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Journal Articles

Development of a design support system for geological disposal of radioactive waste using a CIM concept

Sugita, Yutaka; Kageyama, Takeshi*; Makino, Hitoshi; Shimbo, Hiroshi*; Hane, Koji*; Kobayashi, Yuichi*; Fujisawa, Yasuo*; Makanae, Koji*; Yabuki, Nobuyoshi*

Proceedings of 17th International Conference on Computing in Civil and Building Engineering (ICCCBE 2018) (Internet), 8 Pages, 2018/06

This paper presents status of development of the iSRE (integrated system for repository engineering) as a design supporting system that enables rational designing of a geological disposal repository. The complimentary technique of construction information modeling/management (CIM) has been employed for the development of iSRE. CIM uses a shared three dimensional (3D) model of associated data through common data models. In this paper, as a design support system that conforms to the characteristics of information management about engineering technology represented by repetition of design during the disposal project period, we examined and designed the function of the "iSRE", constructed a prototype, and confirmed the function through a trial simulating actual work in the disposal project. As a result, with respect to the functions of DB and IF of the iSRE, we got a prospect that these functions can be the foundation of information management on engineering technology, and development of the prototype of the iSRE and its test run extracted issues for practical use of such system.

Journal Articles

Feasibility study on an upgraded future Monju core concept with extended operation cycle length of one year and increased fuel burnup

Kinjo, Hidehito*; Kageyama, Takeshi*; Kitano, Akihiro; Usami, Shin

Nuclear Technology, 167(2), p.254 - 267, 2009/08

 Times Cited Count:1 Percentile:87.33(Nuclear Science & Technology)

A conceptual design study has been performed on upgrading the core performance of the Japanese FBR Monju. The main aim of this study is to investigate and demonstrate the feasibility of an upgraded core with an extended refueling interval of 365 EFPD and increased average fuel burnup of 150 GWd/t, which are expected in future commercial FBRs. Two design measures have been taken to accommodate the largely increased burnup reactivity for the longer cycle: (1) A modified fuel pin with increased pin diameter, pellet density and active core height has been introduced to improve the burnup reactivity, (2) The control rod specification has been modified to enhance the reactivity worth by increasing the $$^{10}$$B content to assure sufficient shutdown margin. The evaluation results show that even a medium sized core of about 2.5 m$$^{3}$$ could achieve the target, without causing significant drawbacks to the core characteristics. The feasibility is thus demonstrated.

Journal Articles

Studies on Plutonium Burning in the Prototype Fast Breeder Reactor Monju

Udo, Wehmann; Kinjo, H.; Kageyama, Takeshi*

Nuclear Science and Engineering, 140(3), p.205 - 222, 2002/03

 Times Cited Count:2 Percentile:80.93(Nuclear Science & Technology)

None

JAEA Reports

Feasibility study on Plutonium burning in future Monju cores

Udo, Wehmann; Kageyama, Takeshi*

JNC-TN4400 99-001, 96 Pages, 1999/12

JNC-TN4400-99-001.pdf:4.25MB

These studies have been planned and performed as a contribution to the demon- stration of the plutonium burning capabilities of fast reactors in future Monju cores. For an upgraded Monju core design with an increased average discharge burnup of 100 GWd/t, burner cores with diluents and with diluting pins have been investigated, the main aim of which is to increase the average plutonium enrichment of the fuel and thus the plutonium burning rate. On the other side the consequences of the suppression of the radial and/or axial blanket have been investigated. The results of these studies had been documented separately in [1] to [5], while this reports gives the compilation of these studies and a judgement about the different burner concepts. Among the burner concepts different types of diluents (containing sodium and steel or B4C) and diluting pins (Steel, moderator or B4C) have been compared with each other. The diluent concept with B4C-diluents has been found to be the preferable one, because it causes the smallest increase of the maximum linear rating and because it offers the largest design flexibility to adapt the core reactivity via a modification of the B4C content. For the case of the blanket suppression the replacement of the blanket zones by a steel reflector has been found to be the best solution, whereby the addition of some B4C in the outer reflector regions may be necessary to increase the shielding efficiency. The main consequence of the suppression of both blankets is the increase of the maximum linear rating by up to 12%. Whether this increase may lead to problems, will depend on the actual linear power level of the core and the maximum allowable value as defined by the non-melting criterion. For cores with partly reduced radial and/or axial blanket data are also provided.

