Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 20
  • 1

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 ...

Save select records

Journal Articles

Selective recovery of thorium and uranium from leach solutions of rare earth concentrates in continuous solvent extraction mode with primary amine N1923

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:9 Percentile:83.6(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.

Journal Articles

Journal Articles

Oxidation kinetics of silicon carbide in steam at temperature range of 1400 to 1800$$^{circ}$$C studied by laser heating

Pham, V. H.; Nagae, Yuji; Kurata, Masaki; Bottomley, D.; Furumoto, Kenichiro*

Journal of Nuclear Materials, 529, p.151939_1 - 151939_8, 2020/02

AA2019-0197.pdf:1.61MB

 Times Cited Count:14 Percentile:86.19(Materials Science, Multidisciplinary)

Journal Articles

Oxidation of silicon carbide in steam studied by laser heating

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

Journal Articles

Steam oxidation of silicon carbide at temperatures above 1600$$^{circ}$$C

Pham, V. H.; Nagae, Yuji; Kurata, Masaki

Proceedings of Annual Topical Meeting on Reactor Fuel Performance (TopFuel 2018) (Internet), 6 Pages, 2018/10

Journal Articles

High temperature oxidation test of simulated BWR fuel bundle in steam-starved conditions

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$$_{2}$$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-H$$_{2}$$O/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.

Oral presentation

Interaction of zircaloy and molten mixture of stainless steel-B$$_{4}$$C at elevated temperatures

Pham, V. H.; Matsuura, Suguru*; Nanko, Makoto*; Nagae, Yuji; Kurata, Masaki

no journal, , 

Oral presentation

High-temperature interaction of silicon carbide with steam above 1600$$^{circ}$$C

Pham, V. H.; Nagae, Yuji; Kurata, Masaki

no journal, , 

Oral presentation

Recession of ZrO$$_{2}$$ scale on fuel tube cladding by the melt of control rod assemble

Nakajima, Shotaro*; Matsuura, Suguru*; Nanko, Makoto*; Kurata, Masaki; Pham, V. H.

no journal, , 

Oral presentation

Consideration for modeling of Zry oxidation and hydrogen uptake in steam-starved conditions

Yamazaki, Saishun; Pshenichnikov, A.; Pham, V. H.; Nagae, Yuji; Kurata, Masaki

no journal, , 

no abstracts in English

Oral presentation

Oral presentation

Behavior of ZrO$$_{2}$$ scale formed on zircaloy in steam starvation conditions

Nakajima, Shotaro*; Matsuura, Suguru*; Nanko, Makoto*; Kurata, Masaki; Pham, V. H.

no journal, , 

no abstracts in English

Oral presentation

Steam oxidation of silicon carbide at high temperature up to 1800$$^{circ}$$C

Pham, V. H.; Nagae, Yuji; Kurata, Masaki; Furumoto, Kenichiro*; Sato, Hisaki*; Ishibashi, Ryo*; Yamashita, Shinichiro

no journal, , 

Oral presentation

Development of laser heating facility for steam oxidation at extreme temperatures

Kurata, Masaki; Pham, V. H.; Nagae, Yuji

no journal, , 

Oral presentation

Oral presentation

ATF fundamental research at JAEA

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

Oral presentation

Development of SiC cladding for BWR application

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

Oral presentation

Study on coating technic to enhance accident tolerance of fuel cladding, 1; Overview of accident tolerant coating technic studies and apparatus development in JAEA

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.

Oral presentation

Study on coating technic to enhance accident tolerance of fuel cladding, 4; Oxidation behavior of the TiN/TiAlN multilayer coated Zry-4

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.

20 (Records 1-20 displayed on this page)
  • 1