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Journal Articles

Appropriate damping on seismic design analysis for inelastic response assessment of piping

Watakabe, Tomoyoshi; Morishita, Masaki

Proceedings of 2018 ASME Pressure Vessels and Piping Conference (PVP 2018), 6 Pages, 2018/07

A new Code Case for seismic design of piping is now under development in the framework of JSME Nuclear Codes and Standards as an alternative rule to the current design rule. Simplified analysis with an additional damping taking the response reduction due to plasticity into account is now under consideration to incorporate the convenience in design. In this study, a series of analysis was made to see the adequacy of the simplified inelastic analysis. Design margins contained in the current design analysis method composed of response spectrum analysis and stress factors was quantitatively assessed in the view point of additional damping.

Journal Articles

Ultimate strength of a thin wall elbow for sodium cooled fast reactors under seismic loads

Watakabe, Tomoyoshi; Tsukimori, Kazuyuki; Kitamura, Seiji; Morishita, Masaki

Journal of Pressure Vessel Technology, 138(2), p.021801_1 - 021801_10, 2016/04

 Times Cited Count:3 Percentile:71.96(Engineering, Mechanical)

With a purpose of identifying the failure mode and the associating ultimate strength of piping components against seismic integrity, many kinds of failure tests have been conducted for thick wall piping for Light Water Reactors (LWRs). However, there are little failure test data on thin wall piping for Sodium Cooled Fast Reactors (SFRs). In this paper, a series of failure tests on thin wall elbows for SFRs is presented. Based on the tests, the failure mode of a thin wall piping component under seismic loads was identified to be fatigue. The safety margin included in the current design methodology was clarified quantitatively.

Journal Articles

Application of the system based code concept to the determination of in-service inspection requirements

Takaya, Shigeru; Asayama, Tai; Kamishima, Yoshio*; Machida, Hideo*; Watanabe, Daigo*; Nakai, Satoru; Morishita, Masaki

Journal of Nuclear Engineering and Radiation Science, 1(1), p.011004_1 - 011004_9, 2015/01

A new process for determination of inservice inspection (ISI) requirements was proposed based on the System Based Code concept to realize effective and rational ISI by properly taking into account plant specific features. The proposed process consists of two complementary evaluations, one focusing on structural integrity and the other one on detectability of defects before they would grow to an unacceptable size in light of plant safety. If defect detection was not feasible, structural integrity evaluation would be required under sufficiently conservative hypothesis. The applicability of the proposed process was illustrated through an application to the existing prototype fast breeder reactor, Monju.

Journal Articles

Development of structural codes for JSFR based on the system based code concept

Asayama, Tai; Wakai, Takashi; Ando, Masanori; Okajima, Satoshi; Nagae, Yuji; Takaya, Shigeru; Onizawa, Takashi; Tsukimori, Kazuyuki; Morishita, Masaki

Proceedings of 2014 ASME Pressure Vessels and Piping Conference (PVP 2014) (DVD-ROM), 6 Pages, 2014/07

This paper overviews the ongoing research and development as well as activities for codification of structural codes for the Japan Sodium Cooled Fast Reactor (JSFR). Not only the design and construction code which has been published and updated on a regular basis, codes on welding, fitness-for-service, leak-before-break evaluation as well as the guidelines for structural reliability evaluation are being developed. The basic strategy for the development is to fully take advantage of the favorable technical characteristics associated with sodium-cooled fast reactors; the codes will be developed based on the System Based Code concept. The above mentioned set of codes are planned to be published from the Japan Society of Mechanical Engineers in 2016.

Journal Articles

Elaboration of the system based code concept; Activities in JSME and ASME, 4; Joint efforts of JSME and ASME

Asayama, Tai; Takaya, Shigeru; Morishita, Masaki; Schaaf, F.*

Proceedings of 22nd International Conference on Nuclear Engineering (ICONE-22) (DVD-ROM), 9 Pages, 2014/07

This paper describes the ongoing activities at the Joint Task Group for System Based Code established in 2012 by the Japan Society of Mechanical Engineers (JSME) and the American Society of Mechanical Engineers (ASME) in the ASME Boiler and Pressure Vessel Code Committee. The Joint Task Group aims at developing alternative rules for ASME Boiler and Pressure Vessel Code Section XI Division 3, inservice inspection requirements for liquid metal reactors. The alternative rules will be developed based on the System Based Code concept which was originally proposed in Japan and is being elaborated both in JSME and ASME.

