Neptunium mononitride as a target material for Pu-238 production

Peruski, Kathryn M.

doi:10.3389/fnuen.2022.1044657

Neptunium mononitride as a target material for Pu-238 production

Journal Article · Sun Nov 06 23:00:00 EST 2022 · Frontiers in Nuclear Engineering

DOI:https://doi.org/10.3389/fnuen.2022.1044657· OSTI ID:1905390

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

Deep space exploration requires specialized sources for both thermal and power applications. Radioactive decay heat of plutonium-238 (238Pu) provides these sources in the form of radioisotope thermoelectric generators (RTGs). The ²³⁸Pu is produced via neutron capture reaction involving neptunium-237 (²³⁷Np) target material. Continual optimization of ₂₃₇Np target materials and evaluation of potential alternative targets for production of ²³⁸Pu RTGs are advantageous for meeting ongoing space power system resource requirements. Current production of ²³⁸Pu for RTGs for the United States space program utilizes neptunium dioxide (²³⁷NpO₂) targets; however, the use of neptunium mononitride (²³⁷NpN) presents an opportunity to increase the mass of ²³⁷Np per target compared to the dioxide form, as well as increase the thermal conductivity of the target. To assess the viability of a ²³⁷NpN target material, the material chemistry must be thoroughly evaluated, including synthesis methods and dissolution and reprocessing schemes. This review presents a summary of synthesis pathways for ²³⁷NpN based on published literature on actinide mononitrides. Specific literature on ²³⁷NpN is limited, necessitating evaluation of other actinide systems to gather parallels. This suggests a need for additional experimental studies on ²³⁷NpN. A particular limitation in the existing literature is a lack of information on the differences in material characteristics, such as morphology, particle size, and trace chemical impurities, as a function of synthesis method. These parameters may affect subsequent reactor performance or dissolution of irradiated targets. The evaluation of existing literature is presented with a focus on the efficacy of ²³⁷NpN targets for ²³⁸Pu production.

View Accepted Manuscript (DOE)

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

Sponsoring Organization:: USDOE Office of Science (SC), Nuclear Physics (NP); National Aeronautics and Space Administration (NASA)

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1905390

Journal Information:: Frontiers in Nuclear Engineering, Journal Name: Frontiers in Nuclear Engineering Vol. 1; ISSN 2813-3412

Publisher:: Frontiers Media S.A.Copyright Statement

Country of Publication:: United States

Language:: English

References (51)

