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JAEA Reports

Conceptual design of multipurpose compact research reactor; Annual report FY2011

Watahiki, Shunsuke; Hanakawa, Hiroki; Imaizumi, Tomomi; Nagata, Hiroshi; Ide, Hiroshi; Komukai, Bunsaku; Kimura, Nobuaki; Miyauchi, Masaru; Ito, Masayasu; Nishikata, Kaori; et al.

JAEA-Technology 2013-021, 43 Pages, 2013/07

JAEA-Technology-2013-021.pdf:5.12MB

The number of research reactors in the world is decreasing because of their aging. On the other hand, the necessity of research reactor, which is used for human resources development, progress of the science and technology, industrial use and safety research is increasing for the countries which are planning to introduce the nuclear power plants. From above background, the Neutron Irradiation and Testing Reactor Center began to discuss a basic concept of Multipurpose Compact Research Reactor (MCRR) for education and training, etc., on 2010 to 2012. This activity is also expected to contribute to design tool improvement and human resource development in the center. In 2011, design study of reactor core, irradiation facilities with high versatility and practicality, and hot laboratory equipment for the production of Mo-99 was carried out. As the result of design study of reactor core, subcriticality and operation time of the reactor in consideration of an irradiation capsule, and about the transient response of the reactor to the reactivity disturbance during automatic control operation, it was possible to do automatic operation of MCRR, was confirmed. As the result of design study of irradiation facilities, it was confirmed that the implementation of an efficient mass production radioisotope Mo-99 can be expected. As the result of design study with hot laboratory facilities, Mo-99 production, RI export devised considered cell and facilities for exporting the specimens quickly was designed.

JAEA Reports

Conceptual design of multipurpose compact research reactor; Annual report FY2010 (Joint research)

Imaizumi, Tomomi; Miyauchi, Masaru; Ito, Masayasu; Watahiki, Shunsuke; Nagata, Hiroshi; Hanakawa, Hiroki; Naka, Michihiro; Kawamata, Kazuo; Yamaura, Takayuki; Ide, Hiroshi; et al.

JAEA-Technology 2011-031, 123 Pages, 2012/01

JAEA-Technology-2011-031.pdf:16.08MB

The number of research reactors in the world is decreasing because of their aging. However, the planning to introduce the nuclear power plants is increasing in Asian countries. In these Asian countries, the key issue is the human resource development for operation and management of nuclear power plants after constructed them, and also the necessity of research reactor, which is used for lifetime extension of LWRs, progress of the science and technology, expansion of industry use, human resources training and so on, is increasing. From above backgrounds, the Neutron Irradiation and Testing Reactor Center began to discuss basic concept of a multipurpose low-power research reactor for education and training, etc. This design study is expected to contribute not only to design tool improvement and human resources development in the Neutron Irradiation and Testing Reactor Center but also to maintain and upgrade the technology on research reactors in nuclear power-related companies. This report treats the activities of the working group from July 2010 to June 2011 on the multipurpose low-power research reactor in the Neutron Irradiation and Testing Reactor Center and nuclear power-related companies.

Journal Articles

Magnetic and superconducting properties of LaIrSi$$_3$$ and CeIrSi$$_3$$ with the non-centrosymmetric crystal structure

Okuda, Yusuke*; Miyauchi, Yuichiro*; Ida, Yuki*; Takeda, Yuji*; Tonohiro, Chie*; Ozuchi, Yasuhiro*; Yamada, Tsutomu*; Nguyen, D.; Matsuda, Tatsuma; Haga, Yoshinori; et al.

