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Sample records for jaeri

  1. JAERI RERTR program

    Sato, M.

    1983-01-01

    In 1979, Japan Atomic Energy Research Institute (JAERI) has started a five year program for the utilization of reduced enrichment uranium fuel, in place of currently used highly enriched uranium fuel for the JAERI Research and Test Reactors (RERTR), such as the JRR-2 (10 MWt), the JRR-4 35 MWt), the JMTR(50 MWO and the JMTRC (100 Wt, nuclear mockup of the JMTR), for contributing to the reduction of proliferation concerns. In order to assess the feasibility of converting the JAERI reactors to use of fuel with reduced enrichment uranium, ANL and JAERI have embarked on a joint study program since January 1980. This document provides outlines of the JAERI RERTR Program and of the ANL-JAERI Joint Study, and main results of JAERI's Phase A report which was made under the joint study

  2. Citation analysis in JAERI

    Nakamoto, Hideshiro; Shimizu, Takehiro.

    1982-01-01

    For purposes of the acquisition strategy the citation statistics were investigated on the articles which were published by JAERI staff in 1976, '77 and '78. The citations of 14,769 listed in the off-prints of 1,300 were analized by types of Literature, publication year, scattering, and so on. The results show that the occupation of technical reports increased and the lifetime became longer compared with the results of fifteen years ago. The journal ranking list is the important material for the acquisition of journals in our library. (author)

  3. Modular programming method at JAERI

    Asai, Kiyoshi; Katsuragi, Satoru

    1982-02-01

    In this report the histories, concepts and a method for the construction and maintenance of nuclear code systems of Japan Atomic Energy Research Institute (JAERI) are presented. The method is mainly consisted of novel computer features. The development process of the features and experiences with them which required many man-months and efforts of scientists and engineers of JAERI and a computer manufacturer are also described. One of the features is a file handling program named datapool. The program is being used in code systems which are under development at JAERI. The others are computer features such as dynamic linking, reentrant coding of Fortran programs, interactive programming facility, document editor, quick system output viewer and editor, flexible man-machine interactive Fortran executor, and selective use of time-sharing or batch oriented computer in an interactive porgramming environment. In 1980 JAERI has replaced its two old computer systems by three FACOM M-200 computer systems and they have such features as mentioned above. Since 1981 most code systems, or even big single codes can be changed to modular code systems even if the developers or users of the systems will not recognize the fact that they are using modular code systems. The purpose of this report is to describe our methodology of modular programming from aspects of computer features and some of their applications to nuclear codes to get sympathetic understanding of it from persons of organizations who are concerned with the effective use of computers, especially, in nuclear research fields. (author)

  4. JAERI tandem annual report, 1982

    Harada, Kichinosuke; Maruyama, Michio; Ozawa, Kunio; Shikazono, Naomoto; Tamura, Tsutomu; Tanaka, Shigeya

    1983-06-01

    This annual report describes research activities which have been performed with JAERI tandem accelerator from September 1, 1981 to March 31, 1983. Summary reports of 38 papers, publications, personnel and a list of co-operative researches with universities are contained. (author)

  5. JAERI Tandem annual report 1983

    Harada, Kichinosuke; Maruyama, Michio; Okashita, Hiroshi; Ozawa, Kunio; Shikazono, Naomoto; Tanaka, Shigeya

    1984-07-01

    This annual report describes research activities which have been performed with JAERI tandem accelerator from April 1, 1983 to March 31, 1984. Summary reports of 32 papers, publications, personnel and a list of co-operative reserches with universities are contained. (author)

  6. JAERI's activities in JCO accident

    2000-09-01

    The Japan Atomic Energy Research Institute (JAERI) was actively involved in a variety of technical supports and cooperative activities, such as advice on terminating the criticality condition, contamination checks of the residents and consultation services for the residents, as emergency response actions to the criticality accident at the uranium processing facility operated by the JCO Co. Ltd., which occurred on September 30, 1999. These activities were carried out in collaborative ways by the JAERI staff from the Tokai Research Establishment, Naka Fusion Research Establishment, Oarai Research Establishment, and Headquarter Office in Tokyo. As well, the JAERI was engaged in the post-accident activities such as identification of accident causes, analyses of the criticality accident, and dose assessment of exposed residents, to support the Headquarter for Accident Countermeasures of the Science and Technology Agency (STA), the Accident Investigation Committee and the Health Control Committee of the Nuclear Safety Commission of Japan (NSC). This report compiles the activities, that the JAERI has conducted to date, including the discussions on measures for terminating the criticality condition, evaluation of the fission number, radiation monitoring in the environment, dose assessment, analyses of criticality dynamics. (author)

  7. Manual on JSSL (JAERI scientific subroutine library)

    Fujimura, Toichiro; Nishida, Takahiko; Asai, Kiyoshi

    1979-11-01

    A manual on the revised version of JAERI scientific subroutine library is presented. The library is a collection of subroutines developed or modified in JAERI. They are classified into fifteen fields. It is subject to further extension in the future, since there are some fields still insufficient for scientific calculations in the present library. (author)

  8. Manual on JSSL (JAERI scientific subroutine library)

    Fujimura, Toichiro; Nishida, Takahiko; Asai, Kiyoshi

    1977-05-01

    A manual on the revised JAERI scientific subroutine library is presented. The library is a collection of subroutines developed or modified in JAERI which complements the library installed for FACOM 230-75 computer. It is subject to further extension in the future, since the present one is still insufficient for scientific calculations. (auth.)

  9. Status of JAERI tandem accelerator

    Yoshida, Tadashi; Kanda, Susumu; Takeuchi, Suehiro [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] (and others)

    2001-02-01

    JAERI Tandem Accelerator had been operated approximately 230 days in fiscal year of 1999. Meanwhile, we had three times of maintenance period with vent. Total operation-times were 5273 hours. We could not carry out the experiment using rare gas, due to malfunction of the RF power supply for the ECR ion source. The type of the RF power supply is peculiar and it is impossible to get spare parts for repair. We are now investigating the backup RF power supply. The power supply for the magnet became unstable due to degradation of insulation in the shunt resistance, which is used for feedback stabilization. Stability was recovered after cleaning. The acrylic resin shaft was cracked. This cracks have a potential for severe accidents. So far bearing of the shaft has no problem. The reason of cracks may be self-destruction by charge accumulation in the shaft. JAERI Tandem Accelerator is approximately 20 years old. There appear requirements on the higher ion currents for additional ion species. Therefore, authors are investigating cost effective improvement plans of RFQ (Radio Frequency Quadra-pole) and IH type accelerator based on KEK (High Energy Accelerator Research Organization) R and D. As a whole, maintenance services for the control system are increasing due to some changes of computer programs. There are some difficulties to keep skilled personnel for facilities operation. Authors are gradually increasing hired personnel with contract from 1993. However, loads for JAERI permanent staffs are still heavy. It takes much longer time to educate skilled persons especially for safety. (Y. Tanaka)

  10. Neutron Science Project at JAERI

    Oyama, Yukio

    1998-01-01

    Japan Atomic Energy Research Institute, JAERI, is proposing the Neutron Science Project which aims at bringing about scientific and technological innovation in the fields of basic science and nuclear technology for the 21st century, using high intense spallation neutron source. The research areas to be promoted by the project are neutron structural biology, material science, nuclear physics and various technology developments for accelerator-driven transmutation of long-lived radionuclides which are associated with nuclear power generation. JAERI has been carrying out a R and D program for the partitioning and transmutation with the intention to solve the problem of nuclear fuel cycle backend. The accelerator-driven transmutation study is also covered with this program. In the present stage of the project, a conceptual design is being prepared for a research complex utilizing spallation neutrons, including a high intensity pulsed and steady spallation neutron source with 1.5 GeV and 8 MW superconducting proton linac. The idea and facility plan of the project is described, including the status of technological development of the accelerator, target and facilities. (author)

  11. Neutron Science Project at JAERI

    Oyama, Yukio [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1998-03-01

    Japan Atomic Energy Research Institute, JAERI, is proposing the Neutron Science Project which aims at bringing about scientific and technological innovation in the fields of basic science and nuclear technology for the 21st century, using high intense spallation neutron source. The research areas to be promoted by the project are neutron structural biology, material science, nuclear physics and various technology developments for accelerator-driven transmutation of long-lived radionuclides which are associated with nuclear power generation. JAERI has been carrying out a R and D program for the partitioning and transmutation with the intention to solve the problem of nuclear fuel cycle backend. The accelerator-driven transmutation study is also covered with this program. In the present stage of the project, a conceptual design is being prepared for a research complex utilizing spallation neutrons, including a high intensity pulsed and steady spallation neutron source with 1.5 GeV and 8 MW superconducting proton linac. The idea and facility plan of the project is described, including the status of technological development of the accelerator, target and facilities. (author)

  12. Transactinide nuclear chemistry at JAERI

    Nagame, Y.; Haba, H.; Tsukada, K.

    2002-01-01

    Nuclear chemistry study of trans actinide elements in Japan is currently being in progress at JAERI (Japan Atomic Energy Research Institute). We have developed new experimental apparatuses: a beam-line safety system for the usage of the gas-jet coupled radioactive 248 Cm target chamber, a rotating wheel catcher apparatus for the measurement of α and spontaneous fission decay of the transactinides, MANON (Measurement system for Alpha particles and spontaneous fission events ON line), and an automated rapid chemical separation apparatus based on the high performance liquid chromatography, AIDA (Automated Ion exchange separation system coupled with the Detection apparatus for Alpha spectroscopy). The transactinide nuclei, 261 Rf and 262 Db, have been successfully produced via the reactions of 248 Cm( 18 O,5n) and 248 Cm( 19 F,5n), respectively, and the excitation functions for each reaction have been measured to evaluate the optimum irradiation condition for the production of these nuclei. The maximum cross sections in each reaction were 13 nb at the 18 O beam energy of 94-MeV and 1.5 Nb at the 103-MeV 19 F beam energy. On-line ion exchange experiments of Rf together with the lighter homologues Zr and Hf in the HCl, HNO 3 and HF solutions with AIDA have been carried out, and the results clearly show that the behavior of Rf is typical of the group-4 element. Relativistic molecular orbital calculations of the chloride and nitrate complexes of tetravalent Rf are also being performed to gain an understanding of the complex chemistry. Prospects and some recent experimental results for the nuclear chemistry study of the transactinide elements at JAERI are discussed. (author)

  13. JAERI 20 MV tandem accelerator

    Tsukada, Kineo; Harada, Kichinosuke

    1977-01-01

    Accelerators have been developed as the experimental apparatuses for the studies on nuclei and elementary particles. One direction of the development is the acceleration of protons and electrons to more and more high energy, and another direction is the acceleration of heavy ions up to uranium to several MeV up to several hundreds MeV. However recently, accelerators are used as the useful tools for the studies in wider fields. There are electrostatic acceleration and high frequency acceleration in ion acceleration, and at present, super-large accelerators are high frequency acceleration type. In Japan Atomic Energy Research Institute, it was decided in 1975 to construct an electrostatic accelerator of tandem type in order to accelerate heavy ions. In case of the electrostatic acceleration, the construction is relatively simple, the acceleration of heavy ions is easy, the property of the ion beam is very good, and the energy is stable. Especially, the tandem type is convenient for obtaining high energy. The tandem accelerator of 20 MV terminal voltage was ordered from the National Electrostatics Corp., USA, and is expected to be completed in 1978. The significance of heavy ion acceleration in the development and research of atomic energy, tandem van de Graaff accelerators, the JAERI 20MV tandem accelerator, and the research project with this accelerator are described. (Kako, I.)

  14. Manual for JSSL (JAERI Scientific Subroutine Library)

    Fujimura, Toichiro; Tsutsui, Tsuneo

    1991-09-01

    JSSL (JAERI Scientific Subroutine Library) is a library of scientific subroutines developed or modified in JAERI. They are classified into sixteen fields (Special Functions, Linear Problems, Eigenvalue and Eigenvector Problems, Non Linear Problems, Mathematical Programming, Extreme Value Problems, Transformations, Functional Approximation Methods, Numerical Differential and Integral Methods, Numerical Differential and Integral Equations, Statistical Functions, Physical Problems, I/O Routines, Plotter Routines, Computer System Functions and Others). This report is the user manual for the revised version of JSSL which involves evaluated subroutines selected from the previous compilation of JSSL, applied in almost all the fields. (author)

  15. Manual for JSSL (JAERI scientific subroutine library)

    Inoue, Shuji; Fujimura, Toichiro; Tsutsui, Tsuneo; Nishida, Takahiko

    1982-09-01

    A manual on revised version of JAERI scientific subroutine library, which is a collection of scientific subroutines developed or modified in JAERI. They are classified into fifteen fields (Special Functions, Linear Problems, Eigenvalue and Eigen vector Problems, Non linear Problems, Mathematical Programming, Extreme Value Problems, Transformations, Functional Approximation Methods, Numerical Differential and Integral Methods, Numerical Differential and Integral Equations, Statistical Functions, Physical Problems, I/O Routines, Plotter Routines, Computer System Functions and Others). Main expansion of this version is in the fields of mathematical programming and statistical functions. The present library may be said to be a comprehensive compilation of scientific subroutines covering almost all the important fields. (author)

  16. Control system for JAERI Free Electron Laser

    Sugimoto, Masayoshi

    1992-01-01

    A control system comprising of the personal computers network and the CAMAC stations for the JAERI Free Electron Laser is designed and is in the development stage. It controls the equipment and analyzes the electron and optical beam experiments. The concept and the prototype of the control system are described. (author)

  17. Commissioning of the JAERI free electron laser

    Minehara, E.J.; Nagai, R.; Sawamura, M.

    1993-01-01

    We have developed, and constructed a prototype for a quasi-cw, and high-average power free electron laser driven by a 15MeV superconducting rf linac at Tokai, JAERI. In designing a high power FEL, there are many available design options to generate the required power output. By applying the superconducting rf linac driver, some of the options relating to the FEL itself may be relaxed by transferring design difficulties to the driver. Because wall losses become minimal in the superconducting accelerator cavity, very long pulse or quasi-cw, and resultant high average power may be readily attained at the JAERI superconducting rf linac FEL. In 1992 Japanese fiscal year, we have successfully demonstrated better cryogenic (stand-by loss<3.5W at 4.5K) and accelerating fields' performances (Eacc=7-9.4MV/m and Q=1-2x10+9) of four JAERI superconducting accelerator modules, and installed them in the FEL accelerator vault. In 1993, Optical resonators and beam transport systems, which have been already assembled, are now under commissioning. A description and the latest results of the JAERI super-conducting rf linac FEL will be discussed in comparison with a normal-conducting one, and reported in the symposium. (author)

  18. Development of superconducting cavities at JAERI

    Ouchi, N.