A study of nitrogen oxides released into the gas phase during uranium nitride dissolution in nitric acid Kulyukhin, S. A.; Shadrin, A. Yu.; Voskresenskaya, Y. A. Journal of Radioanalytical and Nuclear Chemistry, Vol. 304, Issue 1 https://doi.org/10.1007/s10967-014-3693-x	journal	November 2014
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
Digestion and trace metal analysis of uranium nitride Campbell, Keri; Judge, Elizabeth Journal of Radioanalytical and Nuclear Chemistry, Vol. 331, Issue 1 https://doi.org/10.1007/s10967-021-08104-0	journal	December 2021
European Radioisotope Thermoelectric Generators (RTGs) and Radioisotope Heater Units (RHUs) for Space Science and Exploration Ambrosi, Richard M.; Williams, Hugo; Watkinson, Emily Jane Space Science Reviews, Vol. 215, Issue 8 https://doi.org/10.1007/s11214-019-0623-9	journal	December 2019
Fabrication and testing of uranium nitride fuel for space power reactors Matthews, R. B.; Chidester, K. M.; Hoth, C. W. Journal of Nuclear Materials, Vol. 151, Issue 3 https://doi.org/10.1016/0022-3115(88)90029-3	journal	February 1988
Investigation of the reaction UO2+x + PuO2 + C + N2 by thermogravimetry Pautasso, G.; Richter, K.; Sari, C. Journal of Nuclear Materials, Vol. 158 https://doi.org/10.1016/0022-3115(88)90148-1	journal	August 1988
Mechanism and kinetics of the uranium-plutonium mononitride synthesis Bardelle, Philippe; Warin, Dominique Journal of Nuclear Materials, Vol. 188 https://doi.org/10.1016/0022-3115(92)90451-p	journal	June 1992
The effect of oxygen impurity on the characteristics of uranium and uranium-plutonium mixed nitride fuels Arai, Yasuo; Morihira, Masayuki; Ohmichi, Toshihiko Journal of Nuclear Materials, Vol. 202, Issue 1-2 https://doi.org/10.1016/0022-3115(93)90030-3	journal	June 1993
Properties and thermal decomposition of the double salts of uranyl nitrate-ammonium nitrate Notz, Karl J.; Haas, Paul A. Thermochimica Acta, Vol. 155 https://doi.org/10.1016/0040-6031(89)87154-0	journal	December 1989
Thermodynamic and Thermophysical Properties of the Actinide Nitrides Uno, Masayoshi; Nishi, Tsuyoshi; Takano, Masahide Comprehensive Nuclear Materials, Vol. 7, p. 202-231 https://doi.org/10.1016/b978-0-12-803581-8.11749-7	book	August 2020
Advanced thermal denitration conversion processes for aqueous-based reprocessing and recycling of spent nuclear fuels Collins, Emory D. Reprocessing and Recycling of Spent Nuclear Fuel https://doi.org/10.1016/b978-1-78242-212-9.00012-5	book	January 2015
Thermal conductivity of perspective fuel based on uranium nitride Solntceva, E. S.; Taubin, M. L.; Vybyvanets, V. I. Annals of Nuclear Energy, Vol. 87 https://doi.org/10.1016/j.anucene.2014.08.011	journal	January 2016
Preparation of UC0.07−0.10N0.90−0.93 spheres for TRISO coated fuel particles Hunt, R. D.; Silva, C. M.; Lindemer, T. B. Journal of Nuclear Materials, Vol. 448, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.04.007	journal	May 2014
First principles study of structural, electronic, mechanical and magnetic properties of actinide nitrides AnN (An = U, Np and Pu) Murugan, A.; Priyanga, G. Sudha; Rajeswarapalanichamy, R. Journal of Nuclear Materials, Vol. 478 https://doi.org/10.1016/j.jnucmat.2016.06.016	journal	September 2016
Steam oxidation of uranium mononitride in pure and reducing steam atmospheres to 1200 °C Sooby, Elizabeth S.; Brigham, Brian A.; Robles, Geronimo Journal of Nuclear Materials, Vol. 560 https://doi.org/10.1016/j.jnucmat.2021.153487	journal	March 2022
Electrochemical behaviors of PuN and (U, Pu)N in LiCl–KCl eutectic melts Shirai, O.; Kato, T.; Iwai, T. Journal of Physics and Chemistry of Solids, Vol. 66, Issue 2-4 https://doi.org/10.1016/j.jpcs.2004.06.040	journal	February 2005
