and PuO ₂ Nelson, Andrew T.; Rittman, Dylan R.; White, Joshua T. Journal of the American Ceramic Society, Vol. 97, Issue 11 https://doi.org/10.1111/jace.13170	journal	August 2014
Additive Manufacturing of Ceramics: Issues, Potentialities, and Opportunities Zocca, Andrea; Colombo, Paolo; Gomes, Cynthia M. Journal of the American Ceramic Society, Vol. 98, Issue 7 https://doi.org/10.1111/jace.13700	journal	July 2015
Polymer‐derived silicon nitride ceramics by digital light processing based additive manufacturing Wang, Min; Xie, Chen; He, Rujie Journal of the American Ceramic Society, Vol. 102, Issue 9 https://doi.org/10.1111/jace.16389	journal	March 2019
Stereolithography‐based additive manufacturing of gray‐colored SiC ceramic green body Ding, Guojiao; He, Rujie; Zhang, Keqiang Journal of the American Ceramic Society, Vol. 102, Issue 12 https://doi.org/10.1111/jace.16648	journal	June 2019
3D printing of high‐purity silicon carbide Terrani, Kurt; Jolly, Brian; Trammell, Michael Journal of the American Ceramic Society, Vol. 103, Issue 3 https://doi.org/10.1111/jace.16888	journal	October 2019
Thorium: Not a near-term commercial nuclear fuel Nelson, Andrew T. Bulletin of the Atomic Scientists, Vol. 68, Issue 5 https://doi.org/10.1177/0096340212459125	journal	March 2012
Use of Thoria-Urania Fuels in PWRs: A General Review of a NERI Project to Assess Feasible Core Designs, Economics, Fabrication Methods, In-Pile Thermal/Mechanical Behavior, and Waste Form Characteristics MacDonald, Philip E.; Lee, Chan Bock Nuclear Technology, Vol. 147, Issue 1 https://doi.org/10.13182/NT04-A3510	journal	July 2004
Microheterogeneous Thoria-Urania Fuels for Pressurized Water Reactors Shwageraus, Eugene; Zhao, Xianfeng; Driscoll, Michael J. Nuclear Technology, Vol. 147, Issue 1 https://doi.org/10.13182/NT04-A3512	journal	July 2004
Use of Thorium for Transmutation of Plutonium and Minor Actinides in PWRs Shwageraus, Eugene; Hejzlar, Pavel; Kazimi, Mujid S. Nuclear Technology, Vol. 147, Issue 1 https://doi.org/10.13182/NT04-A3514	journal	July 2004
The Behavior of ThO₂-Based Fuel Rods during Normal Operation and Transient Events in LWRs Long, Yun; Siefken, Larry J.; Hejzlar, Pavel Nuclear Technology, Vol. 147, Issue 1 https://doi.org/10.13182/NT04-A3519	journal	July 2004
Production of High-Density Uranium Carbide Compacts for Use in Composite Nuclear Fuels Vasudevamurthy, Gokul; Knight, Travis W. Nuclear Technology, Vol. 163, Issue 2 https://doi.org/10.13182/NT08-A3991	journal	August 2008
Fabrication of Monolithic RERTR Fuels by Hot Isostatic Pressing Jue, Jan-Fong; Park, Blair H.; Clark, Curtis R. Nuclear Technology, Vol. 172, Issue 2 https://doi.org/10.13182/NT10-A10905	journal	November 2010
Production and Characterization of ZrC-UC Inert Matrix Composite Fuel for Gas Fast Reactors Vasudevamurthy, Gokul; Knight, Travis W.; Adams, Thad M. Nuclear Technology, Vol. 173, Issue 2 https://doi.org/10.13182/NT11-A11549	journal	February 2011
Lightbridge Corporation’s Advanced Metallic Fuel for Light Water Reactors Malone, James; Totemeier, Aaron; Shapiro, Norton Nuclear Technology, Vol. 180, Issue 3 https://doi.org/10.13182/NT12-A15354	journal	December 2012
Neutronics Studies of Uranium-Bearing Fully Ceramic Microencapsulated Fuel for Pressurized Water Reactors George, Nathan Michael; Maldonado, Ivan; Terrani, Kurt Nuclear Technology, Vol. 188, Issue 3 https://doi.org/10.13182/NT14-3	journal	December 2014
Use of Thorium in Light Water Reactors Todosow, Michael; Galperin, A.; Herring, S. Nuclear Technology, Vol. 151, Issue 2 https://doi.org/10.13182/NT151-168	journal	August 2005
