Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 38

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

Anisotropic thermal lattice expansion and crystallographic structure of strontium aluminide within Al-10Sr alloy as measured by in-situ neutron diffraction

Liss, K.-D.*; Harjo, S.; Kawasaki, Takuro; Aizawa, Kazuya; Xu, P. G.

Journal of Alloys and Compounds, 869, p.159232_1 - 159232_9, 2021/07

 Times Cited Count:0 Percentile:0(Chemistry, Physical)

Journal Articles

Effect of oxidizing metallic ions on corrosion of stainless steel during concentration process simulating High-level Activity Liquid Waste (HALW) concentrator

Irisawa, Eriko; Kato, Chiaki; Kamoshida, Michio*; Hakamatsuka, Yasuyuki*; Ueno, Fumiyoshi; Yamamoto, Masahiro

Proceedings of European Corrosion Congress 2017 (EUROCORR 2017) and 20th ICC & Process Safety Congress 2017 (USB Flash Drive), 9 Pages, 2017/09

Journal Articles

Effect of nitrous ion on oxidation of oxidizing-metallic ion in nitric acid solution

Irisawa, Eriko; Seki, Masaharu*; Ueno, Fumiyoshi; Kato, Chiaki; Motooka, Takafumi; Abe, Hitoshi

Proceedings of 21st International Conference & Exhibition; Nuclear Fuel Cycle for a Low-Carbon Future (GLOBAL 2015) (USB Flash Drive), p.1108 - 1112, 2015/09

Journal Articles

Influence of heating method on size and morphology of metallic oxide powder synthesized from metallic nitrate solution

Segawa, Tomomi; Fukasawa, Tomonori*; Yamada, Yoshikazu; Suzuki, Masahiro; Yoshida, Hideto*; Fukui, Kunihiro*

Proceedings of Asian Pacific Confederation of Chemical Engineering 2015 (APCChE 2015), 8 Pages, 2015/09

A mixed solution of uranyl nitrate and plutonium nitrate is converted to MOX raw powder by the microwave heating de-nitration method in nuclear reprocessing. Copper oxide synthesized by heating de-nitration was used as a model for the de-nitration process. The microwave heating method (MW) and infrared heating method (IR) were used, and how they and their heating rate influence the obtained particle morphology and size were investigated. The particles obtained by the MW and IR were sufficiently similar in the surface morphology and the mass median diameter was decreased by the increased heating rate. The mass median diameters by the MW were the heating rate and smaller than those obtained by IR. The particle size distribution of the particle obtained by the MW was broader than that by the IR. The relationship of the temperature distribution and particle size distribution by the MW was discussed by the numerical simulation.

Journal Articles

Influence of seawater-component on corrosion of steel in nitric acid solution containing vanadium and ruthenium

Irisawa, Eriko; Ueno, Fumiyoshi; Uchida, Naoki; Taguchi, Katsuya

Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 3 Pages, 2015/05

Journal Articles

Diffusion of tritium in intermetallic compound $$beta$$-LiAl; Relation to the defect structure

Sugai, Hiroyuki

Solid State Ionics, 177(39-40), p.3507 - 3512, 2007/01

The diffusion coefficient and its activation energy (116.3 $$pm$$ 11.7 kJ/mol) of tritium in an intermetallic compound $$beta$$-LiAl are determined at temperatures from 700 to 848 K. Though the present result for the diffusion coefficient is almost the same as that reported previously, the present result for the activation energy turns out nearly twice of that (64.9 $$pm$$ 3.8 kJ/mol). The present result for the activation energy is consistent with the systematics that an increase of lithium concentration in Al-Li systems increases the activation energy, but the previous result is not. Furthermore, a consideration of the crystal structure and defect structure suggests that tritium diffuses and is impeded by the attractive interaction with lithium atom at lithium sublattices.

