JOPSS - Search Results

Search Results: Records 1-20 displayed on this page of 24

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Journal Articles

Effect of O/M ratio on sintering behavior of (Pu $_{0.3}$ U $_{0.7}$ )O $_{2-x}$

Nakamichi, Shinya; Hirooka, Shun; Kato, Masato; Sunaoshi, Takeo*; Nelson, A. T.*; McClellan, K. J.*

Journal of Nuclear Materials, 535, p.152188_1 - 152188_8, 2020/07

https://doi.org/10.1016/j.jnucmat.2020.152188

Times Cited Count：9 Percentile：75.92(Materials Science, Multidisciplinary)

Oxygen-to-metal ratio (O/M) of uranium and plutonium mixed oxide depends on its oxygen partial pressure. To attain the desirable microstructure and O/M ratio of sintered pellets, it is important to investigate the relation between the sintering behavior and the atmosphere of sintering process. In this study, sintering behavior of (Pu $_{0.3}$ U $_{0.7}$ )O $_{2}$ and (Pu $_{0.3}$ U $_{0.7}$ )O $_{1.99}$ in controlled po $_{2}$ atmosphere were investigated. It was found activation energy of (Pu $_{0.3}$ U $_{0.7}$ )O $_{1.99}$ was higher than that of (Pu $_{0.3}$ U $_{0.7}$ )O $_{2}$ . On the other hand, it was observed grain growth during sintering was suppressed in hypo-stoichiometric composition.

Journal Articles

Post-irradiation examinations of annular mixed oxide fuels with average burnup 4 and 5% FIMA

Cappia, F.*; Tanaka, Kosuke; Kato, Masato; McClellan, K.*; Harp, J.*

Journal of Nuclear Materials, 533, p.152076_1 - 152076_14, 2020/05

https://doi.org/10.1016/j.jnucmat.2020.152076

Times Cited Count：6 Percentile：60.71(Materials Science, Multidisciplinary)

Journal Articles

Thermal and mechanical properties of CeO $_{2}$

Suzuki, Kiichi; Kato, Masato; Sunaoshi, Takeo*; Uno, Hiroki*; Carvajal-Nunez, U.*; Nelson, A. T.*; McClellan, K. J.*

Journal of the American Ceramic Society, 102(4), p.1994 - 2008, 2019/04

https://doi.org/10.1111/jace.16055

Times Cited Count：36 Percentile：90.42(Materials Science, Ceramics)

The fundamental properties of CeO $_{2}$ were assessed using a range of experimental techniques. The oxygen potential of CeO $_{2}$ was measured by the thermogravimetric technique, and a numerical fit for the oxygen potential of CeO $_{2}$ is derived based on defect chemistry. Mechanical properties of CeO $_{2}$ were obtained using sound velocity measurement, resonant ultrasound spectroscopy and nanoindentation. The obtained mechanical properties of CeO $_{2}$ are then used to evaluate the Debye temperature and Gruneisen constant. The heat capacity and thermal conductivity of CeO $_{2}$ were also calculated using the Debye temperature and the Gruneisen constant. Finally, the thermal conductivity was calculated based upon laser flash analysis measurements. This result demonstrates that the thermal conductivity has strong dependence upon material purity.

Journal Articles

Thermal expansion measurement of (U,Pu)O $_{2-x}$ in oxygen partial pressure-controlled atmosphere

Kato, Masato; Ikusawa, Yoshihisa; Sunaoshi, Takeo*; Nelson, A. T.*; McClellan, K. J.*

Journal of Nuclear Materials, 469, p.223 - 227, 2016/02

https://doi.org/10.1016/j.jnucmat.2015.11.048

Times Cited Count：11 Percentile：71.62(Materials Science, Multidisciplinary)

Thermal expansion of (U $_{0.7}$ Pu $_{0.3}$ )O $_{2-x}$ (x = 0, 0.01, 0.02, 0.03) and (U $_{0.52}$ Pu $_{0.48}$ )O $_{2.00}$ was measured with a dilatometer in an oxygen partial pressure-controlled atmosphere. The oxygen partial pressure was controlled to hold a constant oxygen-to-metal ratio in the (U,Pu)O $_{2-x}$ during the measurement. Thermal expansion slightly increased with the decrease in oxygen-to-metal ratio. The relationship was derived to describe thermal expansion.