    2001-01-01

    Development of superconducting (SC) cavities is continued for the high intensity proton accelerator in JAERI. In FY-1999, we carried out R and D work; (1) 2nd vertical test of β=0.886 single-cell cavity, (2) vertical test for observation of Q-disease without heat treatment after electropolishing, (3) vertical test of β=0.5 5-cell cavity, (4) pretuning, surface treatment and vertical test of β=0.886 5-cell cavity, (5) pulsed operation of β=0.886 single-cell cavity in the vertical test to confirm the validity of a new model calculation. This paper describes the present status of the R and D work for the SC cavities in JAERI. (author)

  19. LOCA and RIA studies at JAERI

    Sugiyama, Tomoyuki; Nagase, Fumihisa; Nakamura, Jinichi; Fuketa, Toyoshi

    2004-01-01

    To provide a data base for the regulatory guide of light water reactors, behavior of reactor fuels during off-normal and postulated accident conditions such as loss-of-coolant accident (LOCA) and reactivity-initiated accident (RIA) is being studied at the Japan Atomic Energy Research Institute (JAERI). The LOCA program consists of integral thermal shock tests and other separate tests for oxidation rate and mechanical property of fuel claddings. Prior to the tests on irradiated claddings, the tests have been conducted on non-irradiated claddings to examine separate effects of corrosion and hydrogen absorption during reactor operation. The tests on irradiated claddings have recently been started and results have been obtained. As for an RIA study, a series of experiments with high burnup fuel rods is being performed by using pulse irradiation capability of the NSRR. This paper presents recent results obtained from the LOCA and RIA studies at JAERI. (Author)

  20. JAERI TIARA annual report vol. 2 (1992)

    Ishigaki, Isao; Tanaka, Ryuichi; Nashiyama, Isamu; Naramoto, Hirosi; Omichi, Hideki; Toraishi, Akio; Watanabe, Hiromasa; Watanabe, Hiroshi

    1993-12-01

    This annual report describes research activities which have been performed with the JAERI TIARA (Takasaki Ion Accelerators for Advanced Radiation Application) facilities from April 1, 1992 to March 31, 1993. Summary reports of 60 papers and brief descriptions on status of TIARA in the period are contained. A list of publications, the type of research collaborations and organization of TIARA are also given as appendices. (author)

  1. The present status of JAERI OCTOPUS

    Yokota, Watalu

    1992-01-01

    As the ECR ion source of the JAERI AVF Cyclotron, OCTOPUS was installed. An experimental operation was conducted to increase the capability of generating multi-charged ions and to ameliorate the efficiency of beam transport to the cyclotron. In this paper, the brief description of OCTOPUS is given. And the difference of ion generation characteristics depending on the position of the main gas introduction, and the result of emittance measurement are reported. (J.P.N.)

  2. Laser isotope separation studies in JAERI

    Arisawa, Takashi; Shiba, Koreyuki

    1986-01-01

    For uranium enrichment, Japan Atomic Energy Research Institute (JAERI) has been studying atomic vapor laser isotope separation since 1976, in addition to such separation methods as gas diffusion, chemical exchange and gas-dynamic techniques. Studies carried out to date in JAERI is briefly summarized in the first part of the report. Then, some major separation techniques which have been studied in JAERI are outlined, and typical results obtained are presented. A large part is devoted to the multiple-photon photoionization technique, which is commonly known as the atomic laser isotope separation method for uranium enrichment. It has such advantages as 1) very high spectral selectivity for the relevant isotope and 2) highly improved photoionizing effect by means of two- and three-step resonance photoionization processes. Here, the atomic laser isotope separation method is discussed in detail with respect to the evaporation process, energy levels, photoionization, selectivity, photoionization schemes, ion recovery, separation in macroscopic amounts, and separation of trace amounts of isotopes. Typical observed and claculated results related to these subjects are shown. In addition, the report briefly describes some other separation processes including laser induced chemical reaction, multiple photo-dissociation, multiple-photo excitation and UV dissociation, laser induced thermal diffusion, and laser centrifugation. (Nogami, K.)

  3. Development of seismic PSA methodology at JAERI

    Muramatsu, K.; Ebisawa, K.; Matsumoto, K.; Oikawa, T.; Kondo, M.

    1995-01-01

    The Japan Atomic Energy Research Institute (JAERI) is developing a methodology for seismic probabilistic safety assessment (PSA) of nuclear power plants, aiming at providing a set of procedures, computer codes and data suitable for performing seismic PSA in Japan. In order to demonstrate the usefulness of JAERI's methodology and to obtain better understanding on the controlling factors of the results of seismic PSAs, a seismic PSA for a BWR is in progress. In the course of this PSA, various improvements were made on the methodology. In the area of the hazard analysis, the application of the current method to the model plant site is being carried out. In the area of response analysis, the response factor method was modified to consider the non-linear response effect of the building. As for the capacity evaluation of components, since capacity data for PSA in Japan are very scarce, capacities of selected components used in Japan were evaluated. In the systems analysis, the improvement of the SECOM2 code was made to perform importance analysis and sensitivity analysis for the effect of correlation of responses and correlation of capacities. This paper summarizes the recent progress of the seismic PSA research at JAERI with emphasis on the evaluation of component capacity and the methodology improvement of systems reliability analysis. (author)

  4. Technical publications by JAERI staff in 1997, vol. 31

    1998-06-01

    This list contains 998 references published as JAERI technical reports and selected from JAERI personnel's paper in journals and other publications in 1997. A bibliographic description for each entry consists of title, language, author(s) and source. While JAERI technical reports are sorted by report number, papers-in-journals are arranged by the first author. The personal author index, corporate author index and report number index are included. (author). 998 refs

  5. Technical publications by JAERI staff in 1998, vol. 32

    1999-06-01

    This list contains 1074 references of JAERI technical reports and JAERI personnel's papers in journals and other publications in 1998. A bibliographic description for each entry consists of title, language, author(s) and source. While JAERI technical reports are sorted by report number, papers-in-journals are arranged by the first author. The personal author index, corporate author index and report number index are included. (author). 1074 refs

  6. Technical publications by JAERI staff in 1999, vol. 33

    2000-06-01

    This list contains 1399 references of JAERI technical reports and JAERI personnel's papers in journals and other publications in 1999. A bibliographic description for each entry consists of title, language, author(s) and source. While JAERI technical reports are sorted by report number, papers-in-journals are arranged by the first author. The personal author index, corporate author index and report number index are included. (author)

  7. Technical publications by JAERI staff in 2000, vol. 34

    2001-04-01

    This list contains 830 references of JAERI technical reports and JAERI personnel's papers in journals and other publications in 2000. A bibliographic description for each entry consists of title, language, author(s) and source. While JAERI technical reports are sorted by report number, papers-in-journals are arranged by the first author. The personal author index, corporate author index and report number index are included. (author)

  8. JAERI-KEK joint project on high intensity proton accelerators

    Nagamiya, Shoji

    2000-01-01

    Japan Atomic Energy Research Institute (JAERI) and the High Energy Accelerator Organization (KEK) are promoting the joint project integrating both the Neutron Science Project (NSP) of JAERI and the Japan Hadron Facility Project (JHF) of KEK for comprehensive studies on basic science and technology using high-intensity proton accelerator. This paper describes the joint project prepared by the Joint Project Team of JAERI and KEK to construct accelerators and research facilities necessary both for the NSP and the JHF at the site of JAERI Tokai Establishment. (author)

  9. Technical publications by JAERI staff in 1992, vol. 26

    1993-05-01

    This list contains 969 references published as technical reports by JAERI and selected from JAERI personnel's papers in journals and other publications in 1992. A bibliographic description for each entry consists of title, carrier language, author(s) and source. The references fall into three groups. While JAERI report and JAERI-M report groups are sorted by report number, Papers-in-Journals group is arranged by the first author. The indexes are both by personal author and corporate entry. (author) 969 refs

  10. Technical publications by JAERI staff in 1991, Vol. 25

    1992-05-01

    This list contains 843 references published as technical reports by JAERI and selected from JAERI personnel's papers in journals and other publications in 1991. A bibliographic description for each entry consists of title, carrier language, author(s) and source. The references fall into three groups. While JAERI report and JAERI-M report groups are sorted by report number, Papers-in-Journals group is arranged by the first author. The indexes are both by personal author and corporate entry. (author) 843 refs

  11. Technical publications by JAERI staff in 1990, Vol. 24

    1991-05-01

    This list contains 752 references published as technical reports by JAERI and selected from JAERI personnel's papers in journals and other publications in 1990. A bibliographic description for each entry consists of title, carrier language, author(s) and source. The references fall into three groups. While JAERI report and JAERI-M report groups are sorted by report number, Papers-in-Journals group is arranged by the first author. The indexes are both by personal author and corporate entry. (author) 752 refs

  12. Technical publications by JAERI staff in 1989, Vol. 23

    1990-05-01

    This list contains 801 references published as technical reports by JAERI and selected from JAERI personnel's papers in journals and other publications in 1989. A bibliographic description for each entry consists of title, carrier language, author(s) and source. The references fall into three groups. While JAERI report and JAERI-M report groups are sorted by report number, Papers-in-Journals group is arranged by the first author. The indexes are both by personal author and corporate entry. (author) 801 refs

  13. Waste management for JAERI fusion reactors

    Tobita, K.; Nishio, S.; Konishi, S.; Jitsukawa, S.

    2004-01-01

    In the fusion reactor design study at Japan Atomic Energy Institute (JAERI), several waste management strategies were assessed. The assessed strategies are: (1) reinforced neutron shield to clear the massive ex-shielding components from regulatory control; (2) low aspect ratio tokamak to reduce the total waste; (3) reuse of liquid metal breeding material and neutron shield. Combining these strategies, the weight of disposal waste from a low aspect ratio reactor VECTOR is expected to be comparable with the metal radwaste from a light water reactor (∼4000 t)

  14. Selection of JAERI'S HTGR-GT concept

    Muto, Y.; Ishiyama, S.; Shiozawa, S.

    2001-01-01

    In JAERI, a feasibility study of HTGR-GT has been conducted as an assigned work from STA in Japan since January 1996. So far, the conceptual or preliminary designs of 600, 400 and 300 MW(t) power plants have been completed. The block type core and pebble-bed core have been selected in 600 MW(t) and 400/300 MW(t), respectively. The gas-turbine system adopts a horizontal single shaft rotor and then the power conversion vessel is separated into a turbine vessel and a heat exchanger vessel. In this paper, the issues related to the selection of these concepts are technically discussed. (author)

  15. Development of EC technology in JAERI

    Sakamoto, Keishi; Takahashi, Koji; Kasugai, Atsushi; Hayashi, Kenichi; Ikeda, Yoshitaka; Kajiwara, Ken; Fujii, Tsuneyuki; Imai, Tsuyoshi; Kariya, Tsuyoshi; Mitsunaka, Yoshika

    2003-01-01

    Recent progress of electron cyclotron (EC) heating and current drive technologies in JAERI is reported. In 170 GHz gyrotron development, 0.9 MW/9.2 sec (efficiency: 43%), 0.5 MW/30 sec (46%), etc, have been demonstrated. As for 110 GHz gyrotron, 1 MW/5 sec and 1.2 MW/4.1 sec were obtained. Using four 110 GHz gyrotrons, a 3 MW power injection into JT- 60U plasma was carried out. In parallel, a launcher design and its development that includes neutron irradiation of the launcher components and a remote steering launcher are underway for ITER application. (authors)

  16. JAERI FEL applications in nuclear energy industries

    Minehara, Eisuke J.

    2005-01-01

    The JAERI FEL has first discovered the new FEL lasing of 255fs ultra fast pulse, 6-9% high efficiency, 1GW high peak power, a few kilowatts average power, and wide tunability of medium and far infrared wavelength regions at the same time. Using the new lasing and energy-recovery linac technology, we could extend a more powerful and more efficient free-electron laser (FEL) than 10kW and 25%, respectively, for nuclear energy industries, and others. In order to realize such a tunable, highly-efficient, high average power, high peak power and ultra-short pulse FEL, we need the efficient and powerful FEL driven by the JAERI compact, stand alone and zero boil-off super-conducting RF linac with an energy-recovery geometry. Our discussions on the FEL will cover the application of non-thermal peeling, cutting, and drilling to prevent cold-worked stress-corrosion cracking failures in nuclear energy and other heavy industries. (author)

  17. History of the JAERI linac facility for 33 years

    Ohkubo, Makio; Mizumoto, Motoharu; Nakajima, Yutaka; Mashiko, Katsuo

    1994-01-01

    The JAERI electron linear accelerator will be shutdown and disassembled at the end of 1993. At the JAERI, a prototype 20 MeV linac was constructed at 1960, and was used for the neutron time-of-flight experiments and for the isotope productions. An upgraded 120 MeV linac was constructed at 1972, and was used for many fields of research works until 1993. History of the JAERI Linac and the results of the works made using these facilities are reviewed, and also R/D on the accelerator engineering are described briefly. (author)

  18. JAERI/KEK target material program overview

    Kikuchi, Kenji; Kogawa, Hiroyuki; Sasa, Toshinobu

    2001-01-01

    Mercury target was designed for megawatt neutron scattering facility in JAERI/KEK spallation neutron source. The incident proton energy and current are 3 GeV and 333 μA, respectively: the total proton energy is 1 MW in short pulses at a frequency of 25 Hz. Under the guide rule the mercury target was designed: the maximum temperature of target window is 170degC and induced stresses for the type 316 stainless steel are within limits of design guide. In order to demonstrate ADS (Accelerator Driven Systems) transmutation critical and engineering facilities have been designed conceptually. In engineering facility lead-bismuth spallation target station is to be planned. Objective to build the facility is to demonstrate material irradiation. According to neutronics calculation irradiation damage of the target vessel window will be 5 dpa per year. (author)

  19. JAERI TIARA annual report vol. 1 (1992)

    Ishigaki, Isao; Nashiyama, Isamu; Naramoto, Hiroshi; Omichi, Hideki; Tanaka, Ryuichi; Watanabe, Hiromasa; Watanabe, Hiroshi

    1993-03-01

    This annual report describes research activities which have been performed with the JAERI TIARA (Takasaki Ion Accelerators for Advanced Radiation Application) facilities from April 1, 1991 to March 31, 1992, and also gives an outline of the ion accelerators and surrounding apparatus which have been constructed and prepared for various experiments. As well as an outline of the characteristics of AVF cyclotron, 3 MV tandem electrostatic accelerator and other ones, included are 25 summary reports on preparation of experimental apparatus and on the preliminary results of experimental studies using the 3 MV tandem accelerator in the different research fields of beam technology, materials for space environment and nuclear fusion reactor, organic and inorganic functional materials, biology, medicine, radiation chemistry, radioisotope production and nuclear chemistry. Lists of publication, staff of TIARA and cooperated researchers are also given. (author)

  20. Development of radioisotope production in JAERI

    Yamabayashi, H.; Kato, H.; Umezawa, H.

