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JAEA Reports

Verification of alternative dew point hygrometer for CV-LRT in MONJU; Short- and long-term verification for capacitance-type dew point hygrometer (Translated document)

Ichikawa, Shoichi; Chiba, Yusuke; Ono, Fumiyasu; Hatori, Masakazu; Kobayashi, Takanori; Uekura, Ryoichi; Hashiri, Nobuo*; Inuzuka, Taisuke*; Kitano, Hiroshi*; Abe, Hisashi*

JAEA-Research 2017-001, 40 Pages, 2017/03

JAEA-Research-2017-001.pdf:5.19MB

In order to reduce the influence on a plant schedule of the MONJU by the maintenance of dew point hygrometers, The JAEA examined a capacitance type dew point hygrometer as an alternative dew point hygrometer for a lithium-chloride type dew point hygrometer which had been used at the CV-LRT in the MONJU. As a result of comparing a capacitance type dew point hygrometer with a lithium-chloride type dew point hygrometer at the CV-LRT (Atmosphere: nitrogen, Testing time: 24 hours), there weren't significant difference between a capacitance type dew point hygrometer and a lithium-chloride type dew point hygrometer. As a result of comparing a capacitance dew point hygrometer with a high-mirror-surface type dew point hygrometer for long term verification (Atmosphere: air, Testing time: 24 months), the JAEA confirmed that a capacitance type dew point hygrometer satisfied the instrument specification ($$pm$$2.04$$^{circ}$$C) required by the JEAC4203-2008.

JAEA Reports

Verification of alternative dew point hygrometer for CV-LRT in Monju

Ichikawa, Shoichi; Chiba, Yusuke; Ono, Fumiyasu; Hatori, Masakazu; Kobayashi, Takanori; Uekura, Ryoichi; Hashiri, Nobuo*; Inuzuka, Taisuke*; Kitano, Hiroshi*; Abe, Hisashi*

JAEA-Research 2016-021, 32 Pages, 2017/02

JAEA-Research-2016-021.pdf:5.0MB

In order to reduce the influence on a plant schedule of the MONJU by the maintenance of dew point hygrometers, The JAEA examined a capacitance type dew point hygrometer as an alternative dew point hygrometer for a lithium-chloride type dew point hygrometer which had been used at the CV-LRT in the MONJU. As a result of comparing a capacitance type dew point hygrometer with a lithium-chloride type dew point hygrometer at the CV-LRT (Atmosphere: nitrogen, Testing time: 24 hours), there weren't significant difference between a capacitance type dew point hygrometer and a lithium-chloride type dew point hygrometer. As a result of comparing a capacitance dew point hygrometer with a high-mirror-surface type dew point hygrometer for long term verification (Atmosphere: air, Testing time: 24 months), the JAEA confirmed that a capacitance type dew point hygrometer satisfied the instrument specification ($$pm$$2.04$$^{circ}$$C) required by the JEAC4203-2008.

Journal Articles

Development of reactivity feedback effect measurement techniques under sub-critical condition in fast reactors

Kitano, Akihiro; Nishi, Hiroshi; Suzuki, Takayuki; Okajima, Shigeaki; Kanemoto, Shigeru*

Proceedings of International Conference on Physics of Reactors; Advances in Reactor Physics; Linking Research, Industry, and Education (PHYSOR 2012) (CD-ROM), 14 Pages, 2012/04

The "Synthesis Method", a systematic and sophisticated method of sub-criticality measurement, is proposed in this work to ensure the safety margin before operation. The "Synthesis Method" is based on the modified source multiplication method (MSM) combined with the noise analysis method to measure the reference sub-criticality level for MSM. As a result of numerical simulation, it was suggested that a neutron detector located above the core center and three or more neutron detectors located above the radial blanket region enable the measurement of sub-criticality within 10% uncertainty from -0.5 to -2 and within 15% uncertainty for the deeper sub-criticality.

Journal Articles

Development of 3-D detailed FBR core calculation method based on method of characteristics

Takeda, Toshikazu*; Imai, Hideki*; Kitada, Takanori*; Nishi, Hiroshi; Ishibashi, Junichi; Kitano, Akihiro

Proceedings of International Topical Meeting on Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications (M&C 2005) (CD-ROM), 12 Pages, 2005/09

A new detailed 3-D transport calculation method taking into account the heterogeneity of fuel assemblies has been developed in hexagonal-z geometry by combining the method of characteristics and the nodal transport method. From the nodal transport calculation which uses assembly homogenized cross sections, the axial leakage is calculated, and it is used for the MOC calculation which treats the heterogeneity of fuel assemblies. Series of homogeneous MOC calculations which use assembly homogeneous cross sections are carried out of obtain effective cross sections, which preserve assembly reaction rates. This effective cross sections are again used in the 3-D nodal transport calculations. The numerical calculations have been performed to verify 3-D radial calculations of FBR assemblies and partial core calculations. Results are compared with the reference Monte-Carlo calculations. A good agreement has been achieved. It is shown that the present method has an advantage in calculating reaction tates in small region.