Journal Articles

Physical property model for advanced oxide fuels

Kato, Masato; McClellan, K.*

Transactions of the American Nuclear Society, 113(1), p.613 - 614, 2015/10

A joint study on advanced oxide fuels is being carried out under the Civil Nuclear Energy Working Group (CNWG) bilateral collaboration between the U.S. Department of Energy and the Japan Atomic Energy Agency. The main goal of this study is to support development and validation of a science-based fuel analysis code for minor actinide (MA) bearing MOX fuel. In analysis and evaluation of fuel performance, it is essential to understand the physical properties of the advanced oxide fuels. Therefore, we are investigating physical properties of (U,Pu)O $_{2}$ , (U,Ce,)O $_{2}$ , PuO $_{2}$ , CeO $_{2}$ and other related compounds to prepare a physical property database and to construct an integrated mechanistic physical property model. In this paper, we describe the derivation of a model to represent heat capacity and thermal conductivity of (U,Pu)O $_{2-x}$ that is based on the experimental database.

Journal Articles

Sintering behavior of (U,Ce)O $_{2}$ and (U,Pu)O $_{2}$

Nakamichi, Shinya; Hirooka, Shun; Sunaoshi, Takeo*; Kato, Masato; Nelson, A.*; McClellan, K.*

Transactions of the American Nuclear Society, 113(1), p.617 - 618, 2015/10

Cerium dioxide has been used as a surrogate material for plutonium dioxide. Dorr et al reported the use of hyper-stoichiometric conditions causes the start of shrinkage of (U,Ce)O $_{2}$ at low temperature compared with the sintering in reducing atmosphere. However, the precise stoichiometry of the samples investigated was not controlled or otherwise monitored, preventing any quantitative conclusions regarding the similarities or differences between (U,Ce)O $_{2}$ and (U,Pu)O $_{2}$ . The motivation for the present work is therefore to compare the sintering behavior of MOX and the (U,Ce)O $_{2}$ MOX surrogates under controlled atmospheres to assess the role of oxygen defects on densification in both systems.

Journal Articles

An Evaluation of the thermophysical properties of stoichiometric CeO $_{2}$ in comparison to UO $_{2}$ and PuO $_{2}$

Nelson, A. T.*; Rittman, D. R.*; White, J. T.*; Dunwoody, J. T.*; Kato, Masato; McClellan, K. J.*

Journal of the American Ceramic Society, 97(11), p.3652 - 3659, 2014/11

https://doi.org/10.1111/jace.13170

Times Cited Count：60 Percentile：93.26(Materials Science, Ceramics)

Journal Articles

Oxygen thermochemistry of urania-rare earth system; UO-CeO

Hirooka, Shun; Murakami, Tatsutoshi; Nelson, A. T.*; McClellan, K. J.*

INL/EXT-14-33515, p.34 - 36, 2014/10

https://doi.org/10.2172/1169217

Collaborative study has been done on the properties of nuclear materials between the DOE and Japan and the oxygen potential of (U,Ce)O was measured in this year. Experimental measurements of the oxygen potential were conducted on Ce=20% and 30% composition rates simulating Pu content in advanced MOX fuel in JAEA by gas equilibrium method where oxygen partial pressure in the atmosphere was controlled with mixing dry/wet Ar/H gas. More than 100 data points were obtained in the O/M range of 1.945 2.000 at 1200 $^{circ}$ C, 1400 $^{circ}$ C and 1600 $^{circ}$ C. The experimental results were analyzed by the defect analysis and analytical equations were obtained to calculate O/M as functions of temperature and oxygen potential. From the comparison with that of (U,Pu)O, applicability of the same defect chemistry and S-style curve are common. Also, it is revealed that (U,Ce)O requires evidently higher oxygen potential for the O/M.

Journal Articles

Property measurements of (U $_{0.7}$ ,Pu $_{0.3}$ )O $_{2-x}$ in $_{O2}$ -controlled atmosphere

Kato, Masato; Murakami, Tatsutoshi; Sunaoshi, Takeo*; Nelson, A. T.*; McClellan, K.*

Proceedings of International Nuclear Fuel Cycle Conference; Nuclear Energy at a Crossroads (GLOBAL 2013) (CD-ROM), p.852 - 856, 2013/09

Uranium and plutonium mixed oxide (U $_{0.7}$ ,Pu $_{0.3}$ )O $_{2-x}$ which has been developed as a fast reactor fuel is nonstoichiometric compound. The stoichiometry significantly affects various properties. The relationship between oxygen potential and oxygen-to-metal (O/M) ratio has been investigated so far. The measurement results showed that it is essential to control oxygen partial pressure ( $_{O2}$ ) for holding constant O/M ratio in high temperature range. Therefore, properties of (U $_{0.7}$ ,Pu $_{0.3}$ )O $_{2-x}$ were measured in $_{O2}$ -controlled atmosphere in this work. In this work, properties of O/M change, sintering and thermal expansion were investigated in $_{O2}$ -controlled atmosphere.