    1992-01-01

    Since 1962, we have been developing methods and technology for producing a wide variety of processed radioisotopes and sealed radiation sources by using the JAERI's reactors, JRR-2, JRR-3, JRR-4 and JMTR, and providing the products to domestic users. At present, 29 nuclides and 31 products are on our list of processed radioisotopes. Some of those isotopes such as P-32, S-35, Cr-51 and short-lived nuclides are being produced regularly for distribution, but most of the rest are produced upon request. The radiation sources of Co-60 needles and Ir-192 pellets for industrial use and Gd-153 pellet, 7 kinds of Ir-192 and Au-198 grain for medical applications are produced and distributed routinely. (author)

  1. Overview of severe accident research at JAERI

    Sugimoto, Jun

    1999-01-01

    Severe accident research at JAERI aims at the confirmation of the safety margin, the quantification of the associated risk, and the evaluation of the effectiveness of the accident management measures of the nuclear power reactors, in accordance with the government five-year nuclear safety research program. JAERI has been conducting a wide range of severe accident research activities both in experiment and analysis, such as melt coolant interactions, fission product behaviors in coolant system, containment integrity and assessment of accident management measures. Molten core/coolant interaction and in-vessel molten coolability have been investigated in ALPHA Program. MUSE experiments in ALPHA Program has been conducted for the precise energy measurement due to steam explosion in melt jet and stratified geometries. In VEGA Program, which aims at FP release from irradiated fuels at high temperature and high pressure under various atmospheric conditions, the facility construction is almost completed. In WIND Program the revaporization of aerosols due to decay heating and also the integrity of the piping from this heat source are being investigated. Code development activities are in progress for an integrated source term analysis with THALES, fission product behaviors with ART, steam explosion with JASMINE, and in-vessel debris behaviors with CAMP. The experimental analyses and reactor application have made progress by participating international standard problem and code comparison exercises, along with the use of introduced codes, such as SCDAP/RELAP5 and MELCOR. The outcome of the severe accident research will be utilized for the evaluation of more reliable severe accident scenarios, detailed implementation of the accident management measures, and also for the future reactor development, basically through the sophisticated use of verified analytical tools. (author)

  2. Current status of HTTR project at JAERI

    Saito, Shinzo; Sudo, Yukio; Tanaka, Toshiyuki; Baba, Osamu

    1992-01-01

    The HTTR is a high temperature gas cooled test reactor with thermal output of 30 MW, outlet coolant temperatures of 850degC at rated operation and 950degC at high temperature test operation and primary coolant pressure of 4 MPa. The HTTR consists of a reactor pressure vessel with a prismatic core in it, a primary cooling loop with an intermediate helium-helium heat exchanger and a pressurized water cooler in parallel, an auxiliary cooling system, a reactor vessel cooling system and related components. The HTTR is utilized for establishing and upgrading the technology bases for advanced HTGRs including irradiation tests for fuels and materials, safety demonstration tests for HTGRs and nuclear heat application and for carrying out various kinds of innovative basic researches on high temperature technologies. Since 1969, the JAERI has carried out research and development works on block type fuel, high temperature materials, high temperature in-core instrumentations, high temperature components, reactor physics, heat transfer and fluid dynamics, plate-out of fission products etc., in order to construct the HTTR which can supply high temperature coolant of 950degC to the outside of the pressure vessel for the nuclear heat application, for the first time in the world. In November 1990, the installation permit was issued by the Government through about 20 month safety review by the Science and Technology Agency and Nuclear Safety Commission. The construction of the HTTR facility was initiated on the site in the Oarai Research Establishment, JAERI in March 1991. The excavation of ground is now finished at the HTTR site. It will take about six years for the completion of the HTTR facility and the first criticality will be attained in 1996. (author)

  3. Studies in precise neutron optics at JAERI

    Tomimitsu, Hiroshi

    1994-01-01

    Studies in the field of so-called 'Precise Neutron Optics' at JAERI were reported, since the beginning of 1970. It started with the photographic detection of the 'Pendellusung Fringes' in a wedge-shaped Si crystal, promoted by Prof.K.Kohra. Neutron diffraction topography was also tried and used for the 'direct' observation of the substructure in a Cu-5%Ge single crystal, carried out by the present author. So-called 'VSANS' (Very Small Angle Neutron Scattering) was also tried, with the angular resolution better than 0.1 sec. of arc, for the structural observation of several kinds of 'amorphous' materials, such as neutron-irradiated silica glasses, Pb-containing glasses and several ribbon-shaped amorphous alloys, carried out by Dr.K.Doi. Recently with the co-operation with Prof.S.Kikuta's group, some interferometric experiments were tried, such as the detection of the double-refraction phenomenon of the neutron in the magnetic materials, carried out by Dr.S.Nakatani. The apparatus for precise neutron optics and topography (PNO) was constructed at the JRR-3M in JAERI in 1992, which was just properly made for the studies in the present thema. With the PNO, the characterization of Ni-Ti multilayer mirror for the interferometer with the cold/ ultra-cold neutrons was carried out, the results being reported in the other article of this symposium by Dr.H.Funahashi. Through the test use of the PNO with the neutron interferometry, carried out by Dr.Y.Hasegawa, it was revealed that the PNO is the best facility in the world for the neutron interferometry; with the datas of the count ratio upto 20 cps and the contrast more than 40%. Dr.K.Aizawa is now refining the VSANS-technique on the PNO, for the precise observation of the precipitation behaviour of high density small particles such as metatic alloy-system. (author)

  4. Concurrent control system for the JAERI tandem accelerator

    Hanashima, Susumu; Shozi, Tokio; Shiozaki, Yasuo; Saito, Motoi; Oogane, Yasuo; Sekiguchi, Satoshi.

    1994-01-01

    A new control system for the JAERI tandem accelerator is constructed. The system utilizes concurrent processing technology with multiprocessor. Transputers are used both for central processor and I/O front end processors. (author)

  5. Annual report on neutron scattering studies in JAERI

    Sato, Masatoshi; Nishi, Masakazu; Fujishita, Hideshi; Iizumi, Masashi

    1982-07-01

    Neutron scattering studies carried out from September 1979 to August 1981 by Division of Physics, JAERI, and universities with JRR-2 and -3 neutron beam facilities are described: 61 summary reports, and a list of publications. (author)

  6. The ion source development for neutral injection heating at JAERI

    Shirakata, H.; Itoh, T.; Kondoh, U.; Matsuda, S.; Ohara, Y.; Ohga, T.; Shibata, T.; Sugawara, T.; Tanaka, S.

    1976-01-01

    The neutral beam research and development effort at JAERI has been mainly concentrated on design, construction and testing of ion sources needed for present and planned heating experiments. Fundamental characteristics of the ion sources developed are described

  7. Centralized environmental radiation monitoring system in JAERI

    Katagiri, H.; Kobalyashi, H.

    1993-01-01

    JAERI has continued the environmental radiation background survey and monitoring to ensure the safety of the peoples around the institute since one year before the first criticality of JRR-1 (Japan Research Reactor No.1) in August 1957. Air absorbed doses from β and γ radiation, α and β radioactivity in air and the radioactivities in environmental samples were the monitoring items. For the monitoring of β and γ radiation and α and β radioactivity in air, monitoring station and the centralized automatic environmental radiation monitoring system applying a computer were established as a new challenging monitoring system for nuclear facility, which was the first one not only in Japan but also in the would in 1960 and since then the system has been renewed two times (in 1973 and 1988) by introducing the latest technology in the fields of radiation detection and computer control at each stage. Present system renewed in 1988 was designed to prevent the interruption of monitoring due to computer troubles, communication troubles and power failures especially an instant voltage drop arisen from thunder by reflecting the experiences through the operation and maintenance of the former system. Dual telemeters whose power is constantly supplied via batteries (capable of 10 min monitoring after power failure) are equipped in the monitoring center to cope with telemeter troubles, which has operated successfully without any suspension being attributable to the power failures and telemeter troubles

  8. Progress report on neutron scattering at JAERI

    Morii, Yukio [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1998-10-01

    In the first half of fiscal year 1997, JRR-3M was operated for 97 days followed by a long term shut down for its annual maintenance. Three days were lost out of 100 scheduled operation days, due to a trouble in irradiation facility. Neutron scattering research activities at the JRR-3M have been extended from that of fiscal year 1996. In the Research Group for Quantum Condensed Matter System, experimental study under high pressures, low temperatures and high fields as well as coupling of these conditions were planned to find new quantum condensed matter systems. And, obtained experimental results were immediately provided to theorists for their investigations. In cooperation with new group, Research Group for Neutron Scattering of Strongly Correlated Electron Systems and Research Group for Neutron Scattering at Ultralow Temperatures were carrying neutron scattering experiments at JRR-3M. Research Group for Neutron Crystallography in Biology had opened a way for investigating biomatter neutron diffraction research with high experimental accuracy by growing a millimeter-class large single crystal. In fiscal year 1997, 39 research projects were conducted by these four groups and other staffs in JAERI, 27 projects collaborated with university researchers and 3 projects collaborated with private enterprises were also conducted as complementary researches. 2117 days of machine times were requested to use 8 neutron scattering instruments this year, which corresponded to 1.51 times larger than those planned at its beginning. (G.K.)

  9. Neutron scattering equipments in JAERI. Current status

    Hamaguchi, Yoshikazu; Minakawa, Nobuaki

    2003-01-01

    24 neutron scattering instruments are installed in the JRR-3M research reactor. Among them JAERI has 12 neutron scattering instruments. Those instruments are HRPD for high-resolution structural analysis, TAS-1 and TAS-2 for elastic and inelastic scattering and for magnetic scattering measurements by the polarized neutron, LTAS for elastic and inelastic scattering measurement at a low energy region, and for neutron device development, PNO for topography and for very small angle scattering measurement in a small Q range, NRG for neutron radiography, RESA for internal strain measurements, SANS for the molecule and semi-macroscopic magnetic structural analysis, BIX-2 and BIX-3 for the biological structural analysis research, and PGA for the research of prompt gamma-ray analysis. The university groups have 12 neutron scattering instruments. Since those instruments were installed at the period when JRR-3M was completed, about 10 years have passed. In order to match the old control systems with the progress of recent computer technologies, and peripheral equipment, numbers of instruments are being renewed. In the neutron guide hall of JRR-3M, the Ni mirror guide tube was replaced by a super mirror guide tube to increase neutron flux. The intensity of 2A flux was increased by a factor of about two. (J.P.N.)

  10. JAERI's activities on photon production data

    Shibata, Keiichi; Maekawa, Fujio; Niita, Koji

    1996-01-01

    Summarized are activities on photon production data at JAERI. The activities consists of evaluation of photon production data for JENDL Fusion File, benchmark tests of JENDL and FENDL-1 data, and calculation of photon production data in the framework of the Quantum Molecular Dynamics. The capture cross sections of 12 C and 16 O were evaluated for JENDL Fusion File by taking account of the direct radiative capture calculations obtained by A. Mengoni (ENEA). The presently evaluated data are in good agreement with the measurements of Igashira et al. in the keV region, describing the behaviour of p-wave capture which is in proportion to υ. Photon production data on Fe and Ni were updated for JENDL Fusion File by using a statistical-model calculations. According to the results of benchmark tests, the calculations with the updated data reproduce the integral measurements on gamma-ray heating. Benchmark tests of evaluated photon production data have been continued by analyzing the integral experimental performed at OKTAVIAN and FNS. The calculations with JENDL Fusion File are in good agreement with the integral measurements. Preliminary calculation of photon production data in the high energy region has been done in the framework of the Quantum Molecular Dynamics approach. The quasi-deuteron model was used to describe photon absorption in the low energy region. Above pion production threshold, pion production channels were included in the calculation. The neutron-proton bremsstrahlung obtained with the one-boson-exchange model was incorporated into QMD codes. (Abstract only)

  11. Centralized environmental radiation monitoring system in JAERI

    Katagiri, Hiroshi; Kobayashi, Hideo

    1993-03-01

    Japan Atomic Energy Research Institute (JAERI) has continued the radiation background survey and environmental radiation monitoring to ensure the safety of the residents around the Institute. For the monitoring of β and γ radiations and α and β radioactivities in air, the centralized automatic environmental radiation monitoring system (EMS) applying a computer with monitoring stations (MS) was established. The system has been renewed twice in 1973 and 1988. In 1962, a new concept emergency environmental γ-ray monitoring system (MP) was begun to construct and completed in 1965 independent of EMS. The first renewal of the EMS was carried out by focusing on the rapid and synthetic judgement and estimation of the environmental impacts caused by radiation and radioactive materials due to the operation of nuclear facilities by centralizing the data measured at MS, MP, a meteorological station, stack monitors and drainage monitoring stations under the control of computer. Present system renewed in 1988 was designed to prevent the interruption of monitoring due to computer troubles, communication troubles and power failures especially an instant voltage drop caused by thunder by reflecting the experiences through the operation and maintenance of the former system. Dual telemeters whose power is constantly supplied via batteries (capable of 10 min. monitoring after power failure) are equipped in the monitoring center to cope with telemeter troubles, which has operated successfully without any suspension being attributable to the power failures and telemeter troubles. (J.P.N.)

  12. Health physics in JAERI, no.28

    1986-09-01

    In the annual report No.28 (fiscal 1985) are described the activities of health physics including radioactive waste management in Tokai Research Establishment, Takasaki Radiation Chemistry Research Establishment and Oarai Research Establishment. There were no occupational exposure exceeding the maximum permissible dose and no release of radioactive gaseous and liquid waste beyond the release limit specified according to the regulations. In the environment there were observed no abnormal radioactivity due to facilities. Technology development and research; Technology developments were made as in the previous years for improving the techniques and methods in monitoring of individuals, facilities and environment, radiation measurement instrumentation and also in waste management and decontamination. The following works were made in the researches of radiation dosimetry, body radioactivity, airborne radioactivity and estimation of radiation dose due to low level waste disposal. For radiation dosimetry: portable apparatus for calibration of radioactive gas monitors, evaluation of β-ray depth dose distribution, and exposure analysis through an extended series of specific jobs at JRR-2. For body radioactivity: characteristic of JAERI phantom for an assessment of Pu in lung, transfer compartment in the internal dose evaluation method, and radiosensitivity of chromosomes of rabbit lymphocytes. For airborne radioactivity and estimation of radiation dose due to wastedisposal: sheltering effect of houses for radioactive effluent, tritium oxide permeability of membrance in protective appliances, conversion rate of low concentration tritium gas to tritiated water, computer code for calculation of radiation dose from very low-level radioactive waste disposal and safety demonstration tests of national disposal of very low-level radioactive solid waste. (J.P.N.)

