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JAEA Reports

Fuel debris criticality analysis technology using non-contact measurement method (Contract research); FY2022 Nuclear Energy Science & Technology and Human Resource Development Project

Collaborative Laboratories for Advanced Decommissioning Science; Tokyo Institute of Technology*

JAEA-Review 2024-013, 48 Pages, 2024/07

JAEA-Review-2024-013.pdf:1.99MB

The Collaborative Laboratories for Advanced Decommissioning Science (CLADS), Japan Atomic Energy Agency (JAEA), had been conducting the Nuclear Energy Science & Technology and Human Resource Development Project (hereafter referred to "the Project") in FY2022. The Project aims to contribute to solving problems in the nuclear energy field represented by the decommissioning of the Fukushima Daiichi Nuclear Power Station, Tokyo Electric Power Company Holdings, Inc. (TEPCO). For this purpose, intelligence was collected from all over the world, and basic research and human resource development were promoted by closely integrating/collaborating knowledge and experiences in various fields beyond the barrier of conventional organizations and research fields. The sponsor of the Project was moved from the Ministry of Education, Culture, Sports, Science and Technology to JAEA since the newly adopted proposals in FY2018. On this occasion, JAEA constructed a new research system where JAEA-academia collaboration is reinforced and medium-to-long term research/development and human resource development contributing to the decommissioning are stably and consecutively implemented. Among the adopted proposals in FY2021, this report summarizes the research results of the "Fuel debris criticality analysis technology using non-contact measurement method" conducted in FY2022. The purpose of research was to improve the fuel debris criticality analysis technology using non-contact measurement method by the development of the fuel debris criticality characteristics measurement system and the multi-region integral kinetic analysis code. It was performed by Tokyo Institute of Technology, National Institute of Advanced Industrial Science and Technology, and Nagaoka University of Technology as the second year of three years research project.

Journal Articles

Relationship between the contact angle of pure Cu and its alloys owing to liquid Na and electronic states at the interface

Saito, Junichi; Monbernier, M.*

Surfaces and Interfaces (Internet), 41, p.103248_1 - 103248_8, 2023/10

 Times Cited Count:5 Percentile:56.18(Chemistry, Physical)

JAEA Reports

Introduce of friction model into fuel pin bundle deformation analysis code "BAMBOO"

Uwaba, Tomoyuki; Ito, Masahiro*; Ishitani, Ikuo*

JAEA-Technology 2023-006, 36 Pages, 2023/05

JAEA-Technology-2023-006.pdf:3.45MB

The BAMBOO code developed by the Japan Atomic Energy Agency is a computer code to analyze fuel pin bundle deformation in a fast reactor wire-spaced type fuel pin bundle subassembly. In this study we developed an analysis model to consider friction at the contact points between adjacent fuel pins, and at these between outermost fuel pins and a duct that are due to bundle-duct interaction. This model deals with friction forces at contact points in the contact and separation analysis of the code, and employs a convergent calculation where contact forces are gradually determined to avoid numerical instability when the friction occurs. Analyses of BAMBOO with the model showed very slight effects on the onset of contact between outer most pins and a duct, and on directions of pin displacements, within the range of practical friction coefficients.

JAEA Reports

Fuel debris criticality analysis technology using non-contact measurement method (Contract research); FY2021 Nuclear Energy Science & Technology and Human Resource Development Project

Collaborative Laboratories for Advanced Decommissioning Science; Tokyo Institute of Technology*