Journal Articles

Study on ultimate strength of thin-wall piping components for fast breeder reactors under seismic loading

Watakabe, Tomoyoshi; Kitamura, Seiji; Tsukimori, Kazuyuki; Morishita, Masaki

Transactions of 22nd International Conference on Structural Mechanics in Reactor Technology (SMiRT-22) (CD-ROM), 10 Pages, 2013/08

It is important to confirm failure modes and safety margin until ultimate strength of piping components from the point of view of seismic safety. Though, many dynamic failure tests of the thick-wall piping components for Light Water Reactors (LWRs) have been performed, there are little dynamic failure test data of the thin-wall pipe for Fast Breeder Reactors (FBRs). This paper presents a series of dynamic failure tests of thin-wall elbows with the diameter/thickness ratio close to that of the main piping of FBRs and discusses about vibration characteristics in elastic-plastic region, failure modes under dynamic load and the results of piping design evaluation for the test model. Moreover, the test results were compared to the Finite Element Analysis (FEA) results.

Journal Articles

Shaking table tests with large test specimens of seismically isolated FBR plants, 1; Response behavior of test specimen under design ground motions

Kitamura, Seiji; Morishita, Masaki; Yabana, Shuichi*; Hirata, Kazuta*; Umeki, Katsuhiko*

Proceedings of 2009 ASME Pressure Vessels and Piping Division Conference (PVP 2009) (CD-ROM), 8 Pages, 2009/07

Journal Articles

Current status and perspective of advanced loop type fast reactor in fast reactor cycle technology development project

Niwa, Hajime; Aoto, Kazumi; Morishita, Masaki

Proceedings of International Conference on Advanced Nuclear Fuel Cycles and Systems (Global 2007) (CD-ROM), p.62 - 70, 2007/09

Journal Articles

Development of elevated temperature structural design standard and three-dimensional seismic isolation technology for advanced nuclear power plant

Inoue, Kazuhiko*; Shibamoto, Hiroshi*; Takahashi, Kenji; Ikutama, Shinya*; Morishita, Masaki; Aoto, Kazumi; Kasahara, Naoto; Asayama, Tai; Kitamura, Seiji

Nippon Genshiryoku Gakkai-Shi, 48(5), p.333 - 338, 2006/05

no abstracts in English

JAEA Reports

H$$^{-}$$ ion beam acceleration in a single gap multi-aperture accelerator

Watanabe, Kazuhiro; Takayanagi, Tomohiro; Okumura, Yoshikazu; Hanada, Masaya; Inoue, Takashi; Kashiwagi, Mieko; Morishita, Takatoshi; Taniguchi, Masaki

JAEA-Technology 2005-002, 19 Pages, 2006/01

JAEA-Technology-2005-002.pdf:2.34MB

no abstracts in English

Journal Articles

Spin multiplicity and charge state of a silicon vacancy (${it T}$ $$_{V2a}$$) in 4${it H}$-SiC determined by pulsed ENDOR

Mizuochi, Norikazu*; Yamasaki, Satoshi*; Takizawa, Haruki; Morishita, Norio; Oshima, Takeshi; Ito, Hisayoshi; Umeda, Takahide*; Isoya, Junichi*

Physical Review B, 72(23), p.235208_1 - 235208_6, 2005/12

 Times Cited Count:46 Percentile:16.09(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Experimental study on spatial uniformity of H$$^{-}$$ ion beam in a large negative ion source

Hanada, Masaya; Seki, Takayoshi*; Takado, Naoyuki*; Inoue, Takashi; Morishita, Takatoshi; Mizuno, Takatoshi*; Hatayama, Akiyoshi*; Imai, Tsuyoshi*; Kashiwagi, Mieko; Sakamoto, Keishi; et al.

Fusion Engineering and Design, 74(1-4), p.311 - 317, 2005/11

 Times Cited Count:7 Percentile:52.03(Nuclear Science & Technology)

no abstracts in English

Journal Articles

R&D on a high energy accelerator and a large negative ion source for ITER

Inoue, Takashi; Taniguchi, Masaki; Morishita, Takatoshi; Dairaku, Masayuki; Hanada, Masaya; Imai, Tsuyoshi*; Kashiwagi, Mieko; Sakamoto, Keishi; Seki, Takayoshi*; Watanabe, Kazuhiro

Nuclear Fusion, 45(8), p.790 - 795, 2005/08

The R&D of a 1 MeV accelerator and a large negative ion source have been carried out at JAERI. The paper presents following progress as a step toward ITER NB system. (1) Accelerator R&D: According to success in improvement of voltage holding capability, the acceleration test of H$$^{-}$$ ions up to 1 MeV class energy is in progress. H$$^{-}$$ ion beams of 1 MeV, 100 mA class have been generated with a substantial beam current density (100 A/m$$^{2}$$), and the current density is still increasing by the ion source tuning. (2) Large ion source R&D: One of major causes that limited the NB injection performance was spatial unifomity of negative ion production in existing negative-ion based NB systems. The present study revealed that the negative ions produced in the extraction region of the source were locally destructed by fast electrons leaking through magnetic filter. Some countermeasures and their test results are also described.