  13. Development and operation of nuclear material accounting system of JAERI

    Obata, Takashi; Numata, Kazuyoshi; Namiki, Shinji; Yamauchi, Takahiro

    2003-01-01

    For the nuclear material accounting system, the mainframe computer had been used in Japan Atomic Energy Research Institute (JAERI). For the purpose of more flexible use and easy operation, the PC base accounting system has been developed since 1999, and operation started from October, 2002. This system consists of the server with the database software and the client PC with original application software. The functions of this system are the input and edit of data, the creation of inspection correspondence data, and creation of a report to the states. Furthermore, it is also possible to create the Web application which used accounting data on a user level by using the programming language. Now, this system is being specialized in JAERI, but it is during a plan to develop as a system which can be also used at other institutions and organization. In the paper, the outline and operating situation of the nuclear material accounting system of JAERI are presented. (author)

  14. Evaluation of nuclear knowledge management: An outcome in JAERI

    Yanagisawa, K.

    2006-01-01

    The author performed an ex post evaluation on the nuclear research of JAERI and revealed that the national funds invested in this field were 4 b$. With aid of NKM, it was revealed that the total outcome was 6 b$, where the creation of nuclear markets for electricity and nuclear facilities was the main stream. This implies that the cost benefit effect is 6 b$/4 b$ = 1.5 (>1). From this, it can be concluded that JAERI contributes not only to technological promotion of nuclear activity but also to the increase of gross domestic product (GDP). (author)

  15. Development and operation of the JAERI superconducting energy recovery linacs

    Minehara, Eisuke J.

    2006-02-01

    The Japan Atomic Energy Research Institute free-electron laser (JAERI FEL) group at Tokai, Ibaraki, Japan has successfully developed one of the most advanced and newest accelerator technologies named "superconducting energy recovery linacs (ERLs)" and some applications in near future using the ERLs. In the text, the current operation and high power JAERI ERL-FEL 10 kW upgrading program, ERL-light source design studies, prevention of the stainless-steel cold-worked stress-corrosion cracking failures and decommissioning of nuclear power plants in nuclear energy industries were reported and discussed briefly as a typical application of the ERL-FEL.

  16. JAERI contribution to the 19th IAEA Fusion Energy Conference

    2003-03-01

    This report compiles the contributed papers and presentation materials from JAERI to the 19th IAEA Fusion Energy Conference held at Lyon, France, from October 14th to 19th, 2002. The papers describe the recent progress in the experimental research in JT-60U and JFT-2M tokamaks, theoretical studies, fusion technology and R and D for ITER and fusion reactors. Total 32 papers consist of 1 overview talk, 14 oral and 17 poster presentations. Eight papers written by authors from other institutes and universities under collaboration with JAERI are also included. The 40 of the presented papers are indexed individually. (J.P.N.)

  17. Atomic and Molecular Data activities at NDC/JAERI

    Shirai, Toshizo

    2000-01-01

    The NDC/JAERI is a member of the international atomic and molecular (A+M) data center network for fusion, coordinated by the International Atomic Energy Agency. In this poster we introduce our Evaluated Atomic and Molecular Data Library (JEAMDL) developed in collaboration with the JAERI Research Committee on A+M Data and with researchers of ORNL and NIST under the US-Japan fusion cooperation program. JEAMDL comprises databases of collision cross section data and of spectroscopic data. We briefly summarize these two databases below. (author)

  18. A system of nuclear material accountancy in the JAERI

    Kase, Toshio; Nishizawa, Satoshi; Takahashi, Yoshindo

    1983-05-01

    Pursuant to the domestic law and regulations revised in 1978 as to be conformed to the requirements specified in the Safeguards Agreement under the Non-Proliferation Treaty (NPT), the JAERI's system of nuclear material accountancy has been effectively developed. The system of accountancy in the JAERI is based on the information treatment by the computer. The data of nuclear material are retained batchwisely together with their complicate history reflected the inventory changes and other transactions. The reports represented these data are prepared and submitted to the IAEA through the Government every month. The inspections are frequently conducted to the JAERI to verify the material appeared in the reports. Item counting, item identification and non-destructive assay technique are brought to the verification. In some cases, seals of the Government and the IAEA are applied to the nuclear material at the inspections, as their containment measures. The surveillance camera is also installed in the facility to look whole view of reactor room and spent fuel pond. In this paper, the general safeguards application and its corresponding accountancy system on JAERI's nuclear facility are described. (author)

  19. JAERI's activities in JCO accident

    NONE

    2000-09-01

    The Japan Atomic Energy Research Institute (JAERI) was actively involved in a variety of technical supports and cooperative activities, such as advice on terminating the criticality condition, contamination checks of the residents and consultation services for the residents, as emergency response actions to the criticality accident at the uranium processing facility operated by the JCO Co. Ltd., which occurred on September 30, 1999. These activities were carried out in collaborative ways by the JAERI staff from the Tokai Research Establishment, Naka Fusion Research Establishment, Oarai Research Establishment, and Headquarter Office in Tokyo. As well, the JAERI was engaged in the post-accident activities such as identification of accident causes, analyses of the criticality accident, and dose assessment of exposed residents, to support the Headquarter for Accident Countermeasures of the Science and Technology Agency (STA), the Accident Investigation Committee and the Health Control Committee of the Nuclear Safety Commission of Japan (NSC). This report compiles the activities, that the JAERI has conducted to date, including the discussions on measures for terminating the criticality condition, evaluation of the fission number, radiation monitoring in the environment, dose assessment, analyses of criticality dynamics. (author)

  20. Cable systems for experimental facilities in JAERI TANDEM ACCELERATOR BUILDING

    Tukihashi, Yoshihiro; Yoshida, Tadashi; Takekoshi, Eiko

    1979-03-01

    Measuring cable systems for experimental facilities in JAERI TANDEM ACCELERATOR BUILDING were completed recently. Measures are taken to prevent penetration of noises into the measuring systems. The cable systems are described in detail, including power supplies and grounding for the measuring systems. (author)

  1. Concurrent control system for the JAERI tandem accelerator

    Hanashima, S.; Shoji, T.; Horie, K.; Tsukihashi, Y.

    1992-01-01

    Concurrent processing with a multiprocessor system is introduced to the particle accelerator control system region. The control system is a good application in both logical and physical aspects. A renewal plan of the control system for the JAERI tandem accelerator is discussed. (author)

  2. Scaling of the optical parameters for the JAERI tandem accelerator

    Hanashima, S.; Minehara, E.

    1986-01-01

    A scaling rule of the beam optical parameters was adopted for computer-aided beam transport in the JAERI tandem accelerator. Tests have shown that the computer program can transport a specified beam in a short time using a reference parameter set. Problems of ion source control and accuracy of the optical devices are also discussed

  3. Proceedings of the 1st JAERI symposium on HTGR technologies

    1990-07-01

    This report was edited as the Proceedings of the 1st JAERI Symposium on HTGR Technologies, - Design, Licensing Requirements and Supporting Technologies -, collecting the 21 papers presented in the Symposium. The 19 of the presented papers are indexed individually. (J.P.N.)

  4. First results of beam generation test for JAERI AVF cyclotron

    Tachikawa, T.; Hayashi, Y.; Ishii, K.

    1992-01-01

    The performance of JAERI AVF cyclotron was investigated with several kinds of ions in the wide energy range. The 90 MeV protons of 10 μA intensity was successfully extracted for the first time by the model 930 cyclotron. The feature of beam chopping system is also presented. (author)

  5. Intercomparison of JAERI Torso Phantom lung sets

    Kramer, Gary H.; Hauck, Barry M.

    2000-01-01

    During the course of an IAEA sponsored In Vivo intercomparison using the JAERI phantom the Human Monitoring Laboratory was able to intercompare thirteen lung sets made by three suppliers. One set consisted of sliced lungs with planar inserts containing different radionuclides. The others consisted of whole lung sets with the activity homogeneously distributed throughout the tissue substitute material. Radionuclides in the study were: natural uranium, 3% enriched uranium, 241 Am, 238 Pu, 239 Pu, 152 Eu, and 232 Th Except for the 241 Am (59.5 keV) and occasionally one of the 232 Th (209 keV) photopeaks, the lung sets that had radioactivity homogeneously distributed throughout the tissue equivalent lung tissue material showed good agreement. The 241 Am lung set gave a counting efficiency that appeared 25% too high for all overlay plate configurations. This was observed by other participants. It exemplifies that the manufacture of tissue substitute lung sets is still something of a black art. Despite all precautions, this lung set is either inhomogeneous or has had the wrong activity added. Heterogeneity can lead to an error in the activity estimate of a factor of three if the activity was severely localised due to improper mixing. A factor of 1.25, which appears to be the discrepancy, could easily be explained in this way. It will not be known for some time, however, what the true reason is as the participants are still waiting for the destructive analysis of this lung set to determine the 'true' activity. The sliced lungs ( 241 Am, 152 Eu, and U-nat) manufactured by the Human Monitoring Laboratory are in excellent agreement with the other lung sets. The advantages of sliced lung sets and planar sources are manifold. Activity can be distributed in a known and reproducible manner to mimic either a homogeneous or heterogeneous distribution in the lung. Short lived radionuclides can be used. Cost is much less than purchasing or manufacturing lung sets that have the

  6. Development of superconducting pulsed poloidal coil in JAERI

    Shimamoto, S.; Okuno, K.; Ando, T.; Tsuji, H.

    1990-01-01

    In the Japan Atomic Energy Research Institute, (JAERI), development work on pulsed superconductors and coils started in 1979, aiming at the demonstration of the applicability of superconducting technologies to pulsed poloidal coils in a fusion reactor. Initially our effort was concentrated mainly on the development of pool-cooled large-current pulsed conductors. Over the past ten years, superconducting technology has made great progress and the forced-flow cooled coil has assumed great importance in the development work. Now the Demo Poloidal Coil Project is in progress in JAERI, and three large forced-flow cooled coils have so far been fabricated and tested. Many improvements have been achieved in ac-loss performance and mechanical characteristics. (author)

  7. Analysis of Doppler effect with JAERI-Fast set

    Takano, Hideki; Matsui, Yasushi.

    1977-07-01

    Temperature dependence of group cross sections in the JAERI-Fast set versions I, IR, II and IIR has been tested from the analysis of Doppler experiments performed with two different methods. One is Doppler reactivity measurement for the whole core of SEFOR assembly, and the other sample Doppler reactivity measurement for natural UO 2 in FCA assemblies V-1, V-2, VI-1 and VI-2, ZPR-6-7, ZPR-3-47, and ZPPR-2 and 3. Doppler effects were calculated with one- and two-dimensional diffusion 1-st order perturbation code DOPP2D. The results calculated with the JAERI-Fast set versions II and IIR are in good agreement with the experimental ones. In these calculation, resonance heterogeneity effect, stainless-stell buffer effect and plate heterogeneity effect are considered, and these effects contribute significantly to Doppler effect. (auth.)

  8. Production of radioisotopic gamma radiation sources in JAERI

    Katoh, Hisashi; Kogure, Hiroto; Suzuki, Kyohei

    1980-04-01

    The present state of production of gamma radiation sources in Japan Atomic Energy Research Institute (JAERI) is described. Sources of 192 Ir, 60 Co and 170 Tm for industrial and 198 Au and 192 Ir for medical applications are produced and delivered routinely by JAERI. Prefabricated assembly targets are irradiated in JRR-2, JRR-3, JRR-4 or JMTR. The irradiated targets are disassembled in a heavy density concrete cave or a lead-shielded cell, depending on the level of radioactivity. The yield of radioactivity in each target is measured with the aid of an ionization chamber. Where necessary, irradiated targets are encapsulated hermetically in capsules of aluminium, stainless steel or other material. The yield of radioactivity is estimated in relation with the burn-up of target nuclide and product nuclide. (author)

  9. Help system for control of JAERI FEL (Free Electron laser)

    Sugimoto, Masayoshi

    1993-01-01

    The control system of JAERI FEL (Free Electron Laser) has a help system to provide the information necessary to operate the machine and to develop the new user interface. As the control software is constructed on the MS-Windows 3.x, the hyper-text feature of the Windows help system can be accessed. It consists of three major parts: (1) on-line help, (2) full document, and (3) tutorial system. (author)

  10. Burnup credit implementation plan and preparation work at JAERI

    Nomura, Y.; Itahara, K.

    2001-01-01

    Application of the burnup credit concept is considered to be very effective to the design of spent fuel transport and storage facilities. This technology is all the more important when considering construction of the intermediate spent fuel storage facility, which is to be commissioned by 2010 due to increasing amount of accumulated spent fuel in Japan. Until reprocessing and recycling all the spent fuel arising, they will be stored as an energy stockpile until such time as they can be reprocessed. On the other hand, the burnup credit has been partly taken into account for the spent fuel management at Rokkasho Reprocessing Plant, which is to be commissioned in 2005. They have just finished the calibration tests for their burnup monitor with initially accepted several spent fuel assemblies. Because this monitoring system is employed with highly conservative safety margin, it is considered necessary to develop the more rational and simplified method to confirm burnup of spent fuel. A research program has been instituted to improve the present method employed at the spent fuel management system for the Spent Fuel Receiving and Storage Pool of Rokkasho Reprocessing Plant. This program is jointly performed by Japan Nuclear Fuel Limited (JNFL) and JAERI.This presentation describes the current status of spent fuel accumulation discharged from PWR and BWR in Japan and the recent incentive to introduce burnup credit into design of spent fuel storage and transport facilities. This also includes the content of the joint research program initiated by JNFL and JAERI. The relevant study has been continued at JAERI. The results by these research programs will be included in the Burnup Credit Guide Original Version compiled by JAERI. (author)

  11. Knowledge based operation assist system for JAERI AVF cyclotron

    Agematsu, T.; Okumura, S.; Yokota, W.; Arakawa, K.; Murakami, T.; Okamura, T.