JAEA Reports

Conceptual study of transmutation experimental facility, 2; Study on ADS target test facility

Sasa, Toshinobu; Umeno, Makoto*; Mizubayashi, Hiroshi*; Mori, Keijiro*; Futakawa, Masatoshi; Saito, Shigeru; Kai, Tetsuya; Nakai, Kimikazu*; Zako, Akira*; Kasahara, Yoshiyuki*; et al.

JAERI-Tech 2005-021, 114 Pages, 2005/03

JAERI-Tech-2005-021.pdf:9.66MB

To perform the research and development for accelerator-driven system (ADS), Japan Atomic Energy Research Institute (JAERI) plans to build a Transmutation Experimental Facility under the JAERI-KEK joint J-PARC program. Transmutation Experimental Facility consists of two buildings, Transmutation Physics Experimental Facility to make reactor physics experiment with subcritical core, and ADS Target Test Facility for the preparation of irradiation database for various structural materials. In this report, purpose to build, experimental schedule, and design study of the ADS target test facility with drawer type spallation target are summarized.

Journal Articles

High power millimeter and submillimeter wave material processing

Mitsudo, Seitaro*; Hoshizuki, Hisanori*; Matsuura, Kazunari*; Saji, T.*; Idehara, Toshitaka*; Glyavin, M.*; Eremeev, A.*; Zapevalov, V.*; Kitano, Akihiro; Nishi, Hiroshi; et al.

Proceedings of 29th International Conference on Infrared and Millimeter Waves (IRMMW 2004)/12th International Conference on Terahertz Electronics (THz 2004), p.727 - 728 , 2004/09

Boron carbide (B$$_{4}$$C) is one of advanced materials and is being used in a wide rage of applications. The unique feature of this material is its large neutron-absorbing cross-section. Some of its most prominent applications are controlling rods in nuclear reactors and radiation protection. 24 GHz microwave processing for B$$_{4}$$C ceramics were performed under flowing argon gas using the sintering system. The sintered samples were characterized by the density, the shrinkage and SEM micrographs of fracture surface. Above the temperature of 2000$$^{circ}$$C, the shrinkage and the grain grows were observed.

JAEA Reports

Improvements of the Control Rod Material for Long Lifetime by the High Power Millimeter-wave Ceramics Sintering Method

Idehara, Toshitaka*; Mitsudo, Seitaro*; Hoshizuki, Hisanori*; Ogawa, Isamu*; Shibahara, Itaru; Nishi, Hiroshi; Kitano, Akihiro; Ishibashi, Junichi

JNC TY4400 2003-005, 106 Pages, 2003/03

JNC-TY4400-2003-005.pdf:9.48MB

Boron Carbide B4C pellet is an important part of control rod used to control the reactivity of nuclear reactors. B4C pellet put in a nuclear reactor suffers heavy radiation damage and deformation, which result in a partial destruction and shorten the lifetime of B4C. It is important to improve the characteristics of the B4C pellets for extension of its lifetime. As the results, if the control rod without the shroud will be available, we can realize much simpler structure. In order to improve, the B4C pellet, which was sintered by the hot-press methods, we have re-sintered it by high power millimeter wave ceramics nano-indentation test. The increase of the plasticity is observed. The same improvement of plasticity was observed in alumina pellets that were sintered by millimeter wave sintering methods. Such results imply that the further improvement is expected, if the B4C pellet is sintered from powder specimen by the high power millimeter-wave sintering method. To simulate a partial destruction of B4C pellet under the thermal stress, preliminary internal heating experiments of B4C pellet are performed by using high power millimeter-wave. At the difference between internal and surface temperatures of 1000C, the partial destructions and small cracks are observed in B4C pellet. Thes may be a kind of model experiment for destruction of B4C pellet irradiated by neutrons.

Journal Articles

B$$_{4}$$C ceramics sintering using 24 GHz gyrotron radiation

Hoshizuki, Hisanori*; Kuroda, Tsutomu*; Mitsudo, Seitaro*; Idehara, Toshitaka*; Glyavin, M.*; Kitano, Akihiro; Ishibashi, Junichi; Nishi, Hiroshi; Shibahara, Itaru

En Sekigai Ryoiki Kaihatsu Kenkyu, 4, p.179 - 185, 2003/00

None

Journal Articles

MA/LLFP TRANSMUTATION EXPERIMENT OPTIONS IN THE FUTURE MONJU CORE

Kitano, Akihiro; Nishi, Hiroshi; Ishibashi, Junichi

GENES4/ANP2003, 0 Pages, 2003/00

None

Journal Articles

Millimeter wave sintering of B$$_{4}$$C by using a compact gyrotron system

Hoshizuki, Hisanori*; Mitsudo, Seitaro*; Glyavin, M.*; Eremeev, A.*; *; *; Kitano, Akihiro; Ishibashi, Junichi; Nishi, Hiroshi; Shibahara, Itaru; et al.