Journal Articles

R&D on a high energy accelerator and a large negative ion source for ITER

Inoue, Takashi; Taniguchi, Masaki; Morishita, Takatoshi; Dairaku, Masayuki; Hanada, Masaya; Imai, Tsuyoshi*; Kashiwagi, Mieko; Sakamoto, Keishi; Seki, Takayoshi*; Watanabe, Kazuhiro

Nuclear Fusion, 45(8), p.790 - 795, 2005/08

 Times Cited Count:22 Percentile:38.47(Physics, Fluids & Plasmas)

The R&D of a 1 MeV accelerator and a large negative ion source has been carried out at JAERI for the ITER NB system. The R&D is in progress at present toward: (1) 1 MeV acceleration of H$$^{-}$$ ion beams at the ITER relevant current density of 200 A/m$$^{2}$$, and (2) improvement of uniform negative ion production over wide extraction area in large negative ion sources. Recently, H$$^{-}$$ ion beams of 1 MeV, 140 mA level have been generated with a substantial beam current density (100 A/m$$^{2}$$). In the uniformity study, it has been clarified that electron temperature in the ion extraction region is locally high ($$>$$ 1 eV), which resulted in destruction of negative ions at a high reaction rate. Interception of fast electrons leaking through a transverse magnetic field called "magnetic filter" has been found effective to lower the local electron temperature, followed by an improvement of negative ion beam profile.

JAEA Reports

Study on advanced structual design for commercialized fast breeder reactors

Morishita, Masaki; Aoto, Kazumi; Kasahara, Naoto; Asayama, Tai; Nakamura, Kyotada*; Inoue, Kazuhiko*; Nagashima, Hideaki*

JNC-TY9400 2005-012, 2351 Pages, 2005/07

JNC-TY9400-2005-012-1.pdf:135.59MB
JNC-TY9400-2005-012-2.pdf:63.18MB

Aiming to realize safety and economcal commercialized fast reactor, R6D activities on structural design methods launched FY 2000 and continued up to FY 2004. The reserch scope was identified as (1)FBR Structural Design Standard (FDS), (2)Standardiation of new material and (3)System Based Code for Integrity. Since this fisical year is the Last year for the R6D activities, the results are summarized as FBR Design Stndard (interim proposal), Standadization of new material (interim prpposal) etc. The results of this report include a part of

Journal Articles

Development of vertical component isolation system with coned disk springs for FBR plant

Kitamura, Seiji; Okamura, Shigeki; Takahashi, Kenji; Kamishima, Yoshio*; Somaki, Takahiro*; Morishita, Masaki

Proceedings of 9th World Seminar on Seismic Isolation, Energy Dissipation and Active Vibration Control of Structures (CD-ROM), p.209 - 216, 2005/00

A structural concept of a vertical component isolation system for fast reactors, assuming a building adopting a horizontal base isolation system, has been studied. In this concept, a reactor vessel and major primary components are suspended from a large common deck supported by vertical isolation devices consisting of large coned disk springs. We designed the isolation device, which could be achieved vertical isolation frequency of 1 Hz and damping ratio of 20 %. Full scale coned disk spring and damper performance tests were carried out to verify the validity of design equations. And a series of shaking table test using a 1/8 scale model was performed. The test results fit well the simulation analysis results, so the validity of the design methods was able to be verified. The prospect that the vertical component isolation system applied to the FBR plant could technically realize was obtained.

Journal Articles

Development of three-dimensional seismic isolation for power plant

Takahashi, Kenji; Inoue, Kazuhiko; Kato, Asao*; Morishita, Masaki; Fujita, Takafumi*

Proceedings of 9th World Seminar on Seismic Isolation, Energy Dissipation and Active Vibration Control of Structures (CD-ROM), p.177 - 184, 2005/00

We carried out reflection seismic and multi-offset VSP surveys at JNC Shobasama-site to develop the investigation technique in the granite area, and evaluated the applicability of these geophysical methods. As the result of this study, we consider that (1) It is possible to infer the existence of the lower angle fracture zone in the granite by reflection seismic survey and (1) Multi-offset VSP supplements the result of reflection seismic survey and it is possible to infer the distribution of the fracture zone in deeper area in the granite.