Journal of the Physical Society of Japan, 76(4), p.044708_1 - 044708_11, 2007/04

 Times Cited Count:83 Percentile:91.99(Physics, Multidisciplinary)

Single crystals of LaIrSi$$_3$$ and CeIrSi$$_3$$ were grown by the Czochralski pulling method in a tetra-arc furnace and the magnetic and superconducting properties, together with super- conductivity in CeIr$$_{1-x}$$Co$$_x$$Si$$_3$$, were clarified by measuring the electrical resistivity, specific heat, magnetic susceptibility, magnetization and de Haas-van Alphen (dHvA) effect. From the results of the dHvA experiment for LaIrSi$$_3$$, the Fermi surface is found to split into two Fermi surfaces due to the spin-orbit interaction arising from the non-centrosymmetric crystal structure. The electronic state of CeIrSi$$_3$$ is tuned from the antiferro- magnetic state to the superconducting state by applying pressure. The upper critical field H$$_{c2}$$(0) at a pressure of 2.65 GPa is found to be highly anisotropic. Large magnitude and anisotropy of H$$_{c2}$$(0) in CeIrSi$$_3$$ are consistent with the theoretical prediction for superconductivity in the non-centrosymmetric crystal structure.

JAEA Reports

Present status of chemical analysis of uranyl nitrate solution used for the criticality experiments in NUCEF

Haga, Takahisa*; Gunji, Kazuhiko; Fukaya, Hiroyuki; Sonoda, Takashi; Sakazume, Yoshinori; Sakai, Yutaka; Niitsuma, Yasushi; Togashi, Yoshihiro; Miyauchi, Masakatsu; Sato, Takeshi; et al.

JAERI-Tech 2004-005, 54 Pages, 2004/02

JAERI-Tech-2004-005.pdf:2.06MB

Criticality experiments using uranyl nitrate solution fuel are being conducted at STACY (the Static Experiment Critical Facility) and TRACY (the Transient Experiment Critical Facility) in NUCEF (the Nuclear Fuel Cycle Safety Engineering Research Facility). Chemical analyses of the solution have been carried out to take necessary data for criticality experiments, for treatment and control of the fuel, and for safeguards purpose at the analytical laboratory placed in NUCEF. About 300 samples are analyzed annually that provide various kinds of data, such as uranium concentration, isolation acid concentration, uranium isotopic composition, concentration of fission product (FP) nuclides, tri-butyl phosphoric acid (TBP) concentration, impurities in the solution fuel and so on. This report summarizes the analytical methods and quality management of the analysis for uranyl nitrate solution relating to the criticality experiments.

Journal Articles

In situ EXAFS study on GeS$$_{2}$$ glass under high-pressure

Miyauchi, Koichi*; Qiu, J.*; Shojiya, Masanori*; Kawamoto, Yoji*; Kitamura, Naoyuki*; Fukumi, Kohei*; Katayama, Yoshinori; Nishihata, Yasuo

Solid State Communications, 124(5-6), p.189 - 193, 2002/10

 Times Cited Count:7 Percentile:39.4(Physics, Condensed Matter)

A GeS$$_{2}$$ glass was compressed up to 8 GPa at room temperature, heated up to 270 $$^{circ}$$C under 8 GPa and then decompressed to ambient pressure at room temperature, using a large volume high-pressure apparatus. The local structural-changes around Ge were examined by means of EXAFS method. The Ge-S bond length became monotonously short with increasing applied-pressure up to 8 GPa at room temperature. When the specimen was heated to 270 $$^{circ}$$C under 8 GPa, however, the vond length became slightly long. The elongated bond lengthe was almost kept even after the temperature was descended to room tempertature. In decompression process, the bond length became gradually long with releasing applied-pressure down to 2 GPa, following a change in compression process. Below 2 GPa, however, the Ge-S bond length was largely elongated, being lnger than the initial one. No significant change of coordination number was found in the compression and decompression processes up to 8 GPa. This change canbe explained by a combined effect of elastic and inelastic structural-changes.

JAEA Reports

Report of TRACY operation

Aizawa, Eiju; Ogawa, Kazuhiko; Sakuraba, Koichi; Tsukamoto, Michio; Sugawara, Susumu; Takeuchi, Masaki*; Miyauchi, Masakatsu; Yanagisawa, Hiroshi; Ono, Akio

JAERI-Tech 2002-031, 120 Pages, 2002/03

JAERI-Tech-2002-031.pdf:4.32MB

TRACY (Transient Experiment Critical Facility) in NUCEF (Nuclear Safety Research Facility) is the pulse-type critical facility using uranyl nitrate solution which can carry out various supercritical experiments changing reactivity addition up to 3$.TRACY achieved its first criticality on 20th December 1995,and transient operations have been conducted Since1996.This report summarizes the operation data of 176 experiments from the first criticality to FY2000.