Proceedings of 28th International Conference on Infrared and Millimeter Waves (IRMMW 2003), P. 1005, 2003/00

None

Journal Articles

3D Transport Theory Method Based on MOC for Analyzing Integral Dta of Transmutation

Takeda, Toshikazu*; Hamada, Yuzuru*; Kitada, Takanori*; Nishi, Hiroshi; Ishibashi, Junichi; Kitano, Akihiro

Proceedings of International Conference on Advanced Nuclear Energy and Fuel Cycle Systems (GLOBAL 2003) (CD-ROM), p.1005 - 1010, 2003/00

A new 3-D transport calculation method taking into account the heterogeneity of fuel assemblies has been developed by combining the characteristics method and the nodal transport method. In the axial direction the nodal transport method is applied, and the characteristics method is applied to take into account the radial heterogeneity of fuel assemblies. The numerical calculations have been performed to verify 2-D radial calculations of FBR assemblies and partial core calculations. Results are compared with the reference Monte-Carlo calculations. A good agreement has been achieved. It is shown that the present method has an advantage in calculating reaction rates in a small region.

Journal Articles

Development of Monju Easy-to-Introduce System for Total Evaluation of Reactor Core

Kitano, Akihiro; Teruyama, Hidehiko; Nishi, Hiroshi; Yamaoka, Mitsuaki*; Moriki, Yasuyuki*; Nakagawa, Masatoshi*

Saikuru Kiko Giho, (15), p.1 - 16, 2002/06

None

JAEA Reports

Evaluation of mechanical properties of hydrided cladding by usig modified ring tensile test

Kitano, Koji*; Fuketa, Toyoshi; Uetsuka, Hiroshi

JAERI-Research 2001-041, 24 Pages, 2001/08

JAERI-Research-2001-041.pdf:2.75MB

no abstracts in English

JAEA Reports

Optimization of tensile method and specimen geometry in modified ring tensile test

Kitano, Koji*; Fuketa, Toyoshi; Sasajima, Hideo; Uetsuka, Hiroshi

JAERI-Research 2001-011, 34 Pages, 2001/03

JAERI-Research-2001-011.pdf:2.48MB

no abstracts in English

JAEA Reports

Cost estimation for the geological disposal system of high level ratioactive wast, for 1988; The Development of cost integrating system

Maki, Yasuro*; Kitano, Koichi*; Inoue, Daiei*; Onuma, Hiroshi*; Komada, Hiroya*; Yamaji, Kenji*; Osumi, Takashi*; Tanaka, Hiroshi*; Imazu, Masanori*

JNC TJ1400 2005-005, 98 Pages, 1989/03

JNC-TJ1400-2005-005.pdf:2.98MB

no abstracts in English

Journal Articles

None

Teruyama, Hidehiko; Nishi, Hiroshi; Kitano, Akihiro

Nihon Genshiryoku Gakkai-Shi, 8, , 

None

Oral presentation

Oral presentation

Analyses of Monju core by European reactor analysis system "ERANOS"

Usami, Shin; Kageyama, Takeshi*; Morohashi, Yuko; Kitano, Akihiro; Kishimoto, Yasufumi*; Teruyama, Hidehiko; Nishi, Hiroshi

no journal, , 

no abstracts in English

Oral presentation

Development of reactivity feedback effect measurement techniques under sub-critical condition in fast reactor, 1-3; A Study on neutron detector response evaluation model

Nishi, Hiroshi; Kitano, Akihiro; Suzuki, Takayuki; Okajima, Shigeaki

no journal, , 

A simulation calculation study has been carried out on the relationship between the control rod insertion patterns and the neutron detector responses under sub-critical state, assuming a measurement of the core reactivity change by the modified source multiplication (MSM) method. Location-dependent characteristics of the neutron detectors were analyzed based on the results of the simulation calculations. A sensitivity analysis on the fuel composition burn-up change to the neutron detector responses was performed at the same time, and the major sensitive macroscopic cross-sections were identified. It is important to take into account the actual burn-up reactivity change of the actual reactor in order to reduce the effect of the uncertainty, induced by the fuel composition burn-up change, on the modification factor for MSM. It was concluded that the adjustment of these major macroscopic cross-sections will be effective and practical for this purpose.

Oral presentation

Development of reactivity feedback effect measurement techniques under sub-critical condition in fast reactor, 1-6; A Feasibility study on sub-critical reactivity measurement system application to power reactors

Kitano, Akihiro; Nishi, Hiroshi; Suzuki, Takayuki; Okajima, Shigeaki; Kanemoto, Shigeru*

no journal, , 

A study on the basic algorithm and application to actual reactors of the synthesis method, which combines the reactor noise analysis and modified source multiplication (MSM) method, has been conducted based on numerical simulation calculations, in order to establish a concept of the sub-critical reactivity measurement system. Required performances of the sub-criticality measurement algorithm for the reactor noise analysis was studied, assuming the reference sub-criticality measurement by noise analysis for MSM. As a result it was found out that the accuracy of the measurement will be dominated by the neutron detector efficiency and the improvement of the accuracy will be expected by using lower frequency amplitude data for the break (corner) frequency method. A numerical simulation was performed for actual reactors based on these results, and the dual-detector method was identified to be effective, which can avoid the influence of higher-order effect.

29 (Records 1-20 displayed on this page)