Dissolution Performance of Plutonium Nitride Based Fuel Materials Aneheim, Emma; Hedberg, Marcus Procedia Chemistry, Vol. 21 https://doi.org/10.1016/j.proche.2016.10.033	journal	January 2016
Carbothermic synthesis of (Cm,Pu)N Takano, Masahide; Itoh, Akinori; Akabori, Mitsuo Journal of Nuclear Materials, Vol. 294, Issue 1-2 https://doi.org/10.1016/s0022-3115(01)00463-9	journal	April 2001
Fabrication of nitride fuels for transmutation of minor actinides Minato, Kazuo; Akabori, Mitsuo; Takano, Masahide Journal of Nuclear Materials, Vol. 320, Issue 1-2 https://doi.org/10.1016/s0022-3115(03)00163-6	journal	July 2003
Thermodynamics of carbothermic synthesis of actinide mononitrides Ogawa, Toru; Shirasu, Yoshiro; Minato, Kazuo Journal of Nuclear Materials, Vol. 247 https://doi.org/10.1016/s0022-3115(97)00041-x	journal	August 1997
XPS and XRD studies of corrosion of uranium nitride by water Sunder, S.; Miller, N. H. Journal of Alloys and Compounds, Vol. 271-273 https://doi.org/10.1016/s0925-8388(98)00157-1	journal	June 1998
Thermal conductivity of actinide mononitride solid solutions Arai, Yasuo; Nakajima, Kunihisa; Suzuki, Yasufumi Journal of Alloys and Compounds, Vol. 271-273 https://doi.org/10.1016/s0925-8388(98)00168-6	journal	June 1998
Effects of H₂O₂ Concentration on Formation of Uranyl Peroxide Species Probed by Dissolution of Uranium Nitride and Uranium Dioxide Hickam, Sarah; Breier, Jaclyn; Cripe, Yasmeen Inorganic Chemistry, Vol. 58, Issue 9 https://doi.org/10.1021/acs.inorgchem.9b00231	journal	April 2019
Microscopic Characterization of Uranium Nitrides Synthesized by Oxidative Ammonolysis of Uranium Tetrafluoride Silva, G. W. Chinthaka; Yeamans, Charles B.; Ma, Longzhou Chemistry of Materials, Vol. 20, Issue 9 https://doi.org/10.1021/cm7033646	journal	April 2008
Production of Neptunium Dioxide Porter, J. A. Industrial & Engineering Chemistry Process Design and Development, Vol. 3, Issue 4 https://doi.org/10.1021/i260012a001	journal	October 1964
Fabrication of Targets for Neutron Irradiation of Neptunium Dioxide Myrick, R. E.; Folger, R. L. Industrial & Engineering Chemistry Process Design and Development, Vol. 3, Issue 4 https://doi.org/10.1021/i260012a006	journal	October 1964
Reaction Sequence and Kinetics of Uranium Nitride Decomposition Silva, G. W. Chinthaka; Yeamans, Charles B.; Sattelberger, Alfred P. Inorganic Chemistry, Vol. 48, Issue 22 https://doi.org/10.1021/ic901165j	journal	October 2009
The Melting Point and Decomposition Pressure of Neptunium Mononitride Olson, W. M.; Mulford, R. N. R. The Journal of Physical Chemistry, Vol. 70, Issue 9 https://doi.org/10.1021/j100881a035	journal	September 1966
New Neptunium Compounds Sheft, Irving; Fried, Sherman Journal of the American Chemical Society, Vol. 75, Issue 5 https://doi.org/10.1021/ja01101a067	journal	March 1953
Crystal and Electronic Structures of Neptunium Nitrides Synthesized Using a Fluoride Route Silva, G. W. Chinthaka; Weck, Philippe F.; Kim, Eunja Journal of the American Chemical Society, Vol. 134, Issue 6 https://doi.org/10.1021/ja209503n	journal	February 2012
The preparation and properties of some plutonium compounds. Part II. Plutonium nitride Brown, F.; Ockenden, Heather M.; Welch, G. A. Journal of the Chemical Society (Resumed) https://doi.org/10.1039/jr9550004196	journal	January 1955
New techniques for high-temperature melting measurements in volatile refractory materials via laser surface heating Manara, D.; Sheindlin, M.; Heinz, W. Review of Scientific Instruments, Vol. 79, Issue 11 https://doi.org/10.1063/1.3005994	journal	November 2008
Dissolution of uranium nitrides in LiCl-KCl eutectic melt Hayashi, Hirokazw; Kobayashi, Fumiaki; Ogawa, Toru Journal of Nuclear Science and Technology, Vol. 39, Issue sup3 https://doi.org/10.1080/00223131.2002.10875545	journal	November 2002