    1992-01-01

    We have developed two operation assist systems for easy and rapid operation of the JAERI AVF cyclotron. One is a knowledge based expert system guiding the sequence of parameter adjustment to inexperienced cyclotron operators. The other is a real-time simulation of the beam trajectories which are calculated from actual operating parameters. It graphically indicates feasible setting range of parameters that satisfies the acceptance of the cyclotron. These systems provide a human interface to adjust the parameters of the cyclotron. (author)

  12. Generation of Coherent Synchrotron Radiation from JAERI-ERL

    Hajima, R; Kikuzawa, N; Minehara, E J; Nagai, R; Nishitani, T; Sawamura, M

    2005-01-01

    An electron beam with high-average current and short bunch length can be accelerated by energy-recovery linac. Coherent synchrotron radiation (CSR) from such an electron beam will be a useful light source around millimeter wavelength. We report results from a preliminary measurement of CSR emitted from a bending magnet of JAERI-ERL. Possible enhancement of CSR power by FEL micro-bunching is also discussed.

  13. Characterization and evaluation studies on some JAERI dosimetry systems

    Kojima, T.; Sunaga, H.; Tachibana, H.; Takizawa, H.; Tanaka, R.

    2000-01-01

    Characterization and evaluation studies were carried out on some JAERI dosimetry systems, mainly alanine-ESR, in terms of the influence on the dose response of parameters such as orientation at ESR analysis, and the temperature during irradiation and analysis. Feasibility study for application of these dosimetry systems to electrons with energies lower than 4 MeV and bremsstrahlung (X rays) was also performed parallel to their reliability check through international dose intercomparison. (author)

  14. Design studies of Tokamak power reactor in JAERI

    Tone, T.; Nishikawa, M.; Tanaka, Y.

    1985-01-01

    Recent design studies of tokamak power reactor and related activities conducted in JAERI are presented. A design study of the SPTR (Swimming-Pool Type Reactor) concept was carried out in FY81 and FY82. The reactor design studies in the last two years focus on nuclear components, heat transport and energy conversion systems. In parallel of design studies, tokamak systems analysis code is under development to evaluate reactor performances, cost and net energy balance

  15. JAERI Material Performance Database (JMPD); outline of the system

    Yokoyama, Norio; Tsukada, Takashi; Nakajima, Hajime.

    1991-01-01

    JAERI Material Performance Database (JMPD) has been developed since 1986 in JAERI with a view to utilizing the various kinds of characteristic data of nuclear materials efficiently. Management system of relational database, PLANNER was employed and supporting systems for data retrieval and output were expanded. JMPD is currently serving the following data; (1) Data yielded from the research activities of JAERI including fatigue crack growth data of LWR pressure vessel materials as well as creep and fatigue data of the alloy developed for the High Temperature Gas-cooled Reactor (HTGR), Hastelloy XR. (2) Data of environmentally assisted cracking of LWR materials arranged by Electric power Research Institute (EPRI) including fatigue crack growth data (3000 tests), stress corrosion data (500 tests) and Slow Strain Rate Technique (SSRT) data (1000 tests). In order to improve user-friendliness of retrieval system, the menu selection type procedures have been developed where knowledge of system and data structures are not required for end-users. In addition a retrieval via database commands, Structured Query Language (SQL), is supported by the relational database management system. In JMPD the retrieved data can be processed readily through supporting systems for graphical and statistical analyses. The present report outlines JMPD and describes procedures for data retrieval and analyses by utilizing JMPD. (author)

  16. An outcome of nuclear safety research in JAERI. Case study for LOCA, FP, criticality and reprocessing

    Yanagisawa, Kazuaki; Ito, Keishiro; Kawashima, Kei; Katsuki, Chisato; Shirabe, Masashi

    2009-09-01

    An outcome of nuclear safety research done by JAERI was case studied by the bibliometric method. (1) For LOCA (loss-of-coolant accident) a domestic share of JAERI in monoclinic research paper was 63% at the past (20) 1978-1982 but was decreased to 40% at the present 1998-2002. For co-authored papers a domestic share between JAERI and PS (public sectors) is almost zero at past (20) but increased to 4% at the present. Research cooperation is active between Tokyo University and JAERI or between JAERI and Nagoya University. (2) Project-type research is to have a large monopolization in papers and that of basic-type research is to have a large development of research networking (DRN). (3) For FP, a share of co-authored paper is high due to an enhanced cooperation among JAERI-PO (Public Organization)-PS. For criticality, research activity was enhanced after JCO accident, especially at NUCEF. (4) For reprocessing, PS had a monopolistic position with a domestic share of 71% and a share of JAERI was about 20%. (5) LOCA and RIA outputs born by NSR-JAERI coincided partly to those of the Safety Licensing Guidelines but a share of contribution done by JAERI was ambiguous due to the lack of necessary information. (author)

  17. Report of the JAERI's Institution Evaluation Committee on general organizational managements

    1999-11-01

    In accordance with the National Guidelines on the Method of Evaluation for Government R and D, the Institution Evaluation Committee of JAERI conducted the extensive review on overall aspects in the JAERI's organizational management, starting with the Committee Meeting held in December 1998. This report describes the results of the review on 'JAERI's organizational management in view of the National Guidelines', 'Summary of evaluation of R and D themes' and 'Recommendations by the Committee and its Members', The contents, reported to news agencies in March 1999, are also available in the JAERI's internet home page. (author)

  18. Publish literature on the research activities using the JMRT (II). Publication as JAERI research reports

    Nagao, Yoshiharu; Ishii, Tadahiko; Niimi, Motoji; Fujiki, Kazuo; Takahashi, Hidetake (eds.) [Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment

    2002-11-01

    The published reports on the research and development activities using the JMTR since 1971 to date have been surveyed by the search of literature database and questionnaire survey. This report compiles the title lists and abstracts of reports published by JAERI and survey the trend of the research and development in JAERI using the JMTR. (author)

  19. Published literature on the research activities using the JMRT (II). Publication as JAERI research reports

    Nagao, Yoshiharu; Ishii, Tadahiko; Niimi, Motoji; Fujiki, Kazuo; Takahashi, Hidetake

    2002-11-01

    The published reports on the research and development activities using the JMTR since 1971 to date have been surveyed by the search of literature database and questionnaire survey. This report compiles the title lists and abstracts of reports published by JAERI and survey the trend of the research and development in JAERI using the JMTR. (author)

  20. Cost benefit effect of application of radiation in JAERI

    Kazuaki Yanagisawa

    2009-01-01

    It is important for us to show accountability and transparency of nuclear funds invested to Japan Atomic Energy Research Institute (JAERI, now JAEA). We have not only to simply present the R and D outputs to tax payers by the bibliometric methods as measurable as possible but also to carry out a cost benefit analysis to show quantitatively the effect of economic representation which enables to make efficient allotment of resources. The task is heavy but unavoidable. In the present work, a cost benefit effect (CBE) of application of radiation known as one of big R and D project conducted in JAERI-Takasaki Branch is focused on. After defining CBE as Market Creation Effect (MCE) / Total amounts of investment, one tried to reveal the long-term CBE as long as 44 years. It is found that 31 research items, such as radial tires, cross-linking of wires, sterilization, and sterile of melon flies were succeeded to create markets in industrial and agricultural fields. Estimated MCE of those was totaled to 1,125 million dollars (M$). On the other hand, investment was 396 M$ for personnel (4,092 man/year) and 509 M$ for research costs. It totaled as 905 M$. Therefore, CBE for application of radiation in Takasaki Branch shall be 1,125/905=1.2. The mission dictated by the Long-Range Research Plan for Nuclear settled by the Atomic Energy Commission involves a lot of R and D tasks including partly the technical difficulties as well as partly the deep uncertainties for future prospects. JAERI is a national research institute and this figure may be regarded as reasonably acceptable because of many high risk and complex tasks were conducted successfully resulting in the creation of 31 new markets. It contributed to the increase of GDP. (Author)

  1. Overview of HTGR heat utilization system development at JAERI

    Miyamoto, Y.; Shiozawa, S.; Ogawa, M.; Akino, N.; Shimizu, S.; Hada, K.; Inagaki, Y.; Onuki, K.; Takeda, T.; Nishihara, T.

    1998-01-01

    The Japan Atomic Energy Research Institute (JAERI) has conducted research and development of nuclear heat utilization systems of a High Temperature Gas cooled Reactor (HTGR), which are capable to meet a large amount of energy demand without significant CO 2 emission to relax the global warming issue. The High Temperature engineering Test Reactor (HTTR) with thermal output of 30 MW and outlet coolant temperature of 950 deg C, the first HTGR in Japan, is under construction on the JAERI site, and its first criticality is scheduled for mid-1998. After the reactor performance and safety demonstration tests for several years, a hydrogen production system will be connected to the HTTR. A demonstration program on hydrogen production started in January 1997, in JAERI, as a study consigned by the Science and Technology Agency. A hydrogen production system connected to the HTTR is designed to be able to produce hydrogen by steam reforming of natural gas, using nuclear heat of 10 MW from the HTTR. The safety principle and standard are investigated for the HTTR hydrogen production system. In order to confirm safety, controllability and performance of key components in the HTTR hydrogen production system, an out-of-pile test facility on the scale of approximately 1/30 of the HTTR hydrogen production system is installed. It is equipped with an electric heater as a heat source instead of the HTTR. The out-of-pile test will be performed for four years after 2001. The HTTR hydrogen production system will be demonstratively operated after 2005 at its earliest plan. Other basic studies on the hydrogen production system using thermochemical water splitting, an iodine sulphur (IS) process, and technology of distant heat transport with microencapsulated phase change material have been carried out for more effective and various uses of nuclear heat. (author)

  2. KEK/JAERI joint project on high intensity proton accelerators

    Nagamiya, Shoji

    2002-01-01

    From JFY01, which started on April 1, 2001, a new accelerator project to provide high-intensity proton beams proceeded into a construction phase. This project is conducted under a cooperation of two institutions, KEK and JAERI. The accelerator complex will provide 1 MW proton beams at 3 GeV and 0.75 MW beams at 50 GeV. The project will be completed within six years. In this article I will describe a) the project itself, b) sciences to be pursued at this new accelerator complex and c) the present status and future plans of the project. (author)

  3. JAERI electrostatic accelerators for multiple ion beam application

    Ishii, Yasuyuki; Tajima, Satoshi; Takada, Isao

    1993-01-01

    An electrostatic accelerators facility of a 3MV tandem accelerator, a 3MV single-ended accelerator and a 400kV ion implanter was completed mainly for materials science and biotechnology research at JAERI, Takasaki. The accelerators can be operated simultaneously for multiple beam application in triple and dual beam modes. The single-ended machine was designed to satisfy an extremely high voltage stability of ±1x10 -5 to provide a submicron microbeam stably. The measured voltage stability and ripple were within the designed value. (author)

  4. Progress report on JAERI-ORNL cooperative neutron scattering research

    Iizumi, Masashi

    1985-08-01

    One year activities done under the JAERI-DOE(ORNL) cooperative neutron scattering program are summarized. This period just followed the completion of the wide-angle neutron diffractometer dedicated to the cooperative research. The report contains results of the performance test of the instrument and early research activities. The latter part includes the time-resolved measurements of the transition kinetics in tin and Ni-Mn alloy as well as the single-crystal diffraction by the flat-cone method. (author)

  5. Program of nuclear criticality safety experiment at JAERI

    Kobayashi, Iwao; Tachimori, Shoichi; Takeshita, Isao; Suzaki, Takenori; Ohnishi, Nobuaki

    1983-11-01

    JAERI is promoting the nuclear criticality safety research program, in which a new facility for criticality safety experiments (Criticality Safety Experimental Facility : CSEF) is to be built for the experiments with solution fuel. One of the experimental researches is to measure, collect and evaluate the experimental data needed for evaluation of criticality safety of the nuclear fuel cycle facilities. Another research area is a study of the phenomena themselves which are incidental to postulated critical accidents. Investigation of the scale and characteristics of the influences caused by the accident is also included in this research. The result of the conceptual design of CSEF is summarized in this report. (author)

  6. Development of seismic risk analysis methodologies at JAERI

    Tanaka, T.; Abe, K.; Ebisawa, K.; Oikawa, T.

    1988-01-01

    The usefulness of probabilistic safety assessment (PSA) is recognized worldwidely for balanced design and regulation of nuclear power plants. In Japan, the Japan Atomic Energy Research Institute (JAERI) has been engaged in developing methodologies necessary for carrying out PSA. The research and development program was started in 1980. In those days the effort was only for internal initiator PSA. In 1985 the program was expanded so as to include external event analysis. Although this expanded program is to cover various external initiators, the current effort is dedicated for seismic risk analysis. There are three levels of seismic PSA, similarly to internal initiator PSA: Level 1: Evaluation of core damage frequency, Level 2: Evaluation of radioactive release frequency and source terms, and Level 3: Evaluation of environmental consequence. In the JAERI's program, only the methodologies for level 1 seismic PSA are under development. The methodology development for seismic risk analysis is divided into two phases. The Phase I study is to establish a whole set of simple methodologies based on currently available data. In the Phase II, Sensitivity study will be carried out to identify the parameters whose uncertainty may result in lage uncertainty in seismic risk, and For such parameters, the methodology will be upgraded. Now the Phase I study has almost been completed. In this report, outlines of the study and some of its outcomes are described

  7. Design of a lattice for JAERI storage ring (JSR)

    Harada, Shunji; Yokomizo, Hideaki; Yanagida, Kenichi

    1990-08-01

    The new 8GeV synchrotron radiation facility (SPring-8) is planned to be constructed in Japan, and our institute (JAERI) are involved in this project with RIKEN. A compact electron storage ring JSR has been constructed in JAERI in order to study various kind of accelerator technologies, to test some devices such as the insertion devices and the beam monitors, and to train young researchers. The ring size is limited by the available space of a linac building, so that the circumference of JSR becomes 20.546 m. However, even in this small ring, one straight section with the length of ∼1.5 m, where the dispersion is free, is provided for the insertion device study. JSR takes Chasman-Green lattice with a superperiodicity of three. JSR is possible not only to suppress the dispersion but also to leave it on the long straight section. An electron beam from a linac is accepted into JSR in any operating modes. (author)

  8. Status of work on superconducting quarter wave resonators at JAERI

    Takeuchi, S.