Journal Articles

Diffusion of tritium in intermetallic compound $$beta$$-LiAl; Relation to the defect structure

Sugai, Hiroyuki

Solid State Ionics, 177(39-40), p.3507 - 3512, 2007/01

 Times Cited Count:3 Percentile:18.97(Chemistry, Physical)

The diffusion coefficients and its activation energy (103.7$$pm$$9.5 kJ/mol) for tritium in intermetallic compound $$beta$$-LiAl are determined at temperatures from 699 to 886 K. Though the present result for the diffusion coefficient is almost the same as that reported earlier, the activation energy turns out nearly twice of that (64.9$$pm$$3.8 kJ/mol) reported earlier. On the basis of the crystal structure and defect structure, the large activation energy of this study suggest that tritium diffuses interstitially and is impeded by an attractive interaction with lithium atoms in lithium sublattices.

Journal Articles

Vaporization behaviour of Pu-Cd intermetallic compounds

Nakajima, Kunihisa; Nakazono, Yoshihisa; Arai, Yasuo

Recent Advances in Actinide Science, p.448 - 450, 2006/06

A pyrochemical process for the metallurgical treatment of the spent nuclear fuels contains the Cd-distillation step, where Pu is recovered as a residue. For understanding this Cd-ditillation behavior the samples of PuCd$$_{2}$$+PuCd$$_{4}$$ and PuCd$$_{4}$$+PuCd$$_{6}$$ were prepared and Knudsen-cell mass-spectrometric measurements were carried out to determine the vapour pressures of Cd(g) over these samples. Further,the thermodynamic quantities of PuCd$$_{2}$$ and PuCd$$_{4}$$ were evaluated from these vapour pressures.

Journal Articles

Rapid dissolution techniques with microwave heating devices for solidified products made from non-metallic wastes by plasma melting

Haraga, Tomoko; Kameo, Yutaka; Nakashima, Mikio

Bunseki Kagaku, 55(1), p.51 - 54, 2006/01

 Times Cited Count:4 Percentile:15.3(Chemistry, Analytical)

A relatively large quantity of sample solutions have to be prepared for radiochemical analysis of solidified products yielded by plasma melting treatment of non-metallic radioactive wastes. In order to dissolve the solidified products sample rapidly, dissolution method with microwave heating devices was applied. In a conventional method only by external heating with various mixtures of acids (HNO$$_{3}$$, HF, HClO$$_{4}$$ and H$$_{2}$$SO$$_{4}$$), a 0.1 g amount of the sample was dissolved with difficulty. However, applying the microwave assisted dissolution method, a 1 g amount of the sample was completely dissolved in a shorter time. Thereby the time for dissolution procedures was shortened less than a one-tenth. The present dissolution method was successfully applied to the blast furnace slag as a reference material to determine main elements with good precision.

Journal Articles

Positron lifetime measurement on centrifuged Bi$$_{3}$$Pb$$_{7}$$ intermetallic compound

Ono, Masao; Huang, X. S.*; Shibata, Yasuhiro*; Iguchi, Yusuke*; Sakai, Seiji; Maekawa, Masaki; Chen, Z. Q.*; Osakabe, Toyotaka; Kawasuso, Atsuo; Naramoto, Hiroshi*; et al.

Proceedings of 1st International Conference on Diffusion in Solids and Liquids (DSL 2005), p.531 - 533, 2005/07

Recently, we formed atomic-scale graded structures in some miscible alloys and observed the decomposition in Bi$$_{3}$$Pb$$_{7}$$ intermetallic compound by sedimentation of atoms under strong gravitational field. In this study, we measured positron lifetime of centrifuged Bi$$_{3}$$Pb$$_{7}$$, to which the composition change was very small as it was treated at low temperature. It was found that the positron lifetime became longer than that of starting state. This indicated that the point defects (vacancy or divacancy) increased in the sample by centrifugal treatment. We are now investigating the relationship between increase in point defects and sedimentation of atoms.