JAEA-Review 2022-043, 52 Pages, 2023/01

JAEA-Review-2022-043.pdf:3.48MB

The Collaborative Laboratories for Advanced Decommissioning Science (CLADS), Japan Atomic Energy Agency (JAEA), had been conducting the Nuclear Energy Science & Technology and Human Resource Development Project (hereafter referred to "the Project") in FY2021. The Project aims to contribute to solving problems in the nuclear energy field represented by the decommissioning of the Fukushima Daiichi Nuclear Power Station, Tokyo Electric Power Company Holdings, Inc. (TEPCO). For this purpose, intelligence was collected from all over the world, and basic research and human resource development were promoted by closely integrating/collaborating knowledge and experiences in various fields beyond the barrier of conventional organizations and research fields. The sponsor of the Project was moved from the Ministry of Education, Culture, Sports, Science and Technology to JAEA since the newly adopted proposals in FY2018. On this occasion, JAEA constructed a new research system where JAEA-academia collaboration is reinforced and medium-to-long term research/development and human resource development contributing to the decommissioning are stably and consecutively implemented. Among the adopted proposals in FY2021, this report summarizes the research results of the "Fuel debris criticality analysis technology using non-contact measurement method" conducted in FY2021. The purpose of research was to improve the fuel debris criticality analysis technology using non-contact measurement method by the development of the fuel debris criticality characteristics measurement system and the multi-region integral kinetic analysis code. It was performed by Tokyo Institute of Technology (Tokyo Tech), National Institute of Advanced Industrial Science and Technology (AIST), and National Research Nuclear University (MEPhI) as the first year of four years research project. For the criticality characteristic measurement systems to be developed by the Japanese and Russian sides, …

JAEA Reports

Countercurrent extraction/stripping experiments using TDdDGA solvent extractant in a centrifugal contactor system,2; Evaluation on the improved flowsheet for MA recovery

Kibe, Satoshi; Fujisaku, Kazuhiko*; Sakamoto, Atsushi; Sano, Yuichi; Takeuchi, Masayuki; Suzuki, Hideya; Tsubata, Yasuhiro; Matsumura, Tatsuro

JAEA-Research 2016-024, 40 Pages, 2017/02

JAEA-Research-2016-024.pdf:6.73MB

The Japan Atomic Energy Agency has been developing some flowsheets with TDdDGA (N,N,N,Ntetradodecyldiglycolamide) extractant to recover MA (minor actinide) from raffinate. In this study, countercurrent experiments with the improved flowsheet, e.g. the addition of alcohol into the solvent for preventing the precipitation, were performed using miniature centrifugal contactors in order to compare the extraction/stripping behavior of each element with the mixer-settler type. As a result, no entrainments were observed and sufficient phase separation was achieved by centrifugal contactors without any abnormal fluid behavior, such as overflow. The extraction and stripping of Ln(III) which show the similar tendencies as MA could be achieved successfully, especially their stripping proceeded more efficiently in centrifugal contactors. This might be due to the increase in stripping rates by improving the flowsheet and to superior phase separation performance of centrifugal contactors.

JAEA Reports

Countercurrent extraction/stripping experiments using TDdDGA solvent extractant in a centrifugal contactors system

Kibe, Satoshi; Fujisaku, Kazuhiko*; Ambai, Hiromu; Sakamoto, Atsushi; Sano, Yuichi; Takeuchi, Masayuki; Suzuki, Hideya; Tsubata, Yasuhiro; Matsumura, Tatsuro

JAEA-Research 2015-021, 40 Pages, 2016/02

JAEA-Research-2015-021.pdf:2.3MB

The flowsheet with TDdDGA extractant has been being developed for recovering MA from PUREX raffinate. In the previous study, the yields of MA and other elements in countercurrent extraction/stripping experiments using mixer-settlers were not enough for the target and it would be due to the insufficient phase (aqueous/organic) separation. In this study, we carried out countercurrent experiments with surrogate PUREX raffinate using centrifugal contactors which had superior phase separation ability, and evaluated the extraction/stripping behavior of each element. During the operation, abnormal fluid behavior, such as overflow and entrainment, was not observed, and sufficient phase separation was achieved by centrifugal contactors. Extraction behavior of lanthanides was similar to that in mixer-settlers, but their stripping efficiencies decreased. This would be due to shorter residence time in mixing zone.