    1988-01-01

    A superconducting heavy ion linac is being proposed for the JAERI-tandem booster. For the accelerating structure of the tandem booster which ought to accelerate heavy ions of wide range of mass numbers, quarter wave resonator (QWR)s are suitable because of their wide ion-velocity acceptance. Ions of hydrogen to bismuth from the JAERI tandem can be accelerated by β = 0.1 QWRs. The excellent result of a niobium QWR at Argonne National Laboratory was a motive for the development of niobium QWRs. Further considerations on the design were required, because the Argonne's QWR did not have beam ports nor frequency tuners. As a result of considerations on these points, it has been decided to have an oval cylinder for the outer conductor. The prototype resonator has been built and tested. The fabrication techniques of explosive bonding, electron beam welding and heat treatment were found to be available in domestic companies in 1984. After obtaining niobium and niobium-clad-copper materials in 1985, the prototype resonator was built in 1985-86. Electro-polishing was done in their laboratory. Tests at 4.2 K have been repeated several times in combination of treatments of the niobium surface. The work is proceeding to the construction of a buncher and a prototype linac unit which are composed of superconducting QWRs. 4 references, 4 figures, 2 tables

  9. Construction of new critical experiment facilities in JAERI

    Takeshita, Isao; Itahashi, Takayuki; Ogawa, Kazuhiko; Tonoike, Kotaro; Matsumura, Tatsuro; Miyoshi, Yoshinori; Nakajima, Ken; Izawa, Naoki

    1995-01-01

    Japan Atomic Energy Research Institute (JAERI) has promoted the experiment research program on criticality safety since early in 1980s and two types of new critical facilities, Static Experiment Critical Facility (STACY) and Transient Experiment Critical Facility (TRACY) were completed on 1994 in Nuclear Fuel Cycle Safety Engineering Research Facility (NUCEF) of JAERI Tokai Research Establishment. STACY was designed so as to obtain critical mass data of low enriched uranium and plutonium solution which is extensively handled in LWR fuel reprocessing plant. TRACY is the critical facility where critical accident phenomenon is demonstrated with low enriched uranium nitrate solution. For criticality safety experiments with both facilities, the Fuel Treatment System is attached to them, where composition and concentration of uranium and plutonium nitrate solutions are widely varied so as to obtain experiments data covering fuel solution conditions in reprocessing plant. Design performances of both critical facilities were confirmed through mock-up tests of important components and cold function tests. Hot function test has started since January of 1995 and some of the results on STACY are to be reported. (author)

  10. Present status of low-Z coating development in JAERI

    Nakamura, K.; Abe, T.; Obara, K.; Murakami, Y.

    1986-01-01

    In the JT-60 at JAERI, TiC-coated molybdenum and TiC-coated Inconel tiles are currently used as plasma interactive components. They have already been subjected to initial ohmic heating experiments and exhibited good adhesion characteristics under high heat flux conditions. The present article reviews a JAERI's coating development program for JT-60 experiments currently under way and for the next-step experiments. The program includes development and performance tests of the TiC-coated tiles, development of an in-situ coating technique for the repair of damaged surface of the tiles, and research on carbonization. Stress is laid on thermal shock and thermal fatigue tests of these coatings. In the thermal tests, adhesion between low-Z coatings and bulk materials have been investigated under high heat irradiation. TiC and TiN are used as coating material while Mo and Inconel 625 are employed as bulk material. Results are shown in this report concerning calculated temperature elavation of TiC/TiN/Mo due to hydrogen beam irradiation. As regards the irradiation time required for the melting of the substrate, experimental results mostly agree with calculations. Almost all coatings investigated are not exfoliated from the substrate until the melting of the substrate. (Nogami, K.)

  11. R and D thermochemical I-S process at JAERI

    Onuki, K.; Kubo, S.; Nakajima, H.; Higashi, S.; Kasahara, S.; Ishiyama, S.; Okuda, H.

    2004-01-01

    The Japan Atomic Energy Research Institute (JAERI) has conducted a study on the thermochemical water-splitting process of the iodine-sulfur family (IS process). In the IS process, water will react with iodine and sulfur dioxide to produce hydrogen iodide and sulfuric acid, which are then decomposed thermally to produce hydrogen and oxygen. High temperature nuclear heat, mainly supplied by a High Temperature Gas-cooled Reactor (HTGR), is used to drive the endothermic decomposition of sulfuric acid. JAERI has demonstrated the feasibility of the water-splitting hydrogen production process by carrying out laboratory-scale experiments in which combined operation of fundamental reactions and separations using the IS process was performed continuously. At present, the hydrogen production test is continuing, using a scaled-up glass apparatus. Corrosion-resistant materials for constructing a large-scale plant and process improvements by introducing advanced separation techniques, such as membrane separation, are under study. Future R and D items are discussed based on the present activities. (author)

  12. How should the JAERI neutron source be designed?

    Watanabe, Noboru

    1996-01-01

    The importance of a next-generation neutron source in JAERI is discussed. The feasibility and the performances of three types of neutron sources, namely continuous wave spallation source (CWSS), long-pulse spallation source (LPSS) and short-pulse spallation source (SPSS), are compared based on a proposed JAERI accelerator, a superconducting (SC) proton linac (1-1.5 GeV, 25-16 mA in peak current, finally CW). How to realize one of the world's best neutron source using such a linac with a modest beam-current and what type of neutron source is the best for such a linac are the most important current problems. Since the accelerator is not favorable for LPSS due to a lower peak current and there exist serious technical problems for a CWSS target, a short-pulse spallation source would be the best candidate to realize a 5 MW-class SPSS like ESS, provided that the H - -injection to a compressor ring over a long pulse duration (>2 ms) is feasible. (author)

  13. Research in JAERI on the backend of nuclear fuel cycle

    Maeda, Mitsuru; Takeshita, Isao

    1999-01-01

    Japan's policy of the backend of nuclear fuel cycle is to reprocess spent fuels and recycle recovered plutonium and uranium, under the principle of no surplus plutonium. High-level radioactive waste separated during reprocessing will be disposed of after solidification in vitrified form, followed by the storage for 30 to 50 years and finally by ultimate disposal in a deep geological formation. The role of JAERI and the effective utilization of NUCEF would become more important. The current status of JAERI's research on backend cycle is reviewed together with the future research direction with emphases on NUCEF utilization. (1) Major objectives of safety research is to develop safety criteria and establish technical bases for licensing, to improve the safety of current or near future technology and to clarify the safety margin of licensed technology. (2) The present goal of fundamental research is to show or clarify the chemical or scientific feasibility of advanced system such as for recycling minor actinides or for incinerating long-lived nuclides. (3) Supporting research for nuclear material control is also conducted mainly for international contribution to strengthened safeguards by IAEA and to frame working of international monitoring system for CTBT. (J.P.N.)

  14. Environmental monitoring activities in JAERI at JCO accident

    Yamaguchi, Takenori

    2001-01-01

    The Japan Atomic Energy Research Institute (JAERI) was involved in a various environmental monitoring activities, such as environmental radiation monitoring by monitoring post and monitoring car, air dust, soil, green vegetables and water sampling and measurements, neutron and gamma radiation dose rate survey around the JCO site for emergency response actions to the JCO accident on September 30, 1999. These activities were performed from Sep. 30 to Oct. 2, and were the initial and first stage activities in the emergency environmental monitoring activities. JAERI has been assigned to the public organization to support the government by Disaster Prevention Fundamental Law. These activities were performed to ensure the public safety to avoid the effluent of the accident. Through the environmental monitoring activities, I recognized that the importance of the accident information to make the best use for the initial environmental monitoring, and the monitoring information exchange is important to perform the effective monitoring activities for taking the early countermeasures such as evacuation to the public. (author)

  15. US/JAERI calculational benchmarks for nuclear data and codes intercomparison. Article 8

    Youssef, M.Z.; Jung, J.; Sawan, M.E.; Nakagawa, M.; Mori, T.; Kosako, K.

    1986-01-01

    Prior to analyzing the integral experiments performed at the FNS facility at JAERI, both US and JAERI's analysts have agreed upon four calculational benchmark problems proposed by JAERI to intercompare results based on various codes and data base used independently by both countries. To compare codes the same data base is used (ENDF/B-IV). To compare nuclear data libraries, common codes were applied. Some of the benchmarks chosen were geometrically simple and consisted of a single material to clearly identify sources of discrepancies and thus help in analysing the integral experiments

  16. Development of web database system for JAERI ERL-FEL

    Kikuzawa, Nobuhiro

    2005-01-01

    The accelerator control system for the JAERI ERL-FEL is a PC-based distributed control system. The accelerator status record is stored automatically through the control system to analyze the influence on the electron beam. In order to handle effectively a large number of stored data, it is necessary that the required data can be searched and visualized in easy operation. For this reason, a web database (DB) system which can search of the required data and display visually on a web browser was developed by using open source software. With introduction of this system, accelerator operators can monitor real-time information anytime, anywhere through a web browser. Development of the web DB system is described in this paper. (author)

  17. Development of web database system for JAERI ERL-FEL

    Kikuzawa, Nobuhiro [Japan Atomic Energy Research Inst., Kansai Research Establishment, Advanced Photon Research Center, Tokai, Ibaraki (Japan)

    2005-06-01

    The accelerator control system for the JAERI ERL-FEL is a PC-based distributed control system. The accelerator status record is stored automatically through the control system to analyze the influence on the electron beam. In order to handle effectively a large number of stored data, it is necessary that the required data can be searched and visualized in easy operation. For this reason, a web database (DB) system which can search of the required data and display visually on a web browser was developed by using open source software. With introduction of this system, accelerator operators can monitor real-time information anytime, anywhere through a web browser. Development of the web DB system is described in this paper. (author)

  18. Development of the four group partitioning process at JAERI

    Kubota, Masumitsu; Morita, Yasuji; Yamaguchi, Isoo; Yamagishi, Isao; Fujiwara, T.; Watanabe, Masayuki; Mizoguchi, Kenichi; Tatsugae, Ryozo

    1999-01-01

    At JAERI, development of a partitioning method started about 24 years ago. From 1973 to 1984, a partitioning process was developed for separating elements in HLLW into 3 groups; TRU, Sr-Cs and others. The partitioning process consisted of three steps; solvent extraction of U and Pu with TBP, solvent extraction of Am and Cm with DIDPA, and adsorption of Sr and Cs with inorganic ion exchangers. The process was demonstrated with real HLLW. Since 1985, a four group partitioning process has been developed, in which a step for separating the Tc-PGM group was developed in addition to the three group separation. Effective methods for separating TRU, especially Np, and Tc have been developed. In this paper, the flow sheet of the four group partitioning and the results of tests with simulated and real HLLW in NUCEF hot-cell are shown. (J.P.N.)

  19. Outline of application plans of accelerator beams in JAERI

    Suzuki, Yasuo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1997-03-01

    Japan Atomic Energy Research Institute (JAERI) has various application plans of accelerators such as; Neutron Science Research Complex (NSRC), Positron Factory, International Fusion Material Irradiation Facility (IFMIF), and Spring-8 Project. Each application plan has its own research program and its own core accelerator. The NSRC is a multi-purpose research complex composed of seven research facilities: slow neutron scattering facility for material science, the nuclear energy research facility like nuclear transmutation and so on. The Positron Factory will be applied to the research of precise analysis of material structure by novel method of positron probing. The IFMIF aims at simulating the wall loading of a demo fusion reactor by producing high intense neutron flux. The SPring-8 is the largest synchrotron radiation source in the world. More than 60 X-ray beam lines will be equipped for the various researches. (author)

  20. Radioactive waste generated from JAERI partitioning-transmutation cycle system

    Shinichi, Nakayama; Yasuji, Morita; Kenji, Nishihara [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)

    2001-07-01

    Production of lower-level radioactive wastes, as well as the reduction in radioactivity of HLW, is an important performance indicator in assessing the viability of a partitioning-transmutation system. We have begun to identify the chemical compositions and to quantify the amounts of radioactive wastes that may be generated by JAERI processes. Long-lived radionuclides such as {sup 14}C and {sup 59}Ni and spallation products of Pb-Bi coolants are added to the existing inventory of these nuclides that are generated in the current fuel cycle. Spent salts of KCl-LiCl, which is not generated from the current fuel cycle, will be introduced as a waste. (author)

  1. Present status of decommissioning materials reuse research at JAERI

    Fujiki, Kazuo; Nakamura, Hisashi; Kanazawa, Katsuo

    1991-01-01

    Rational treatment and disposal of a large volume of the dismantling wastes resulting from the reactor dismantling are the key to success to carry out the decommissioning smoothly. From this viewpoint, the Japan Atomic Energy Research Institute (JAERI) has been conducting development of the recycling technology for metal waste and a investigation study on the rational recycling system for the dismantling wastes recycling. With respect to the development of the recycling technology, melting tests using non-contaminated metals have been conducted and the basic characteristics of experimental facility and material balances understood. In the investigation study on the rational recycling system, review and discussion were made on the amount of waste arising from decommissioning a nuclear power plant, a scenario of recycling the wastes, and the necessary processing facilities. (author)

  2. Radioactive Wastes Generated From JAERI Partitioning-Transmutation Fuel Cycle

    Nakayama, Shinichi; Morita, Yasuji; Nishihara, Kenji

    2003-01-01

    Production of lower-level radioactive wastes, as well as the reduction in radioactivity of HLW, is an important performance indicator in assessing the viability of a partitioning-transmutation system. We have begun to identify the chemical compositions and to quantify the amounts of radioactive wastes that may be generated by JAERI's processes. Long-lived radionuclides such as 14 C and 59 Ni and spallation products of Pb-Bi coolants are added to the existing inventory of these nuclides that are generated in the current fuel cycle. Spent salts of KCl-LiCl, which is not generated from the current fuel cycle, will be introduced as a waste. (authors)

  3. Development program on HTTR heat application systems at JAERI

    Ogawa, M.; Inagaki, Y.; Nishihara, T.; Shimizu, S.; Shiozawa, S.; Miyamoto, Y.