Annular Fuel for High-Power-Density Pressurized Water Reactors: Motivation and Overview Hejzlar, Pavel; Kazimi, Mujid S. Nuclear Technology, Vol. 160, Issue 1 https://doi.org/10.13182/NT160-2-15	journal	October 2007
Effect of Pellet Cracking on Light Water Reactor Fuel Temperatures MacDonald, P. E.; Weisman, J. Nuclear Technology, Vol. 31, Issue 3 https://doi.org/10.13182/NT76-A31672	journal	December 1976
Development and Irradiation Performance of Uranium Aluminide Fuels in Test Reactors Beeston, J. M.; Hobbins, R. R.; Gibson, G. W. Nuclear Technology, Vol. 49, Issue 1 https://doi.org/10.13182/NT80-A32515	journal	June 1980
Preliminary Study of Cost Benefits Associated with Duplex Fuel Pellets of the LOWI Type Ainscough*, John Brian; Coucill, David Norman; Howl, David Anthony Nuclear Technology, Vol. 61, Issue 3 https://doi.org/10.13182/NT83-A33177	journal	June 1983
U-Si and U-Si-Ai Dispersion Fuel Alloy Development for Research and Test Reactors Domagala, R. F.; Wiencek, T. C.; Thresh, H. R. Nuclear Technology, Vol. 62, Issue 3 https://doi.org/10.13182/NT83-A33258	journal	September 1983
Boron-Nitride–Coated Nuclear Fuels Gündüz, Güngör; Uslu, İbrahım; Durmazuçar, Hasan H. Nuclear Technology, Vol. 116, Issue 1 https://doi.org/10.13182/NT96-A35313	journal	October 1996
Local Analysis Technique for the Advanced Neutron Source Reactor Fuel Defect Studies Giles, Gary E. Nuclear Technology, Vol. 117, Issue 3 https://doi.org/10.13182/NT97-A35345	journal	March 1997
Additive Manufacturing of Ti-Based Intermetallic Alloys: A Review and Conceptualization of a Next-Generation Machine Dzogbewu, Thywill Cephas; du Preez, Willie Bouwer Materials, Vol. 14, Issue 15 https://doi.org/10.3390/ma14154317	journal	August 2021
Additive Manufacturing as a Solution to Challenges Associated with Heat Pipe Production Szymanski, Pawel; Mikielewicz, Dariusz Materials, Vol. 15, Issue 4 https://doi.org/10.3390/ma15041609	journal	February 2022
Fabrication of U₃Si₂ Powder for Fuels Used in IEA-R1 Nuclear Research Reactor Saliba-Silva, Adonis M.; Durazzo, Michelangelo; de Carvalho, Elita F. Urano Materials Science Forum, Vol. 591-593 https://doi.org/10.4028/www.scientific.net/MSF.591-593.194	journal	August 2008
Development of High-Density u/al Dispersion Plates for Mo-99 Production Using Atomized Uranium Powder Ryu, Ho Jin; Kim, Chang Kyu; Sim, Moonsoo Nuclear Engineering and Technology, Vol. 45, Issue 7 https://doi.org/10.5516/NET.07.2013.014	journal	December 2013
IRRADIATION PERFORMANCE OF U-Mo MONOLITHIC FUEL Meyer, M. K.; Gan, J.; Jue, J. F. Nuclear Engineering and Technology, Vol. 46, Issue 2 https://doi.org/10.5516/NET.07.2014.706	journal	April 2014

Similar Records

Features that Further Performance Limits of Nuclear Fuel Fabrication: Opportunities for Additive Manufacturing of Nuclear Fuels

Technical Report · Wed May 01 00:00:00 EDT 2019 · OSTI ID:1669784

CONCEPTUAL PROCESS DESCRIPTION FOR THE MANUFACTURE OF LOW-ENRICHED URANIUM-MOLYBDENUM FUEL

Technical Report · Thu Jan 31 23:00:00 EST 2008 · OSTI ID:935449

Development of Thermal Tomography Imaging System for In-Service Nondestructive Evaluation of Additively Manufactured Components

Technical Report · Fri Aug 14 00:00:00 EDT 2020 · OSTI ID:1661878

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
accelerated qualification
additive manufacturing
nuclear fuel

Prospects for additive manufacturing of nuclear fuel forms

Citation Formats

References (169)

Similar Records

Related Subjects