Journal Articles

High-efficiency contact grating fabricated on the basis of a Fabry-Perot type resonator for terahertz wave generation

Yoshida, Fumiko; Nagashima, Keisuke; Tsubouchi, Masaaki; Ochi, Yoshihiro; Maruyama, Momoko; Sugiyama, Akira

Japanese Journal of Applied Physics, 55(1), p.012201_1 - 012201_5, 2016/01

 Times Cited Count:7 Percentile:30.36(Physics, Applied)

Journal Articles

Conversion of hydrophilic surface of poly(ethylene terephthalate) film surface to hydrophobic one under hydrophilic condition

Suzuki, Yasuyuki*; Li, J.; Maekawa, Yasunari; Yoshida, Masaru; Maeyama, Katsuya*; Yonezawa, Noriyuki*

Nihon Kagakkai-Shi, 2002(2), p.255 - 259, 2002/02

The hydrophilic surface of poly(ethylene terephthalate) (PET) film, obtained by partial hydrolysis, was converted to hydrophobic one under dry air, saturated water vapor atmosphere, nitrogen, and vacuum at temperatures ranging from 0 to 80$$^{circ}$$C. The hydrophilicity of the surface increased significantly faster under the saturated water vapor although it was the most hydrophilic in the examined conditions. From the dependence of the absolute temperature on the rate of hydrophilicity change for each storage condition, a discontinuous point at ca. 50$$^{circ}$$C was observable only under the water vapor condition. This relation indicates that the appreciable acceleration of the hydrophilicity change on the surface under the hydrophilic condition might be resulted from the increase of the surface mobility due to the water adsorption on the PET surface.

Journal Articles

Application of neutron radiography to visualization of direct contact heat exchange between water and low melting point alloy

Nishi, Yoshihisa*; ; Furuya, Masahiro*; ; Matsubayashi, Masahito; Tsuruno, Akira

Fifth World Conf. on Neutron Radiography, 0, p.548 - 555, 1996/00

no abstracts in English

Journal Articles

Evaluation of structural integrity on cylindrical graphite component with spherical contact

Ishihara, Masahiro; Iyoku, Tatsuo; Futakawa, Masatoshi

Zairyo, 42(472), p.15 - 21, 1993/01

no abstracts in English

Journal Articles

Simulation code SAFE for analyzing transient solvent extraction behavior

Maeda, Mitsuru; Fujine, Sachio; ;

Transactions of the American Nuclear Society, 66, p.78 - 80, 1992/11

no abstracts in English

Journal Articles

Hydrodynamic characteristics of a single stage annular type centrifugal extractor

Fujine, Sachio; M.Kluth*; J.Lamla*; H.Goldacker*

Proc. of the Symp. on Solvent Extraction 1989, p.141 - 146, 1989/00

no abstracts in English

Journal Articles

Oscillatory flows induced by direct contact condensation of flowing steam with injected water

; ; ; ;

Journal of Nuclear Science and Technology, 22(4), p.269 - 283, 1985/00

 Times Cited Count:5 Percentile:59.28(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Analysis of direct contact condensation of flowing steam onto injected water with a multifluid model of two-phase flow

; Kozawa, Yoshiyuki*; ;

Journal of Nuclear Science and Technology, 20(12), p.1006 - 1022, 1983/00

 Times Cited Count:8 Percentile:67.94(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

FREC-4A : A Computer Program to Predict Fuel Rod Performance under Normal Reactor Operation

Harayama, Yasuo;

JAERI-M 9683, 140 Pages, 1981/10

JAERI-M-9683.pdf:3.19MB

no abstracts in English

JAEA Reports

Contact Pressure Between Pellet and Cladding Tube in Axi-symmetric Two-dimensional Problems

Harayama, Yasuo; ; ;

JAERI-M 8107, 21 Pages, 1979/03

JAERI-M-8107.pdf:0.7MB

no abstracts in English

Journal Articles

Journal Articles

Isotope separation by multiple contact, 2; Analytical procedure for frontal process

;

Journal of Nuclear Science and Technology, 4(11), p.570 - 577, 1967/00

 Times Cited Count:2

no abstracts in English

Journal Articles

Heat transfer between metallic surfaces in contact

Sanokawa, Konomo

Bull.Japan Soc.Precision Engng., 1(4), p.300 - 305, 1966/00

no abstracts in English

24 (Records 1-20 displayed on this page)