    2000-01-01

    The High Temperature Engineering Test Reactor (HTTR), which is a Japanese High Temperature Gas-cooled Reactor (HTGR) with 30 MW thermal output at 950 deg. C of the coolant outlet temperature, was constructed at Oarai Research Establishment of Japan Atomic Energy Research Institute (JAERI). The HTTR has attained the first criticality on November 1998. In JAERI, a hydrogen production system was selected as a heat utilization system of the HTTR. The development program on the HTTR hydrogen production system consists of two parts: one is to establish technologies connecting the hydrogen production system with the HTTR, the other is to establish technologies producing hydrogen from water by using nuclear heat. Finally, hydrogen can be produced from water by using nuclear heat supplied by the HTTR. In the hydrogen production system connected to the HTTR at first, JAERI selected a steam reforming process because its technology had matured. The HTTR hydrogen production system adopting the steam reforming process is being designed to produce hydrogen of about 3800 Nm 3 /hr by using nuclear heat (10MW, 905 deg. C) supplied from the HTTR. The safety principle and criteria are also being investigated for the HTTR hydrogen production system. A facility for an out-of-pile test prior to the demonstration test with the HTTR hydrogen production system is under manufacturing to carry out tests of safety, controllability and performance. The out-of-pile test facility simulates key components downstream an intermediate heat exchanger of the HTTR hydrogen production system on a scale of 1 to 30. The tests will be started in 2001 and continued for 4 years or longer. In parallel to the tests, a hydrogen/tritium permeation test and a corrosion test of a catalyst tube of a steam reformer are being carried out to obtain data necessary for the design of the HTTR hydrogen production system. A kind of thermochemical method called IS process is under studying to produce hydrogen from water by

  4. Current status of JAERI Tokai hot cell facilities

    Itami, Hiroharu; Morozumi, Minoru; Yamahara, Takeshi

    1992-01-01

    JAERI has 4 hot cell facilities in order to examine high radioactive materials. Three of them, the Research Hot Laboratory, the Reactor Fuel Examination Facility and the Waste Safety Testing Facility are located in the JAERI Tokai site, and the rest is the JMTR Hot Laboratory in the Oarai site. The Research Hot Laboratory (RHL) was constructed for post-irradiation examination (PIE), especially nuclear related basic research experiment, such as metallurgical, chemical and mechanical examination on fuels and materials irradiated in research and test reactors. This facility has 10 large dimension concrete and 38 lead cells. At present the RHL is used for various kinds of examinations of high radioactive samples such as fuels of research and test reactors, power reactors and high temperature testing reactor (HTTR), and structural materials. The Reactor Fuel Examination Facility (RFEF) was designed and constructed for carrying out PIE of irradiated full-size fuel assemblies of light water reactors (LWRs). This facility has a storage pool, 8 concrete and 5 lead cells. They are currently used for safety evaluation on high burnup and advanced lWR fuels as part of the national program. The Waste Safety Testing Facility (WASTEF) was designed and constructed for safety research on long-term storage and disposal of high level radioactive wastes, generated by fuel reprocessing. The WASTEF has 5 concrete cells and 1 lead cell. Examinations on the behavior of various long-lived fission products in a glass form and in a canister and, releasing behavior of them out of a canister are carrying out under the condition at storage. (author)

  5. JAERI/U.S. collaborative program on fusion blanket neutronics

    Nakagawa, Masayuki; Mori, Takamasa; Kosako, Kazuaki; Oyama, Yukio; Nakamura, Tomoo

    1989-10-01

    Phase IIa and IIb experiments of JAERI/U.S. Collaborative Program on Fusion Blanket Neutronics have been performed using the FNS facility at JAERI. The phase IIa experimental systems consist of the Li 2 O test region, the rotating neutron target and the Li 2 CO 3 container. In phase IIb, a beryllium layer is added to the inner wall to investigate a multiplier effect. Measured parameters are source characteristics by a foil activation method and spectrum measurements using both NE-213 and proton recoil counters. The measurements inside the Li 2 O region included tritium production rates, reaction rate by foil activation and neutron spectrum measurements. Analysis for these parameters was performed by using two dimensional discrete ordinate codes DOT3.5 and DOT-DD, and a Monte Carlo code MORSE-DD. The nuclear data used were based on JENDL3/PR1 and PR2. ENDF/B-IV, V and the FNS file were used as activation cross sections. The configurations analysed for the test region were a reference, a beryllium front and a beryllium sandwiched systems in phase IIa, and a reference and a beryllium front with first wall systems in phase IIb. This document describes the results of analysis and comparison between the calculations and the measurements. The prediction accuracy of key parameters in a fusion reactor blanket are examined. The tritium production rates can be well predicted in the reference systems but are fairly underestimated in the system with a beryllium multiplier. Details of experiments and the experimental techniques are described separately in the another report. (author)

  6. Report on progress of researches by common utilization of JAERI nuclear facilities, for fiscal 1992

    1993-08-01

    The results of the joint researches by utilizing the facilities of JAERI in 1992 fiscal year were summarized. The number of research themes in 1992 was 247 cases. In this book, 166 reports are collected. (J.P.N.)

  7. Report on progress of researches by common utilization of JAERI nuclear facilities, for fiscal 1993

    1994-07-01

    The results of the joint researches by utilizing the facilities of JAERI in 1993 fiscal year were summarized. The number of research themes in 1993 was 228 cases. In this book, 243 reports are collected. (J.P.N.)

  8. Annual report on neutron scattering studies in JAERI, September 1, 1978 - August 31, 1979

    Iizumi, Masashi; Endoh, Yasuo

    1980-03-01

    Neutron scattering studies carried out from September 1978 to August 1979 by Division of Physics, JAERI, and universities with JRR-2 and -3 neutron beam facilities are described: 51 summary reports, and a list of publications. (author)

  9. LTFR-4, Library Generated for Fast Reactor Design Program from JAERI Fast-Set Multigroup Constant

    Suzuki, Tomoo

    1971-01-01

    Nature of physical problem solved: The program processes JAERI-Fast group constants sets of less than 30-group and prepares a binary library tape for efficient usage by a series of related fast reactor design calculation programmes

  10. An outcome of nuclear safety research in JAERI. Predominance of research

    Yanagisawa, Kazuaki; Kawashima, Kei; Ito, Keishiro; Katsuki, Chisato

    2010-02-01

    Bibliometric study by means of research papers revealed the followings; (1) Nuclear Safety Research (NSR) performed in Japan is the 2nd highest in the world followed by USA. The share of JAERI for safety paper publication is about 25% in Japan (2) During past 25 years, JAERI is predominant at 39 safety fields out of 97, that is, 40% to the total. This is the fact revealed from comparison of published number of research papers with those of other organizations. (3) JAERI is recently changing its stress point from reactor-oriented accidents to the down stream of nuclear fuel cycling. There existed impact of TMI-2 accident on NSR-JAERI, especially in the field of thermal hydraulics, LOCA, severe accident and risk analysis. (author)

  11. Investigation of environmental radioactivity in waste dumping areas of the far eastern seas. JAERI`s activities in the 1st Japanese-Korean-Russian joint expedition 1994

    Amano, Hikaru; Matsunaga, Takeshi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Yabuuchi, Noriaki

    1996-10-01

    Large quantities of radioactive waste have been dumped in the Far Eastern Sea by the former USSR and Russia. In order to survey marine radioactive contamination in the Far Eastern Sea, the first Japanese-Korean-Russian joint expedition was conducted according to the governmental agreement. The joint expedition was conducted at the areas of the Russian radioactive waste dumping site from March 18 1994 to April 6, 1994. JAERI participated in this expedition according to the request from STA Japan, and conducted mainly on-board measurement of marine radioactivities. The results showed that the radionuclides concentrations in seawater and seabed sediment samples from the study site were not different from those in the western North Pacific. This report summarises JAERI`s activities in the expedition. Final report by Japanese-Korean-Russian government and IAEA is annexed. (author)

  12. Proceedings of the third JAERI-KAERI joint seminar on post irradiation examination technology

    1999-09-01

    Between the Department of JMTR of the Japan Atomic Energy Research Institute (JAERI) and the Nuclear Fuel Cycle Research Group of the Korea Atomic Energy Research Institute (KAERI), it has been periodically carried out the collaboration on technical information exchange by specialists and scientists, under the Arrangement of the Implementation of Cooperative Research Program in the Field of Peaceful Uses of Nuclear between JAERI and KAERI. And JAERI-KAERI joint seminar has been held every three years. The 1st and 2nd JAERI-KAERI Joint Seminars were held in November 1992 at JAERI and in September 1995 at KAERI, respectively. The 3rd JAERI-KAERI Joint Seminar was held on 25 and 26 March, 1999 at the Oarai Research Establishment of JAERI. In this seminar, total participants of 84 were joined from JAERI, KAERI, Hanyang University, Japan Nuclear Cycle Development Institute, Oarai Branch of Institute for Materials Research (IMR) of Tohoku University, Nippon Nuclear Fuel Development Co., Ltd., Nuclear Development Corporation and others. Contributed presentations were in three sessions; Current status and future perspectives on PIE, PIE techniques and Evaluation of PIE data. Re-assembling technique for JOYO fuel, Nd-YAG laser welding technique, grain boundary analysis using FEG-TEM, lift time estimation of PWR Rod Cluster Control Assembly (RCCA) rodlet and failure analysis of Korea Nuclear Power Plant (KNP) fuel have been widely noticed as topic items on PIE. And some comments from PIE user, were pointed out that the nano-PIE technique, the flexibility to ad-hoc demands on testing space or utilization, and the international collaboration were very important for the next generation's PIE. The 34 of the present papers are indexed individually. (J.P.N.)

  13. Technical publications by JAERI staff from January 1976 to December 1976

    1977-11-01

    Approximately 400 journal articles, papers at meetings, reports and books are given, which have been published by personnel of JAERI from January 1976 to December 1976. The contents for each entry include the title, language in which it is written, author(s), and journal name or origin. They are presented in INIS subject categories. The indexes are both by authors and report number. A list of the patents, originating at JAERI, including both Japanese and other patents, is also given. (auth.)

  14. JAERI TANDEM annual report 2004. April 1, 2004 - March 31, 2005

    Ishii, Tetsuro; Takeuchi, Suehiro; Oshima, Masumi; Nagame, Yuichiro; Chiba, Satoshi; Sataka, Masao

    2006-01-01

    This annual report describes research activities, which have been performed with the JAERI tandem accelerator and its energy booster from April 1, 2004 to March 31, 2005. Summary reports of 48 papers, and lists of publication, personnel and cooperative research with universities are contained. The JAERI (Japan Atomic Energy Research Institute) have been unified with JNC (Japan Nuclear Fuel Cycle Development Institute) and became JAEA (Japan Atomic Energy Agency) on October 1st, 2005. (author)

  15. Technical publications by JAERI staff from January 1977 to December 1977

    1978-11-01

    Approximately 430 journal articles, papers at meetings, reports and books are given, which have been published by personnel of JAERI from January 1977 to December 1977. The contents for each entry include the title, language in which it is written, author(s), and journal name or origin. They are presented in INIS subject categories. The indexes are both by authors and report number. A list of the patents, originating at JAERI, including both Japanese and other patents, is also given. (author)

  16. Technical publications by JAERI staff from January 1975 to December 1975

    1977-03-01

    Approximately 400 journal articles, papers at meetings, reports and books are given, which have been published by personnel of JAERI from January 1975 to December 1975. The contents for each entry include the title, language in which it is written, author (s), and journal name or origin. They are presented in INIS subject categories. The indexes are both by authors and report number. A list of the patents, originating at JAERI, including both Japanese and other patents, is also given. (auth.)

  17. Proceedings of the third JAERI-KAERI joint seminar on post irradiation examination technology

    NONE

    1999-09-01

    Between the Department of JMTR of the Japan Atomic Energy Research Institute (JAERI) and the Nuclear Fuel Cycle Research Group of the Korea Atomic Energy Research Institute (KAERI), it has been periodically carried out the collaboration on technical information exchange by specialists and scientists, under the Arrangement of the Implementation of Cooperative Research Program in the Field of Peaceful Uses of Nuclear between JAERI and KAERI. And JAERI-KAERI joint seminar has been held every three years. The 1st and 2nd JAERI-KAERI Joint Seminars were held in November 1992 at JAERI and in September 1995 at KAERI, respectively. The 3rd JAERI-KAERI Joint Seminar was held on 25 and 26 March, 1999 at the Oarai Research Establishment of JAERI. In this seminar, total participants of 84 were joined from JAERI, KAERI, Hanyang University, Japan Nuclear Cycle Development Institute, Oarai Branch of Institute for Materials Research (IMR) of Tohoku University, Nippon Nuclear Fuel Development Co., Ltd., Nuclear Development Corporation and others. Contributed presentations were in three sessions; Current status and future perspectives on PIE, PIE techniques and Evaluation of PIE data. Re-assembling technique for JOYO fuel, Nd-YAG laser welding technique, grain boundary analysis using FEG-TEM, lift time estimation of PWR Rod Cluster Control Assembly (RCCA) rodlet and failure analysis of Korea Nuclear Power Plant (KNP) fuel have been widely noticed as topic items on PIE. And some comments from PIE user, were pointed out that the nano-PIE technique, the flexibility to ad-hoc demands on testing space or utilization, and the international collaboration were very important for the next generation's PIE. The 34 of the present papers are indexed individually. (J.P.N.)

  18. Annual report of the research works with joint-use JAERI facilities for fiscal 1974

    1975-01-01

    Results of the research works by national universities with JAERI's (Japan Atomic Energy Research Institute) joint-use facilities for fiscal 1974 are described. Facilities are research reactors, Co-60, Linac, etc. Research results are presented in individual summaries, covering radiation damage and solid state physics, activation analysis and nuclear chemistry, irradiation effects, etc. Results of the joint works with JAERI are also presented similarly. (Mori, K.)

  19. Status and Future Plans of JAERI Eergy-Recovery Linac FEL

    Hajima, R; Kikuzawa, N; Minehara, E J; Nagai, R; Nishimori, N; Nishitani, T; Sawamura, M; Yamauchi, T

    2005-01-01

    An energy-recovery linac for a high-power free-electron laser is in operation at Japan Atomic Energy Research Institute (JAERI). In this paper, we report results of research activities and future plans of JAERI ERL-FEL, which are the construction of FEL transport line, the operation of newly-installed RF controller and IOTs, the development of super-lattice photo cathode.

  20. Technical publications by JAERI staff from January 1974 to December 1974

    1975-03-01

    Approximately 370 journal articles, papers at meetings, reports and books are given, which have been published by personnel of JAERI from January 1974 to December 1974. The contents for each entry include the title, language in which it is written, author(s), and journal name or origin. They are presented in INIS subject categories. The indexes are both by authors and report number. A list of the patents, originating at JAERI, including both Japanese and other patents, is also given. (auth.)