JAEA Reports

Annual report on analytical works in NUCEF in F.Y. 2000

Tanoue, Takahiro; Gunji, Kazuhiko; Haga, Takahisa*; Fukaya, Hiroyuki; Sonoda, Takashi; Sakazume, Yoshinori; Niitsuma, Yasushi; Miyauchi, Masakatsu; Shirahashi, Koichi; Sato, Takeshi

JAERI-Tech 2001-071, 30 Pages, 2001/11

JAERI-Tech-2001-071.pdf:4.15MB

Analytical results of uranyl nitrate solution are essential data for the operation of the Static Experiment Critical Facility (STACY), the Transient Experiment Critical Facility (TRACY) and the fuel treatment system in the Nuclear Fuel Cycle Safety Engineering Research Facility (NUCEF). Analytical works were carried out for the determination of fuel characteristics before and after criticality experiments, fuel preparation and nuclear material accountancy in FY. 2000. In accordance with handling and dissolution of mixed oxide(MOX) powder in the fuel treatment system of NUCEF ,the preliminary tests for dissolution of the MOX powder in nitric acid solution have started since the end of 2000 ,after the MOX powder transfer to the NUCEF. The analytical works were carried out for the preliminary tests. A total number of analytical samples in FY. 2000 were 483 samples . This report summarizes the data on analytical works in FY.2000.

JAEA Reports

Annual report of STACY operation in FY. 2000; Experiments on neutron-interacting systems with two slab-shaped core tanks and 10% enriched uranyl nitrate solution, 2 (Contract research)

Onodera, Seiji; Hirose, Hideyuki; Izawa, Kazuhiko; Tanino, Shuichi; Kaminaga, Jota*; Sakuraba, Koichi; Miyauchi, Masakatsu; Tonoike, Kotaro; Miyoshi, Yoshinori; Yanagisawa, Hiroshi; et al.

JAERI-Tech 2001-057, 54 Pages, 2001/09

JAERI-Tech-2001-057.pdf:4.28MB

no abstracts in English

JAEA Reports

Annual report of STACY operation in FY.1999; Experiments on two unit neutron-interacting system with slab-shaped core tanks and 10% enriched uranyl nitrate solutions, 1 (Contract research)

Onodera, Seiji; Sono, Hiroki; Hirose, Hideyuki; Tanino, Shuichi; Kaminaga, Jota*; Myomae, Tomoki*; Murakami, Kiyonobu; Sakuraba, Koichi; Miyauchi, Masakatsu; Tonoike, Kotaro; et al.

JAERI-Tech 2000-059, 46 Pages, 2000/11

JAERI-Tech-2000-059.pdf:2.86MB

no abstracts in English

JAEA Reports

Annual report of STACY operation in F.Y. 1998, 2; 800mm-diameter cylindrical core$$cdot$$10% enriched uranyl nitrate solution (Contract research)

Onodera, Seiji; Sono, Hiroki; Hirose, Hideyuki; Tanino, Shuichi; Nagasawa, Makoto*; Murakami, Kiyonobu; Sakuraba, Koichi; Miyauchi, Masakatsu; Yamane, Yuichi; Ono, Akio

JAERI-Tech 2000-013, p.57 - 0, 2000/03

JAERI-Tech-2000-013.pdf:2.43MB

no abstracts in English

JAEA Reports

Annual report of STACY operation in F.Y. 1998, 1; 280mm thickness slab core$$cdot$$10% enriched uranyl nitrate solution (Contract research)

Onodera, Seiji; Sono, Hiroki; Hirose, Hideyuki; Tanino, Shuichi; Nagasawa, Makoto*; Murakami, Kiyonobu; Sakuraba, Koichi; Miyauchi, Masakatsu; Kikuchi, Tsukasa; Ono, Akio

JAERI-Tech 99-084, p.54 - 0, 1999/12

JAERI-Tech-99-084.pdf:2.7MB

no abstracts in English

JAEA Reports

Annual report of STACY operation in F.Y. 1997; 280mm thickness slab core・10% enriched uranyl nitrate solution (Contract research)

; ; Hirose, Hideyuki; *; *; Murakami, Kiyonobu; Takahashi, Tsukasa; Sakuraba, Koichi; Miyauchi, Masakatsu; ; et al.