Journal Articles

Oxidation and reduction behaviors of plutonium and uranium mixed oxide powders

Hirooka, Shun; Kato, Masato; Tamura, Tetsuya*; Nelson, A. T.*; McClellan, K. J.*; Suzuki, Kiichi

Proceedings of International Conference on Fast Reactors and Related Fuel Cycles; Safe Technologies and Sustainable Scenarios (FR-13) (USB Flash Drive), 8 Pages, 2013/03

As research and development activities for MOX fuel pellet production, oxidation and reduction behaviors of MOX powders were investigated by thermogravimetry and X-ray diffraction measurements. It was observed that the oxidation limit decreased with oxidizing temperature and Pu content. The MOX powders showed a two-step oxidation and kinetic stability under non-stoichiometry. The oxidation rates were evaluated from the isothermal oxidation tests. It was found that the reduction temperature of M $_{4}$ O $_{9}$ + M $_{3}$ O $_{8}$ was higher than that of M $_{4}$ O $_{9}$ . This indicated that the reduction of M $_{4}$ O $_{9}$ was prevented by the existence of M $_{3}$ O $_{8}$ . Activation energy of the reduction was derived from the non-isothermal reduction tests. The data are expected to contribute to establishing a control technique for O/M ratio during MOX powder storage and pellet production.

Oral presentation

Oxidation behavior of UO $_{2}$ pellet at 673 - 1923 K

Suzuki, Kiichi; Sunaoshi, Takeo*; McClellan, K. J.*; Kato, Masato

no journal, ,

Oral presentation

Oxidation behavior of UO $_{2}$ in air

Suzuki, Kiichi; Nelson, A. T.*; Sunaoshi, Takeo*; McClellan, K.*; Kato, Masato

no journal, ,

In a reactor core or a spent fuel pool loss of coolant accident, fuel cladding may be breached and cause rapid oxidation of UO $_{2}$ pellets. Oxidation of UO $_{2}$ results in pulverization of the pellet and significant evaporation of UO $_{3}$ , possibly leading to spread of nuclear material to the environment. Therefore, understanding the oxidation behavior of UO $_{2}$ is an important factor. In this study, the oxidation behavior of UO $_{2}$ pellets and powders in air was investigated over a wide temperature range. Isothermal oxidations were carried out from 673 to 1923 K. Oxidative pulverization was observed below 1073 K. The weight gain rate at 773 K was larger than that at 873 K, suggesting the oxidation mechanism might change in this regime. Rapid weight loss was observed above 1723 K. The vapor pressure of each phase in the U-O system was calculated, indicating that volatilization of UO $_{3}$ was likely responsible for the measured weight loss. The evaporation rate of UO $_{3}$ for a urania pellet was then evaluated.

Oral presentation

Oxidation behaviors of UO $_{2}$ powder in water vapor

Suzuki, Kiichi; Kato, Masato; Nelson, A.*; McClellan, K.*

no journal, ,

no abstracts in English

Oral presentation

Thermal expansion measurement of (U,Pu)O $_{2-x}$ in oxygen partial pressure controlled atmosphere

Kato, Masato; Ikusawa, Yoshihisa; Sunaoshi, Takeo*; McClellan, K.*; Nelson, A.*

no journal, ,

Thermal expansion of MOX was measured as a function of O/M ratio. The measurements of the thermal expansion and O/M were carried out with dilatometer and thermo gravimeter, respectively, in cooling process of 4 K/min. Oxygen potential of MOX has been measured, and the correlation was derived to represent the relationship between oxygen potential and O/M ratio. The P $_{O2}$ in the atmosphere was controlled according to the previous data which were controlled by adjusting PH $_{2}$ /PH $_{2}$ O ratio. It was confirmed to hold constant O/M ratio during the measurements by thermo-gravimetry. Thermal expansion of (U $_{0.7}$ Pu $_{0.3}$ )O $_{2-x}$ increased with increasing the deviation x. The correlation to represent the thermal expansion was derived with Pu content and O/M ratio. The thermal expansion coefficients are consistent with those of PuO $_{2-x}$ .

