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Journal Articles

Space radiation dosimetry to evaluate the effect of polyethylene shielding in the Russian segment of the International Space Station

Nagamatsu, Aiko*; Casolino, M.*; Larsson, O.*; Ito, Tsuyoshi*; Yasuda, Nakahiro*; Kitajo, Keiichi*; Shimada, Ken*; Takeda, Kazuo*; Tsuda, Shuichi; Sato, Tatsuhiko

Physics Procedia, 80, p.25 - 35, 2015/12

 Times Cited Count:12 Percentile:95.25(Physics, Applied)

JAXA has been investigated the effect of the shielding material for dosimeters in the ISS Russian segment under the ALTCRISS project. The PADLES package is a passive dosimeters which usually consists of two types of passive and integrating dosimeters, a CR-39 plastic nuclear track detector and a thermoluminescence dosimeter. In the ALTCRISS experiments, both tissue-equivalent material CR-39 PNTDs and NAN-JAERI were enclosed in the PADLES packages as radiators for CR-39 to precisely measure a personal exposed doses. We compared the doses obtained by PADLESs with or without the PEs, and with or difference of the two tissue-equivalent materials. The results of space radiation measurements of the ALTCRISS project Phase 1 to 4 using the PADLES system will be reported in this time: Phase 1 experiments was from December 2005 to April 2006, Phase 2 was from April to September 2006, phase 3 was from Sep 2006 to April 2007, and Phase 4 was conducted from May to October 2007.

Journal Articles

Andreev bound states and tunneling characteristics of a noncentrosymmetric superconductor

Iniotakis, C.*; Hayashi, Nobuhiko; Sawa, Yasuo*; Yokoyama, Takehito*; May, U.*; Tanaka, Yukio*; Sigrist, M.*

Physical Review B, 76(1), p.012501_1 - 012501_4, 2007/07

 Times Cited Count:87 Percentile:92.35(Materials Science, Multidisciplinary)

The tunneling characteristics of planar junctions between a normal metal and a noncentrosymmetric superconductor such as CePt$$_3$$Si are examined. It is shown that the superconducting phase with mixed parity can give rise to characteristic zero-bias anomalies in certain junction directions. Andreev bound states at the interface are the origin of these zero-bias anomalies. The tunneling characteristics for different directions allow us to test the structure of the parity-mixed pairing state.

Journal Articles

Properties of TNF-1 track etch detector

Ogura, K.*; Asano, Masaharu; Yasuda, Nakahiro*; Yoshida, Masaru

Nuclear Instruments and Methods in Physics Research B, 185(1-4), p.222 - 227, 2001/12

 Times Cited Count:32 Percentile:89(Instruments & Instrumentation)

no abstracts in English

JAEA Reports

None

*; *; *; *

JNC TJ8400 99-054, 72 Pages, 1999/03

JNC-TJ8400-99-054.pdf:4.98MB

None

JAEA Reports

None

Tanaka, Masahiro*; *

JNC TJ7420 99-012, 49 Pages, 1999/03

JNC-TJ7420-99-012.pdf:1.64MB

no abstracts in English

JAEA Reports

Measurement of secondary stress around excavation by the stress release method

Itamoto, Masaharu*; Tanaka, Masahiro*; Tanno, Takeo*

PNC TJ7592 98-001, 166 Pages, 1998/03

PNC-TJ7592-98-001.pdf:8.43MB

None

JAEA Reports

None

Itamoto, Masaharu*; *; Tanaka, Masahiro*

PNC TJ7592 96-001, 164 Pages, 1996/03

PNC-TJ7592-96-001.pdf:9.73MB

no abstracts in English

Journal Articles

High-melt-strength polypropylene with electron beam irradiation in the presence of polyfunctional monomers

Yoshii, Fumio; Makuuchi, Keizo; *; *; *; *

Journal of Applied Polymer Science, 60, p.617 - 623, 1996/00

no abstracts in English

JAEA Reports

Estimation of critical mass of burned-up fuel

Komuro, Yuichi; Naito, Yoshitaka; Kurosawa, Masayoshi; *; *

JAERI-M 94-018, 32 Pages, 1994/03

JAERI-M-94-018.pdf:0.95MB

no abstracts in English

Oral presentation

Development of manufacturing technology for a large amount of $$^{99m}$$Tc generated from natural-Mo(n,$$gamma$$)$$^{99}$$Mo, 4; Analysis in the verification test of the producing process of $$^{99m}$$Tc milked from a highly radioactive $$^{99}$$Mo

Sonoda, Takashi; Umeda, Miki; Tagami, Susumu; Kurobane, Shiro; Miyoshi, Yoshinori; Tanaka, Atsushi*; Ishikawa, Koji*; Tsuguchi, Akira*; Tatenuma, Katsuyoshi*

no journal, , 

no abstracts in English

Oral presentation

Precise measurements of projectile charge changing cross sections for intermediate energy heavy ions

Chiba, Satoshi; Ota, Shuya*; Yasuda, Nakahiro*; Sihver, L.*; Kodaira, Satoshi*; Ideguchi, Yusuke*; Hasebe, Nobuyuki*

no journal, , 

no abstracts in English

Oral presentation

Precise measurements of projectile charge changing cross sections for intermediate energy heavy ions

Ota, Shuya*; Yasuda, Nakahiro*; Sihver, L.*; Kodaira, Satoshi*; Ideguchi, Yusuke*; Hasebe, Nobuyuki*

no journal, , 

Projectile charge-changing cross sections for nuclei in galactic cosmic rays (GCRs) on hydrogen play essentially important roles for the study of origin and source composition of GCRs. Previous experimental and theoretical works done so far made much progress on those cross sections. However, there are still uncertainties in much of the cross section data, and therefore the present knowledge of cross sections has not led to successful determination of the GCR source composition. To improve the uncertainties, a novel measurement system of projectile charge-changing cross section using CR-39 plastic nuclear track detectors with excellent position and nuclear charge resolutions has been developed. We carried out measurements of total and partial charge-changing cross sections for Fe and Mg on $$C$$ and $$CH_2$$ targets at 0.1 to 1 GeV/n using the method.