JAERI-Tech 98-023, 66 Pages, 1998/06

JAERI-Tech-98-023.pdf:2.89MB

no abstracts in English

JAEA Reports

Improvement of fuel sampling device for STACY and TRACY

Hirose, Hideyuki; Sakuraba, Koichi; ; ; *; *; ; ; ; Miyauchi, Masakatsu; et al.

JAERI-Tech 98-015, 52 Pages, 1998/05

JAERI-Tech-98-015.pdf:1.68MB

no abstracts in English

Oral presentation

Study on the noble metals sedimentation behavior in the melted glass

Morikawa, Yo; Miyauchi, Atsushi; Nakajima, Masayoshi; Oyama, Koichi; Yamashita, Teruo; Komamine, Satoshi*; Ochi, Eiji*

no journal, , 

no abstracts in English

Oral presentation

Influence of long-term melting on the noble metals shape and glass viscosity, 2

Oyama, Koichi; Morikawa, Yo; Miyauchi, Atsushi; Nakajima, Masayoshi; Yamashita, Teruo; Komamine, Satoshi*; Ochi, Eiji*

no journal, , 

no abstracts in English

Oral presentation

Study on the sedimentation behavior of the noble metal particles in molten borosilicate glass

Oyama, Koichi; Morikawa, Yo; Miyauchi, Atsushi; Nakajima, Masayoshi; Yamashita, Teruo; Komamine, Satoshi*; Ochi, Eiji*

no journal, , 

no abstracts in English

Oral presentation

Sedimentation behavior of noble metal particles in simulated high-level waste borosilicate glasses

Nakajima, Masayoshi; Oyama, Koichi; Morikawa, Yo; Miyauchi, Atsushi; Yamashita, Teruo; Komamine, Satoshi*; Ochi, Eiji*

no journal, , 

Noble metal elements (NME) contained in high level liquid waste (HLLW) are distributed in a vitrification melter. Some part of them forms sediment which causes negative effects to steady operation of the melter. The formation process and characteristics of the sediment is useful information for considering methods of removing or discharging them. Thus the sedimentation observation was carried out by using simulated glass. Samples with 1.1wt% of initial NME concentration held at 1100$$^{circ}$$C indicated zone settling, and the settling rate of interface is constant; 2.4 mm/h. This sedimentation behavior is the type of rapid settling. Following the rapid settling, the settling rate goes slower gradually, this is the type of compressive settling. The samples whose initial NME concentrations are 3.0wt% and 6.1wt% showed compression settling form the beginning. From the settling curve of interface, the maximum concentration of NME in sediment was estimated as around 23-26wt%. This value can specify the properties of sediment to be removed, Also, growth of NME particles was observed by holding at 1100$$^{circ}$$C for up to 2880 hours.

Oral presentation

Elemental analysis of simulated waste glass by laser ablation ICP-AES, 4; Verification of quantitative analysis of various elements in simulated waste glass

Inose, Takehiko*; Nishizawa, Daiji; Oyama, Koichi; Miyauchi, Atsushi; Nagai, Takayuki

no journal, , 

no abstracts in English

Oral presentation

Elemental analysis of simulated waste glass by laser ablation ICP-AES, 5; Application of LA-ICP-AES for inactive mock-up test of vitrification process

Inose, Takehiko*; Nishizawa, Daiji*; Miyauchi, Atsushi; Oyama, Koichi; Yamakawa, Atsushi*; Nagai, Takayuki

no journal, , 

no abstracts in English

Oral presentation

Application of laser ablation ICP-AES for inactive mock-up test of vitrification process

Oyama, Koichi; Inose, Takehiko*; Miyauchi, Atsushi; Nishizawa, Daiji*; Nagai, Takayuki

no journal, , 

no abstracts in English

23 (Records 1-20 displayed on this page)