JAEA Reports

Study on Advanced Structural Design for Commercialized Fast Breeder Reactors

Morishita, Masaki; Kitamura, Seiji; Takahashi, Kenji; Inoue, Kazuhiko; Kida, Masanori; Moro, Satoshi*; Kato, Asao*; Fushimi, Minoru*

JNC-TY9400 2004-028, 921 Pages, 2004/11

Japan Nuclear Cycle Development Institute (JNC) and Japan Atomic Power Company (JAPC) launched joint research programs on structural design and three-dimensional seismic isolation technologies, as part of the supporting R&D activities for the feasibility studies on commercialized fast breeder reactor cycle systems. A research project by JAPC under the auspices of the Ministry of Economy, Trade, and Industry (METI) with technical support by JNC is included in this joint study. This report contains the results of the research on the structural design technology. The research scope was identified as (1) Study on Developing Program, (2) Study on 3-dimentional Entire Building Base Isolation System, and (3) Study on Vertical Isolation System for Main Equipment, and the results of this year's studies are summarized as follows. (1) Study on Developing Program -Performance Requirements for 3-dimensional Isolation Devices "The behavior of a three-dimensional isolated reactor building" and "amenity under the strong wind load" were studied in order to set up performance requirements for the three-dimensional isolation system. Consequently, it was proved for the former subject that the structure of horizontal base-dimensional isolated building was applicable to 3-D isolated building and for the latter that amenity of the operator in the 3-D isolated reactor building is not affected under the strong wind. -Development Targets and Schedules for Three-dimensional Isolation Deviece In order to select the development candidate of the three dimensional isolation devices, "evaluation items and criteria" and "technical guideline on seismic three-dimensional isolation system" were studied. For the former subject, detailed requirements to the component in the reactor building were studied based on the 2002 fiscal year result and embodied.(2) Study on 3-dimentional Entire Building Base Isolation System -The 3 system concepts nominated on 2001, "Hydraulic system", "Fiber reinforced air sp

JAEA Reports

Study on Advanced Structural Design for Commercialized Fast Breeder Reactors

Morishita, Masaki; Aoto, Kazumi; Kasahara, Naoto; Asayama, Tai; Inoue, Kazuhiko*; Shibamoto, Hiroshi*; Tanaka, Yoshihiko*

JNC-TY9400 2004-025, 984 Pages, 2004/08

JNC-TY9400-2004-025.pdf:159.61MB

Japan Nuclear Cycle Development Institute (JNC) and Japan Atomic Power Company(JAPC) launched joint research programs on structural design and three-dimensional seismic isolation technologies, as part of the supporting R&D activities for the feasibility studies on commerdalized fast breeder reactor cycle systems. A research project by JAPC under the auspices of the Ministry of Economy, Trade, and Industry (METI) with technical support by JNC is included in this joint study, This report contains the results of the research on the structural design technology. The research scope was identified as (1) FDS(FBR Design Standard), (2) Standardization of new material, and (3)System Based Code for Integrity, and the results of this year's studies are summarized as follows. (1)FDS (FBR Design Standard) * As for failure criteria, ratcheting-fatigue tests were continued. Applicability of rational settling method on creep design regime was evaluated and evaluation method of primary stress was studied. * As for a guideline on inelastic analysis for design, development of conservative detail modle (CRIEPI model for design) is underway. Loading history effect was evaluated through analysis. Conservative evaluation method of creep-fatigue damage coped with inelastic analysis was also developed. Aiming for verification of the guidline, structure model test simulated sodium surface level of reactor vessel is continuing. Policy and items of the guideline were studied. * As for a guideline on thermal loads modeling for design, provisions of the guideline on rational settling method of thermal striping loads were discussed. Screening method to grasp severe thermal load and parts in higher stress was developed. (2)Standardization of new material * As for candidate 12-chromium stainless steel (added tungsten, non-added tungsten), that is expected to improve strength of components of commercialized fast reactor, short and medium-term strength tests (including long-term aged test piece), ob

Journal Articles

Acceleration of 1 MeV, 100 mA class H$$^{-}$$ ion beams in a proof-of-principle accelerator for ITER

Inoue, Takashi; Taniguchi, Masaki; Dairaku, Masayuki; Hanada, Masaya; Kashiwagi, Mieko; Morishita, Takatoshi; Watanabe, Kazuhiro; Imai, Tsuyoshi

Review of Scientific Instruments, 75(5), p.1819 - 1821, 2004/05

 Times Cited Count:11 Percentile:46.36(Instruments & Instrumentation)

The paper reports progress of proof-of-principle test of negative ion accelerator for ITER. The accelerator structure is immersed in vacuum, surrounded by a FRP insulator column as the vacuum boundary. So far, the beam energy has been limited due to poor voltage holding capability of the FRP insulator column. By lowering the electric field strength at the triple junction (interface of FRP insulator, metal flange and vacuum) with large stress ring installed inside the insulator column, high voltage of 1 MV was stably sustained for more than 2 hours. In the following beam test, acceleration of 900 keV, 100 mA H$$^{-}$$ ion beam was succeeded. Although the current was lower (70 mA) at 1 MeV, the beam of this level has been stably accelerated for 6 days, 130 shots in total (each pulse length: 1 s).

68 (Records 1-20 displayed on this page)