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Nguyen, T. H.*; Le Ba, T.*; Tran, C. T.*; Nguyen, T. T.*; Doan, T. T. T.*; Do, V. K.; Watanabe, Masayuki; Pham, Q. M.*; Hoang, S. T.*; Nguyen, D. V.*; et al.
Hydrometallurgy, 213, p.105933_1 - 105933_11, 2022/08
Times Cited Count：15 Percentile：85.77(Metallurgy & Metallurgical Engineering)A continuous counter-current extraction for the selective recovery of thorium (Th) and uranium (U) from the Yen Phu (Vietnam) rare earth concentrate leach solutions was systematically studied. The primary amine N1923 was used as an extractant which was prepared in the isoparaffin IP-2028 diluent. Thorium and uranium were selectively recovered in a hydrometallurgical circuit established by continuous mixer-settler extraction, scrubbing, and back-extraction at the laboratory scale. The desired purity of Th and U can be achieved by managing the volume ratio of organic to aqueous phase (O/A ratio) in the corresponding steps. Highly pure Th and U were recovered from the pregnant back-extraction liquor and the raffinate, respectively, which have satisfactory properties for further processing of the subsequent nuclear materials.
Pham, V. H.; Kurata, Masaki; Steinbrueck, M.*
Thermo (Internet), 1(2), p.151 - 167, 2021/09
C studied by laser heatingPham, V. H.; Nagae, Yuji; Kurata, Masaki; Bottomley, D.; Furumoto, Kenichiro*
Journal of Nuclear Materials, 529, p.151939_1 - 151939_8, 2020/02
Times Cited Count：16 Percentile：85.51(Materials Science, Multidisciplinary)Pham, V. H.; Nagae, Yuji; Kurata, Masaki; Furumoto, Kenichiro*; Sato, Hisaki*; Ishibashi, Ryo*; Yamashita, Shinichiro
Proceedings of International Nuclear Fuel Cycle Conference / Light Water Reactor Fuel Performance Conference (Global/Top Fuel 2019) (USB Flash Drive), p.670 - 674, 2019/09
CPham, V. H.; Nagae, Yuji; Kurata, Masaki
Proceedings of Annual Topical Meeting on Reactor Fuel Performance (TopFuel 2018) (Internet), 6 Pages, 2018/10
Yamazaki, Saishun; Pshenichnikov, A.; Pham, V. H.; Nagae, Yuji; Kurata, Masaki; Tokushima, Kazuyuki*; Aomi, Masaki*; Sakamoto, Kan*
Proceedings of Annual Topical Meeting on Reactor Fuel Performance (TopFuel 2018) (Internet), 8 Pages, 2018/10
It is predictively evaluated that degradation of fuel assembly proceeded in a certain steam-starved condition at the early stage of a SA at 1F unit 2 (BWR). As for PWR fuel assembly, effective steam flow rate was properly indicated by normalizing to a unit of g-H
O/sec/rod which is used as an important parameter for evaluating fuel degradation progression. Due to the inhomogeneous configuration of BWR fuel assembly, the difference of Zry oxidation and hydrogen uptake between the inside and outside of the channel box cannot be properly evaluated by this normalization. Instead of g-HO/sec/rod, proper evaluation unit for BWR configuration is necessary. To accumulate Zry oxidation and hydrogen uptake data for steam-starved conditions, high temperature oxidation tests were performed using a simulated BWR fuel bundle sample. The use of equivalent diameter of the cross section of BWR fuel assembly was proposed for normalization of effective steam flow rate.
CPham, V. H.; Nagae, Yuji; Kurata, Masaki; Furumoto, Kenichiro*; Sato, Hisaki*; Ishibashi, Ryo*; Yamashita, Shinichiro
no journal, ,
Kurata, Masaki; Pham, V. H.; Nagae, Yuji
no journal, ,
Pham, V. H.; Nagae, Yuji; Kurata, Masaki; Ishibashi, Ryo*; Yamashita, Shinichiro
no journal, ,
C under different steam flow ratePham, V. H.; Nagae, Yuji; Kurata, Masaki; Ishibashi, Ryo*
no journal, ,
Mohamad, A. B.; Nemoto, Yoshiyuki; Soma, Yasutaka; Ishijima, Yasuhiro; Sato, Tomonori; Ioka, Ikuo; Pham, V. H.; Miwa, Shuhei; Nakajima, Kunihisa; Kaji, Yoshiyuki; et al.
no journal, ,
no abstracts in English
Ishibashi, Ryo*; Hirosaka, Kazuma*; Ikegawa, Tomohiko*; Shibata, Masatoshi*; Sasaki, Masana*; Tsuchiya, Akiyuki*; Pham, V. H.; Kurata, Masaki; Nemoto, Yoshiyuki
no journal, ,
no abstracts in English
Yamashita, Shinichiro; Mohamad, A. B.; Nemoto, Yoshiyuki; Soma, Yasutaka; Ishijima, Yasuhiro; Sato, Tomonori; Ioka, Ikuo; Pham, V. H.; Miwa, Shuhei; Nakajima, Kunihisa; et al.
no journal, ,
JAEA is conducting research on various coating technologies for fuel cladding tubes aimed at improving accident resistance. In the lecture, we will introduce new equipment development at JAEA aimed at using these studies in addition to an overview of the entire project.
Pham, V. H.; Nemoto, Yoshiyuki; Yamashita, Shinichiro
no journal, ,
As part of an effort to improve accident resistance, a multilayer coating of TiN/TiAlN was applied to the surface of zirconium plate. In this study, oxidation tests were conducted on these specimens in high-temperature steam, and cross-sectional observations were made after the tests. In the lecture, we will introduce the results of these experiments as well as other coating technologies that we plan to develop.
Pshenichnikov, A.; Zubekhina, B.; Ogi, Hiroshi; Pham, V. H.
no journal, ,
Pham, V. H.; Nemoto, Yoshiyuki; Yamashita, Shinichiro
no journal, ,
Mohamad, A. B.; Nemoto, Yoshiyuki; Soma, Yasutaka; Ishijima, Yasuhiro; Sato, Tomonori; Ioka, Ikuo; Pham, V. H.; Miwa, Shuhei; Nakajima, Kunihisa; Kaji, Yoshiyuki; et al.
no journal, ,
JAEA is promoting the characterization of various coating tubes as part of fundamental research that contributes to the practical application of coated fuel cladding aiming at improving accident tolerance. In this presentation, overall outline, the new test equipment under construction, and highlight results of the vapor oxidation characteristic evaluation test for coated claddings will be presented.
C at elevated temperaturesPham, V. H.; Matsuura, Suguru*; Nanko, Makoto*; Nagae, Yuji; Kurata, Masaki
no journal, ,
Pham, V. H.; Ishibashi, Ryo*; Sasaki, Masana*; Nemoto, Yoshiyuki; Yamashita, Shinichiro
no journal, ,
Silicon carbide is the most prominent candidate for accident tolerant fuel cladding in terms of oxidation resistance and cladding integrity at high temperatures in steam. However, dilution of silica from SiC in aqueous environment under long-term corrosion can become a concern when considering SiC as nuclear graded materials. In order to improve its corrosion resistance in water for normal operations, coating of Ti layer on SiC was proposed. In this study, oxidation behavior and oxidation kinetics of Ti-coated SiC are studied via a thermogravimetric system at 1200-1500C. Influence of the Ti coating layer on oxidation kinetics and behavior of SiC will then be discussed and reported.
CPham, V. H.; Nagae, Yuji; Kurata, Masaki
no journal, ,