Journal Articles

Numerical analysis of fractional distillation characteristics for radioactive metallic waste vaporized in the shape of atomic beam

Akaoka, Katsuaki; Maruyama, Yoichiro

Nihon Genshiryoku Gakkai Wabun Rombunshi, 4(2), p.127 - 134, 2005/06

The fractional distillation characteristics of the materials used for the reactor pressure vessel made of ASTM A302B and the structures in reactor made of SUS304 which are the radioactive metallic waste of Japan Power Demonstration Reactor (JPDR) were analyzed numerically. In the simulation, the vaporization rates of the components of the waste were calculated by using the Langmuir's equation and Henry's law. As the result of simulation, it was calculated that $$^{152}$$Eu, $$^{154}$$Eu, $$^{14}$$C and $$^{94}$$Nb can be reduced to less than clearance level by the fractional distillation. On the ASTM A302B case, it was pointed out that the other radioactive nuclei which are $$^{54}$$Mn, $$^{55}$$Fe, $$^{60}$$Co, $$^{59}$$Ni and $$^{63}$$Ni satisfy clearance level after 77 years cooling down. On the SUS304 case, it was pointed out that $$^{59}$$Ni and $$^{63}$$Ni must be separated to satisfy clearance level using isotope separation.

Journal Articles

Numerical analysis of fractional distillation for radioactive metal

Akaoka, Katsuaki; Maruyama, Yoichiro

RIST News, (39), p.23 - 31, 2005/03

For the separation of radionuclide from the radioactive metallic waste generated by the decommissioning of nuclear facilities, a new method combined with the distillation and laser separation is being studied. The characteristics of fractional distillation for duralumin were analyzed numerically using the Henry's law and the Langmuir's equation, and its result agreed well with the experiment. Next, the fractional distillation characteristics of the materials used for the structures in reactor made of SUS304 which are the radioactive metallic waste of Japan Power Demonstration Reactor (JPDR) were analyzed numerically. As the result of the simulation, it was calculated that the radioactive metallic waste will be reduced to less than 1/100.

Journal Articles

Sedimentation of substitutional solute atoms in intermetallic compound of Bi-Pb system under ultra-strong gravitational field

Ono, Masao; Huang, X.*; Kinoshita, Takahiro*; Ueno, Hideto*; Osakabe, Toyotaka; Mashimo, Tsutomu

Defect and Diffusion Forum, 237-240(2), p.1101 - 1104, 2005/00

Ultra-strong gravitational field can induce sedimentation of even atoms in condensed matter. We had realized sedimentation of substitutional solute atoms in some miscible alloys. How about in the other alloys? So, In this study, the ultra-centrifuge experiments were performed on an intermetallic compound of Bi-Pb system (Bi$$_{3}$$Pb$$_{7}$$) by changing time duration of experiment time (experimental conditions; maximum centrifugal force: 1.0$$times$$10$$^{6}$$g level, temperature: 130-150 $$^{circ}$$C, duration: 30-150h, state: solid). Composition changes were observed in the centrifuged samples. And, it was found that the Bi phase appeared from starting state of Bi$$_{3}$$Pb$$_{7}$$ around the weak gravitational field region of the sample. These results showed that sedimentation of substitutional solute atoms occurred, and induced the structure change in intermetallic compounds.

JAEA Reports

Numerical analysis of fractional distillation characteristics for radioactive metallic waste

Akaoka, Katsuaki; Maruyama, Yoichiro

JAERI-Research 2004-012, 12 Pages, 2004/08

JAERI-Research-2004-012.pdf:3.52MB

The fractional distillation characteristics at between 0 $$^{circ}$$C and 2500 $$^{circ}$$C(the rate is 200 $$^{circ}$$C/h) of radioactive metallic waste for JPDR which mainly consists of stainless steel were analyzed numerically. In the simulation, the vaporization rates of the components of JPDR waste were calculated by using the Langmuir's equation and Henry's law. As the results, it was calculated that $$^{152,154}$$Eu, $$^{14}$$C and $$^{94}$$Nb can be removed by the fractional distillation. On the other hand, $$^{54}$$Mn and $$^{55}$$Fe can be reduced by cooling them for about 30 years. Therefore, by removing $$^{59,63}$$Ni and $$^{60}$$Co using laser separation method, it will be possible to reduce the radioactive metallic waste by less than one one-hundredth.