Oral presentation

Oxygen potential measurement of (U,Ce)O $_{2}$

Murakami, Tatsutoshi; Kato, Masato; Nelson, A.*; McClellan, K.*

no journal, ,

no abstracts in English

Oral presentation

Thermal properties of (U,Ce)O $_{2pm x}$

Hirooka, Shun; Murakami, Tatsutoshi; Kato, Masato; Suzuki, Kiichi; Nelson, A.*; White, J.*; McClellan, K.*

no journal, ,

no abstracts in English

Oral presentation

Evaluation of (U,Ce)O $_{2}$ thermal conductivity

Hirooka, Shun; Kato, Masato; Nelson, A.*; McClellan, K.*; White, J.*

no journal, ,

Thermal diffusivity of (U,Ce)O $_{2}$ was measured as a function of O/M, and the thermal conductivity was calculated. Thermal conductivity of (U,Ce)O $_{2}$ decreased more sharply with increasing temperature compared with that of (U,Pu)O $_{2}$ . Also, thermal conductivity of (U,Ce)O $_{2}$ showed the highest peak at O/M of 2 and decreased as the O/M is apart from 2 on both hypo-stoichiometric and hyper-stoichimetric regions.

Oral presentation

Thermophyisical properties of (U,Ce)O $_{2pm x}$

White, J.*; Hirooka, Shun; Murakami, Tatsutoshi; Nelson, A.*; McClellan, K.*; Kato, Masato

no journal, ,

Use of CeO $_{2}$ as a surrogate to better understand the behavior of MOX fuels requires a fundamental investigation of the thermophysical properties to assess the appropriate use. The challenge in performing thermophysical property measurements on oxygen non-toichiometric MOX is in handling the kinetics at elevated temperatures and also in determining a reference state from which to measure the oxygen:metal ratio (O:M). This study integrated the use of identical gas handling systems installed on a thermogravimetric analyzer and the property measurement system (differential scanning calorimeter and laser flash analyzer) to control the partial pressure of oxygen, PO $_{2}$ , between the system and maintain stoichiometry from ambient temperature to 1200 $^{circ}$ C.

Oral presentation

Oxygen potential representation of (U,Ce)O $_{2 pm x}$

Suzuki, Kiichi; Murakami, Tatsutoshi; Hirooka, Shun; Nelson, A.*; McClellan, K.*; Kato, Masato

no journal, ,

The relationship between equilibrium oxygen partial pressure, $P_{rm O2}$ , and deviation from stoichiometric composition, x, was evaluated using a Kroger-Vink diagram. It was found that x was proportional to $P_{rm O2}$ $^{+1/2}$ and $P_{rm O2}$ $^{-1/2}$ near stoichiometry for all compositions. This suggests that intrinsic ionization is dominant near stoichiometry. Also, in the reducing region, x was proportional to $P_{rm O2}$ $^{-1/4}$ for 20 and 30% of Ce, and was proportional to $P_{rm O2}$ $^{-1/6}$ for 5% of Ce. Defect reactions and defect concentrations were evaluated by the relationship between x and $P_{rm O2}$ $^{1/n}$ . Then, the oxygen potential expression was derived using the defect concentrations as functions of O/M ratio, temperature and Ce content. The calculated values reproduced experimental values well.

Oral presentation

Thermal conductivity of uranium-cerium mixed oxide

Hirooka, Shun; Nelson, A.*; White, J.*; Kato, Masato; McClellan, K.*

no journal, ,

Thermal diffusivity of (U $_{0.7}$ Ce $_{0.3}$ )O $_{2}$ and (U $_{0.8}$ Ce $_{0.2}$ )O $_{2}$ was measured by laser flash method as a function of oxygen-to-metal ratio over the temperature range of 373 K to 1473 K and the thermal conductivity was evaluated. Only stoichiometric data of thermal conductivity of (U,Ce)O $_{2}$ was reported and that was comparable with thermal conductivity obtained in this work. Thermal conductivity was highest at stoichiometry, and was not perfectly symmetric with respect to the stoichiometry but slightly lower for hyper-stoichiometric compositions. The thermal conductivity of (U,Ce)O $_{2}$ showed the trend with temperature to be comparable to that of (U,Pu)O $_{2}$ . However, the thermal resistivity did not follow the linear function of temperature, A+BT, which is an unique characteristics in (U,Ce)O $_{2}$ .