Oral presentation

Application of CR-39 plastic nuclear track detectors for quality assurance of MOX fuel pellet

Kodaira, Satoshi*; Yasuda, Nakahiro*; Hosogane, Tatsuya; Ishikawa, Fumitaka; Kageyama, Tomio; Sato, Mitsuhiro

no journal, , 

The plutonium-thermal use is expected as one of the approach for reuse of spent uranium fuel in nuclear power generation. On the other hand, many kinds of nuclides including Pu with extremely long half-lives are generated in the used fuels, which would be problems for storage and control of radioactive waste. The MOX (Mixed Oxide) consisting of plutonium dioxide enriched with 4-9% Pu and uranium oxide from spent uranium fuel would allow to reduce half-lives of radioactive waste significantly through the nuclear fission. The quality of MOX pellet depends on the homogeneous dispersion of Pu. The region of highly concentrated Pu is sometimes observed as "Pu spot" in the pellet, which has the potential of anomalous combustion localized at that region. The detection of Pu spot and evaluation of its size and concentration are one of the important quality assurance of MOX pellet for the safety use in the nuclear power plant. We have applied CR-39 plastic nuclear track detectors for the measurement of Pu spot inside MOX pellet. CR-39 can image a cross-section of MOX pellet by recording $$alpha$$-particle tracks from Pu in the pellet, like autoradiography. The Pu spot is visibly imaged as a "black spot" due to the dense $$alpha$$ tracks compared to homogeneously dispersed region. Conventionally, the Pu spot measurement has been carried out with manual scanning, which takes much longer times and huge amount of human work. We have developed the automatic detection and measurement system of Pu spot recorded on CR-39 by the image processing with filtering and clustering algorithms. The detection efficiency with CR-39 is achieved to be almost 100% compared with conventional manual scanning result. It provides more information about the number, size and position of Pu spot.

Oral presentation

Feasibility study for visualization of radioactive material distribution in Fukushima nuclear reactor based on OSL technology

Nanda, N.*; Usami, Hiroshi; Morishita, Yuki; Sugita, Takeshi*; Torii, Tatsuo; Yasuda, Nakahiro*

no journal, , 

Oral presentation

Examination of stabilization treatment method of radioactive aluminum waste

Seki, Misaki; Ishikawa, Koji*; Nagata, Hiroshi; Otsuka, Kaoru; Omori, Takazumi; Suzuki, Yumi*; Tanaka, Atsushi*; Kawakami, Tomohiko*; Ide, Hiroshi; Tsuchiya, Kunihiko

no journal, , 

no abstracts in English

Oral presentation

Development of neutron source imaging technology using CR-39 solid-state track detector

Kato, Shingo; Ishizuka, Akihiro; Okuyama, Shinichi; Nozaki, Tatsuo; Hayashi, Gaku*; Yasuda, Nakahiro*; Torii, Tatsuo*; Ando, Takasuke*

no journal, , 

no abstracts in English

Oral presentation

Development of neutron source imaging technology using CR-39 detector for decommissioning of nuclear power plants

Hayashi, Gaku*; Torii, Tatsuo*; Ishizuka, Akihiro; Okuyama, Shinichi; Kato, Shingo; Nozaki, Tatsuo; Yasuda, Nakahiro*

no journal, , 

no abstracts in English

Patent

放射性アルミニウム廃棄物処理方法

関 美沙紀; 井手 広史; 永田 寛; 大塚 薫; 大森 崇純

石川 幸治*; 川上 智彦*; 田仲 睦*; 鈴木 祐未*

JP, 2019-149027  Patent licensing information  Patent publication (In Japanese)

【課題】放射性アルミニウム廃棄物に含まれるアルミニウムを、化学的に安定である酸化アルミニウムに変換する放射性アルミニウム廃棄物処理方法を提供する。 【解決手段】本発明に係る放射性アルミニウム廃棄物処理方法は、放射性アルミニウム廃棄物に含まれるアルミニウムを酸化アルミニウムに変換する放射性アルミニウム廃棄物処理方法であって、放射性アルミニウム廃棄物を、アルカリ金属の水酸化物の水溶液で溶解し、不純物を沈殿させる溶解工程(工程S1)と、前記溶解工程で得られた溶液を、固液分離し不純物を除去する第1固液分離工程(工程S2)と、前記第1固液分離工程で得られた溶液に酸性水溶液を添加し、水酸化アルミニウムを主成分とする固体を沈殿させる中和工程(工程S3)と、前記中和工程で得られた溶液を、固液分離し固体を得る第2固液分離工程(工程S4)と、前記第2固液分離工程で得られた固体を焼成する焼成工程(工程S6)と、を含むことを特徴とする。

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