Journal Articles

Heat transfer characteristics of the steam reformer in the HTTR hydrogen production system

Takeda, Tetsuaki

Proceedings of 12th International Conference on Nuclear Engineering (ICONE-12) (CD-ROM), 4 Pages, 2004/00

no abstracts in English

Journal Articles

Phonon density of states in Sr$$_{2}$$FeCoO$$_{6-delta}$$ and SrBaFeCoO$$_{6-delta}$$; Effects induced by magnetic order and transport coherence

Rykov, A. I.*; Nomura, Kiyoshi*; Sawada, Tsuguo*; Mitsui, Takaya; Seto, Makoto*; Tamegai, Tsuyoshi*; Tokunaga, Masashi*

Physical Review B, 68(22), p.224401_1 - 224401_7, 2003/12

 Times Cited Count:8 Percentile:44.11(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Electro-deposition of tantalum on tungsten and nickel in LiF-NaF-CaF$$_{2}$$ melt containing K$$_{2}$$TaF$$_{7}$$; Electrochemical study

Mehmood, M.*; Kawaguchi, Nobuaki*; Maekawa, Hideki*; Sato, Yuzuru*; Yamamura, Tsutomu*; Kawai, Masayoshi*; Kikuchi, Kenji

Materials Transactions, 44(2), p.259 - 267, 2003/02

 Times Cited Count:6 Percentile:44.83(Materials Science, Multidisciplinary)

Electrochemical study has been carried out on the electro-deposition of tantalum in LiF-NaF-CaF$$_{2}$$ melt containing K$$_{2}$$TaF$$_{7}$$ at 700$$^{circ}$$C. This has been done for determining the mechanistic features for preparing electrolytic coating of tantalum on nickel and tungsten substrates. Electro-deposition of metallic tantalum occurs primarily by electro-reduction of Ta(V). Pure metallic tantalum without any entrapped salt is successfully deposited on tungsten by galvanostatic polarization at reasonably low current densities. An additional feature on nickel is the formation of an intermetallic compound at potential 0.25V nobler than that of pure tantalum as a result of underpotential deposition of tantalum. This intermetallic compound covers the surface within a short time followed by deposition of pure tantalum, although intermetallic compound keeps growing at the interface of pure tantalum deposit and the substrate as a result of diffusion.

Journal Articles

Distribution behavior of plutonium and americium in LiCl-KCl eutectic/liquid cadmium systems

Sakamura, Yoshiharu*; Shirai, Osamu; Iwai, Takashi; Suzuki, Yasufumi

Journal of Alloys and Compounds, 321(1), p.76 - 83, 2001/05

 Times Cited Count:53 Percentile:89.97(Chemistry, Physical)

no abstracts in English

Journal Articles

Status report on the JAERI AVF cyclotron system

Nakamura, Yoshiteru; Nara, Takayuki; Agematsu, Takashi; Ishibori, Ikuo; Tamura, Hiroyuki; Kurashima, Satoshi; Yokota, Wataru; Okumura, Susumu; Fukuda, Mitsuhiro; Arakawa, Kazuo

AIP Conference Proceedings 600, p.129 - 132, 2001/00

The AVF cyclotron system at JAERI Takasaki has been smoothly operated without serious troubles since the first beam extraction of 50 MeV 4He2+ in March 1991. A yearly operation time is about 3200 hours on an average for past several years. In last three years, we performed some improvements and developments as followings: stabilization of the cyclotron beam, renewal of the control computers and basic programs, installation of a new ECR ion source and reconstruction of the rotary shutter. Furthermore, cocktail beams of series M/Q=4 and M/Q=2 have been developed continuously. Now we are modifying the RF cavity for the flat-top acceleration by the addition of 5th harmonic frequency.

Journal Articles

Irradiation behavior of microspheres of U-Zr alloys

Ogawa, Toru; *; Ito, Akinori; ; Sekino, Hajime; Nishi, Masahiro; Ishikawa, Akiyoshi; Akabori, Mitsuo

Journal of Alloys and Compounds, 271-273, p.670 - 675, 1998/00

 Times Cited Count:7 Percentile:51.14(Chemistry, Physical)

no abstracts in English

38 (Records 1-20 displayed on this page)