Journal Articles

L X-ray spectra of Fe and Cu by 0.75 MeV/u H, He, Si and Ar ion impacts

Kageyama, H.*; Kawatsura, Kiyoshi*; Takahashi, R.*; Arai, Shigeyoshi*; Kambara, Tadashi*; Oura, M.*; Papp, T.*; Kanai, Y.*; Awaya, Y.*; Takeshita, Hidefumi; et al.

Nuclear Instruments and Methods in Physics Research B, 107(1-4), p.47 - 50, 1996/00

 Times Cited Count:2 Percentile:66.95

no abstracts in English

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

Prototype FBR Monju system start up test "zero power reactor physics test", 3; Evaluation of neutron source

Kato, Yuko; Miyagawa, Takayuki; Kageyama, Takeshi; Okimoto, Yutaka

no journal, , 

no abstracts in English

Oral presentation

Prototype FBR Monju system start up test "zero power reactor physics test", 9; Summary of calculation results

Hazama, Taira; Kageyama, Takeshi; Hikichi, Takuo*; Okawachi, Yasushi; Suzuki, Takayuki

no journal, , 

no abstracts in English

Oral presentation

Prototype FBR Monju system start up test "Reactor Physics Test", 3; Evaluation of neutron source

Kato, Yuko; Miyagawa, Takayuki; Kageyama, Takeshi; Okimoto, Yutaka

no journal, , 

no abstracts in English

Oral presentation

Development of the Integrated System for Repository Engineering (iSRE), 4; Current status of the prototype of the iSRE

Yoshino, Hiroyuki*; Fujisawa, Yasuo*; Kobayashi, Yuichi*; Sugita, Yutaka; Kageyama, Takeshi; Hane, Koji*; Sahara, Fumihiro*; Yabuki, Nobuyoshi*; Makanae, Koji*

no journal, , 

This paper reports development of ISRE (the Integrated System for Repository Engineering), as a knowledge management tool on the repository design and engineering technology, which manages and inherits the information and knowledge of each phase of the disposal project of the radioactive waste during around 100 years, which also enables reasonable design of the repository by using accumulated and integrated information. Content of this paper is current status of the prototype of the iSRE.

Oral presentation

Development of the Integrated System for Repository Engineering (iSRE), 5; Utilization of the protype of the iSRE

Hane, Koji*; Sahara, Fumihiro*; Sugita, Yutaka; Kageyama, Takeshi; Fujisawa, Yasuo*; Yoshino, Hiroyuki*; Kobayashi, Yuichi*; Yabuki, Nobuyoshi*; Makanae, Koji*

no journal, , 

This paper reports development of ISRE (the Integrated System for Repository Engineering), as a knowledge management tool on the repository design and engineering technology, which manages and inherits the information and knowledge of each phase of the disposal project of the radioactive waste during around 100 years, which also enables reasonable design of the repository by using accumulated and integrated information. Content of this paper is outline of trial utilization of the prototype of the iSRE and the extracted issues.

Oral presentation

Development of the Integrated System for Repository Engineering (iSRE), 6; Expansion of function for practical use of the iSRE

Numata, Taro*; Fujisawa, Yasuo*; Kobayashi, Yuichi*; Sugita, Yutaka; Kageyama, Takeshi; Hane, Koji*; Sahara, Fumihiro*; Yabuki, Nobuyoshi*; Makanae, Koji*

no journal, , 

This paper reports development of ISRE (the Integrated System for Repository Engineering), as a knowledge management tool on the repository design and engineering technology, which manages and inherits the information and knowledge of each phase of the disposal project of the radioactive waste during around 100 years, which also enables reasonable design of the repository by using accumulated and integrated information. Content of this paper is expansion of function for practical use of the iSRE.

Oral presentation

Development of the Integrated System for Repository Engineering (iSRE), 7; Utilization of for practical use of prototype of the iSRE

Hane, Koji*; Sahara, Fumihiro*; Sugita, Yutaka; Kageyama, Takeshi; Fujisawa, Yasuo*; Numata, Taro*; Kobayashi, Yuichi*; Yabuki, Nobuyoshi*; Makanae, Koji*

no journal, , 

This paper reports development of ISRE (the Integrated System for Repository Engineering), as a knowledge management tool on the repository design and engineering technology, which manages and inherits the information and knowledge of each phase of the disposal project of the radioactive waste during around 100 years, which also enables reasonable design of the repository by using accumulated and integrated information. Content of this paper is outline of trial utilization of prototype of the iSRE and the extracted issues for practical system.

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