Uranium nitride fuels in superheated steam Jolkkonen, Mikael; Malkki, Pertti; Johnson, Kyle Journal of Nuclear Science and Technology, Vol. 54, Issue 5 https://doi.org/10.1080/00223131.2017.1291372	journal	February 2017
Plutonium-238 Production Program Results, Implications, and Projections from Irradiation and Examination of Initial NpO₂ Test Targets for Improved Production Collins, Emory D.; Morris, Robert N.; McDuffee, Joel L. Nuclear Technology, Vol. 208, Issue sup1 https://doi.org/10.1080/00295450.2021.2021769	journal	April 2022
Reaction between Plutonium Dioxide and Graphite Yahata, Taneaki; Ouchi, Kinji Journal of Nuclear Science and Technology, Vol. 12, Issue 2 https://doi.org/10.1080/18811248.1975.9733077	journal	February 1975
Carbothermic Synthesis of High Purity Plutonium Nitride from Plutonium Oxide Muromura, Tadasumi Journal of Nuclear Science and Technology, Vol. 19, Issue 8 https://doi.org/10.1080/18811248.1982.9734194	journal	August 1982
Fabrication of Uranium-Plutonium Mixed Nitride Fuel Pins for Irradiation Tests in JMTR Arai, Yasuo; Suzuki, Yasufumi; Iwai, Takashi Journal of Nuclear Science and Technology, Vol. 30, Issue 8 https://doi.org/10.1080/18811248.1993.9734553	journal	August 1993
Preparation of Neptunium Mononitride by Carbothermic Reduction Suzuki, Yasufumi; Arai, Yasuo; Okamoto, Yoshihiro Journal of Nuclear Science and Technology, Vol. 31, Issue 7 https://doi.org/10.1080/18811248.1994.9735209	journal	July 1994
Recovery of Neptunium by Electrolysis of NpN in LiCl-KCl Eutectic Melts Shirai, Osamu; Iizuka, Masatoshi; Iwai, Takashi Journal of Nuclear Science and Technology, Vol. 37, Issue 8 https://doi.org/10.1080/18811248.2000.9714943	journal	August 2000
Crystal chemical studies of the 5f-series of elements. XII. New compounds representing known structure types Zachariasen, W. H. Acta Crystallographica, Vol. 2, Issue 6 https://doi.org/10.1107/s0365110x49001016	journal	December 1949
Fabrication of ThN Using a Carbothermic Reduction to Nitridation Process Parkison, Adam J.; Parker, Stephen S.; Nelson, Andrew T. Journal of the American Ceramic Society, Vol. 99, Issue 12 https://doi.org/10.1111/jace.14453	journal	September 2016
Dissolution of a Mixture of Uranium and Plutonium Compounds Fedorov, M. S.; Zhiganov, A. N.; Zozulya, D. V. Radiochemistry, Vol. 63, Issue 3 https://doi.org/10.1134/s1066362221030061	journal	June 2021
Electrochemical Behavior of Np in the Molten LiCl–KCl Eutectic De Córdoba, G.; Laplace, A.; Lacquement, J. Journal of The Electrochemical Society, Vol. 154, Issue 1 https://doi.org/10.1149/1.2388871	journal	January 2007
Solubility and hydrolysis of tetravalent actinides Neck, Volker; Kim, J. I. Radiochimica Acta, Vol. 89, Issue 1 https://doi.org/10.1524/ract.2001.89.1.001	journal	January 2001
Oak Ridge National Laboratory Preparation of Sintered ²³⁷NpO₂ Pellets for Irradiation to Produce ²³⁸Pu Oxide Vedder, Raymond https://doi.org/10.2172/1484146	report	November 2018
Carbothermic Synthesis of a Mixed Uranium-Plutonium Nitride Greenhalgh, W. O.; Weber, E. T. https://doi.org/10.2172/4842584	report	January 1968
Nuclear Material Processing at the Savannah River Site Severynse, T. F. https://doi.org/10.2172/664584	report	July 1998
Direct thermal denitration to prepare mixed oxides for nuclear fuel fabrication Mailen, J. C.; Pruett, D. J.; McTaggart, D. R. https://doi.org/10.2172/707069	report	June 1982
Characterization of Neptunium Oxide Generated Using the HB-Line Phase II Flowsheet Duffey, J. https://doi.org/10.2172/890149	report	August 2003
Lab Scale Production of NpO2 Duffey, J. https://doi.org/10.2172/890151	report	August 2003

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Neptunium mononitride as a target material for Pu-238 production

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