  1. Summaries of research and development activities by using JAERI computer system in FY2003. April 1, 2003 - March 31, 2004

    2005-03-01

    Center for Promotion of Computational Science and Engineering (CCSE) of Japan Atomic Energy Research Institute (JAERI) installed large computer system included super-computers in order to support research and development activities in JAERI. CCSE operates and manages the computer system and network system. This report presents usage records of the JAERI computer system and big user's research and development activities by using the computer system in FY2003 (April 1, 2003 - March 31, 2004). (author)

  2. Summaries of research and development activities by using JAERI computer system in FY2004 (April 1, 2004 - March 31, 2005)

    2005-08-01

    Center for Promotion of Computational Science and Engineering (CCSE) of Japan Atomic Energy Research Institute (JAERI) installed large computer systems including super-computers in order to support research and development activities in JAERI. CCSE operates and manages the computer system and network system. This report presents usage records of the JAERI computer system and the big users' research and development activities by using the computer system in FY2004 (April 1, 2004 - March 31, 2005). (author)

  3. On the compressor ring for the JAERI neutron science project

    Yamane, Isao [National Lab. for High Energy Physics, Tsukuba, Ibaraki (Japan)

    1997-11-01

    (1), As long as a 1.5 GeV-8 MW linear accelerator is constructed in the JAERI neutron science center, it is quite reasonable to construct a 5 MW compressor ring as a driver of a high intensity spallation neutron source to generate pulsed neutron beams. (2), Suppression of beam loss around the compressor ring to an acceptable level is the most crucial subject to be coped with in designing a MW-class compressor ring. This subject should be successfully cleared by carefully studying and designing the overall system of accelerator and tunnel. (3), The `PSR instability` was comprehensively discussed in the NSNS workshop held at Santa Fe in March, 1997, as a remaining problem of a high intensity proton compressor ring. People of Los Alamos attributed it to an e-p instability. But some questions like the cause that makes some part of protons leak away from a beam bunch to a bunch gap are yet left open. (4), A new scheme of two step H{sup 0} injection is proposed to remove defects of the conventional one of Los Alamos PSR. (author)

  4. Experiences in monitoring airborne radioactive contamination in JAERI

    Ikezawa, Y.; Okamoto, T.; Yabe, A.

    1980-01-01

    The following results were obtained at the Japan Atomic Energy Research Institute (JAERI) from experience in air monitoring at the hot cells for handling highly radioactive materials, the glove box containing plutonium and the cell for producing 99 Mo. (1) The ratios of activities of airborne dust to those of whole dust were of the order of 10 -2 for the semi-volatile form of 125 Sb, and 10 -3 to 10 -4 for the particulate form of 137 Cs, 144 Ce and 144 Pr, when irradiated fuels were cut in the hot cells. (2) The activity median aerodynamic diameter (AMAD) of airborne particle size distributions varied from O.4 to 15 μm with changing geometric standard deviation (sigmasub(g)) 1.7 to 7, depending on types of metallurgical treatment of fuels and on kinds of work in the cells. (3) A resuspension factor (the ratio of the concentration of airborne contamination to the surface contamination) was found to be 4x10 -8 to approximately 2x10 -7 cm -1 for plutonium oxide deposited on the floor surface. (4) The collection efficiency of the charcoal-loaded filter paper for airborne radioiodine, consisting of 60% inorganic and 40% organic iodide, was over 95% under conditions of relative humidity 40 to approximately 80% and face velocity 50 cm/sec, during the production of 99 Mo. (H.K.)

  5. Construction plan of ion irradiation facility in JAERI

    Tanaka, Ryuichi

    1987-01-01

    The Takasaki Radiation Chemistry Research Establishment of Japan Atomic Energy Research Institute (JAERI) started the construction of an ion irradiation facility to apply ion beam to the research and development of radiation resistant materials for severe environment, the research on biotechnology and new functional materials. This project was planned as ion beam irradiation becomes an effective means for the research on fundamental physics and advanced technology, and the national guideline recently emphasizes the basic and pioneering field in research and development. This facility comprises an AVF cyclotron with an ECR ion source (maximum proton energy: 90 MeV), a 3 MV tandem accelerator, a 3 MV single end type Van de Graaf accelerator and a 400 kV ion implanter. In this report, the present status of planning the accelerators and the facility to be constructed, the outline of research plan, the features of the accelerators, and the beam characteristics are described. In this project, the research items are divided into the materials for space environment, the materials for nuclear fusion reactors, biotechnology, new functional materials, and ion beam technology. The ion beams required for the facility are microbeam, pulsed beam, multiple beam, neutron beam and an expanded irradiation field. (Kako, I.)

  6. Results from the Argonne, Los Alamos, JAERI collaboration

    Meadows, J.; Smith, D.; Greenwood, L. [Argonne National Lab., IL (United States); Haight, R. [Los Alamos National Lab., NM (United States); Ikeda, Y.; Konno, C. [Japan Atomic Energy Research Inst., Ibaraki (Japan)

    1993-07-01

    Four sample packets containing elemental Ti, Fe, Ni, Cu, Nb, Ag, Eu, Tb and Hf have been irradiated in three distinct accelerator neutron fields, at Argonne National Laboratory and Los Alamos National Laboratory, USA, and Japan Atomic Energy Research Institute, Tokai, Japan. The acquired experimental data include differential cross sections and integral cross sections for the continuum neutron spectrum produced by 7-MeV deuterons incident on thick Be-metal target. The U-238(n,f) cross section was also measured at 10.3 MeV as a consistency check on the experimental technique. This the third progress report on a project which has been carried out under the auspices of an IAEA Coordinated Research Program entitled ``Activation Cross Sections for the Generation Of Long-lived Radionuclides of Importance in Fusion Reactor Technology``. The present report provides the latest results from this work. Comparison is made between the 14.7-MeV cross-section values obtained from the separate investigations at Argonne and JAERI. Generally, good agreement observed within the experimental errors when consistent sample parameters, radioactivity decay data and reference cross values are employed. A comparison is also made between the experimental results and those derived from calculations using a nuclear model. Experimental neutron information on the Be(d,n) neutron spectrum was incorporated in the comparisons for the integral results. The agreement is satisfactory considering the various uncertainties that are involved.

  7. D-T neutron skyshine experiments at JAERI/FNS

    Nishitani, Takeo; Ochiai, Kentaro [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Yoshida, Shigeo [Tokai Univ., Hiratsuka, Kanagawa (JP)] (and others)

    2003-03-01

    The D-T neutron skyshine experiments have been carried out at the Fusion Neutronics Source (FNS) of JAERI with the neutron yield of {approx}1.7x10{sup 11} n/s. The concrete thickness of the roof and the wall of a FNS target room are 1.15 and 2 m, respectively. The FNS skyshine port with a size of 0.9x0.9 m{sup 2} was open during the experimental period. The radiation dose rate outside the target room was measured as far as about 550 m away from the D-T target point with a spherical rem-counter. The highest neutron dose was about 0.5 {mu}Sv/hr at a distance of 30 m from the D-T target point and the dose rate was attenuated to 0.002 {mu}Sv/hr at a distance of 550 m. The measured neutron dose distribution was analyzed with Monte Carlo code MCNP-4B and a simple line source model. The MCNP calculation overestimates the neutron dose in the distance range larger than 250 m. The neutron spectra were evaluated with a {sup 3}He detector with different thickness of polyethylene neutron moderators. Secondary gamma-rays were measured with high purity Ge detectors and NaI scintillation detectors. (author)

  8. Acoustic emission measurement on large scale coils at JAERI

    Yoshida, K.; Hattori, Y.; Nishi, M.F.; Shimamoto, S.; Tsuji, H.

    1986-01-01

    The objective of acoustic emission measurement at Japan Atomic Energy Research Institute (JAERI) is an establishment of a general diagnostic method for superconducting magnet systems. Output of strain and displacement gages can not cover a whole system in monitoring premonitory phenomena of a magnet system s failure, because these sensors are mounted on points and therefore localized. Acoustic emissions can be transmitted to sensors through structural materials without electrical noise. Monitoring of acoustic emission will be one of the methods to predict a serious failure of magnet systems in a vacuum vessel. For this purpose, several sensors were installed on the Japanese LCT coil and the Test Module Coil (TMC). Some of acoustic activity was similar as seen in these coils. The correlation between voltage spikes and acoustic events is excellent during single coil charging mode, but poorer during out of plane force mode. There are no indicative acoustical phenomena before a magnet quench or during normal zone generation. The conditioning of acoustic events and voltage spikes can be seen after any cooling down. The localization of electrical insulation damage with the acoustic emission technique is one of its most useful applications

  9. JAERI tandem-accelerator and tandem-booster

    Yoshida, Tadashi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1998-03-01

    In 1982, aiming at the new development of atomic energy research, the tandem accelerator of Japan Atomic Energy Research Institute (JAERI) was installed. In fiscal year 1993, the superconducting boosters which can increase the ion energy by up to 4 times were added, and the research in the region below 1000 MeV became possible. Those are electrostatic type accelerators which are easy to be used especially in basic research field, and are useful for future research. The tandem accelerator has been operated while maintaining the first class performance as the accelerator for various kinds of heavy ion beam. It has the special shape among electrostatic type accelerators, and is excellent in the easiness of control and stability. The main particulars of the tandem accelerator are shown. As for the ion sources of the tandem accelerator, three cesium sputter type ion sources are installed on two high voltage stands. The kinds of the ions which can be accelerated are mainly negative ions. As the improvement, electron cyclotron resonance (ECR) ion sources are expected to be adopted. As for the tandem boosters, the 1/4 wavelength type resonance hollow cylinder was adopted. The constitution of the tandem boosters is explained. The way of utilizing the tandem accelerator system and the aim for hereafter are reported. (K.I.)

  10. Overview of HTGR utilization system developments at JAERI

    Miyamoto, Y.; Shiozawa, S.; Inagaki, Y.

    1997-01-01

    JAERI has been constructing a 30-MWt HTGR, named HTTR, to develop technology and to demonstrate effectiveness of high-temperature nuclear heat utilization. A hydrogen production system by natural gas steam reforming is to be the first heat utilization system of the HTTR since its technology matured in fossil-fired plant enables to couple with HTTR in the early 2000's and technical solutions demonstrated by the coupling will contribute to all other hydrogen production systems. The HTTR steam reforming system is designed to utilize the nuclear heat effectively and to achieve hydrogen productivity competitive to that of a fossil-fired plant with operability, controllability and safety acceptable enough to commercialization, and an arrangement of key components was already decided. Prior to coupling of the steam reforming system with the HTTR, an out-of-pile test is planned to confirm safety, controllability and performance of the steam reforming system under simulated operational conditions. The out-of-pile system is an approximately 1/20-1/30 scale system of the HTTR steam reforming system and simulates key components downstream from an IHX

  11. Stress analysis of blanket vessel for JAERI experimental fusion reactor

    Sako, K.; Minato, A.

    1979-01-01

    A blanket structure of JAERI Experimental Fusion Reactor (JXFR) consists of about 2,300 blanket cells with round cornered rectangular cross sections (twelve slightly different shapes) and is placed in a vacuum vessel. Each blanket vessel is a double-walled thin-shell structure made of Type 316 stainless steel with a spherical domed surface at the plasma side. Ribs for coolant channel are provided between inner and outer walls. The blanket cell contains Li 2 O pebbles and blocks for tritium breeding and stainless steel blocks for neutron reflection. A coolant is helium gas at 10 kgf/cm 2 (0.98 MPa) and its inlet and outlet temperatures are 300 0 C and 500 0 C. The maxima of heat flux and nuclear heating rate at the first wall are 12 W/cm 2 and 2 W/cc. A design philosophy of the blanket structure is based on high tritium breeding ratio and more effective shielding performance. The thin-shell vessel with a rectangular cross section satisfies the design philosophy. We have designed the blanket structure so that the adjacent vessels are mutually supporting in order to decrease the large deformation and stress due to internal pressure in case of the thin-shell vessel. (orig.)

  12. Research and development of radiation utilizations in 1981 at JAERI

    1981-01-01

    There is the field of radiation utilization such as the application of the effect of radiation on matters and the techniques of measurement and analysis utilizing the properties of radiation, in addition to the use of atomic energy as heat or electric power. The fields of application of radiation utilization are very wide, and are closely related to the health and daily life of people. The Japan Atomic Energy Research Institute has performed the research and development on radiation utilization regarding radiochemistry, the application of irradiation, and the production and industrial utilization of radioisotopes. Also, the research of the radiation resistance of organic materials used for nuclear facilities, the development of organic materials, and the production of tritium have become necessary. In this booklet, the recent results of radiation utilization in the JAERI are summarized. The research and development of ion exchange membranes, organic glasses, the fixation of living body activators and water paints, the techniques of utilizing irradiation, the techniques of radioisotope productions and utilization, and the techniques related to the development of atomic energy are reported. (Kako, I.)

  13. The heavy water accountancy for research reactors in JAERI

    Yoshijima, Tetsuo; Tanaka, Sumitoshi; Nemoto, Denjirou

    1998-11-01

    The three research reactors have been operated by the Department of Research Reactor and used about 41 tons heavy water as coolant, moderator and reflector of research reactors. The JRR-2 is a tank type research reactor of 10MW in thermal power and its is used as moderator, coolant and reflector about 16 tons heavy water. The JRR-3M is a light water cooled and moderated pool type research reactor with a thermal power of 20MW and its is used as reflector about 7.3 tons heavy water. In the JRR-4, which is a light water cooled swimming pool type research reactor with the maximum thermal power of 3.5MW, about 1 ton heavy water is used to supply fully thermalized neutrons with a neutron beam experiment of facility. The heavy water was imported from U.S.A., CANADA and Norway. Parts of heavy water is internationally controlled materials, therefore management of heavy water is necessary for materials accountancy. This report described the change of heavy water inventories in each research reactors, law and regulations for accounting of heavy water in JAERI. (author)

  14. An upgraded version of the nucleon meson transport code: NMTC/JAERI97

    Takada, Hiroshi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Yoshizawa, Nobuaki; Kosako, Kazuaki; Ishibashi, Kenji

    1998-02-01

    The nucleon-meson transport code NMTC/JAERI is upgraded to NMTC/JAERI97 which has new features not only in physics model and nuclear data but also in computational procedure. NMTC/JAERI97 implements the following two new physics models: an intranuclear cascade model taking account of the in-medium nuclear effects and the preequilibrium calculation model based on the exciton one. For treating the nucleon transport process more accurately, the nucleon-nucleus cross sections are revised to those derived by the systematics of Pearlstein. Moreover, the level density parameter derived by Ignatyuk is included as a new option for particle evaporation calculation. Other than those physical aspects, a new geometry package based on the Combinatorial Geometry with multi-array system and the importance sampling technique are implemented in the code. Tally function is also employed for obtaining such physical quantities as neutron energy spectra, heat deposition and nuclide yield without editing a history file. The resultant NMTC/JAERI97 is tuned to be executed on the UNIX system. This paper explains about the function, physics models and geometry model adopted in NMTC/JAERI97 and guides how to use the code. (author)

  15. Preparation and certification of a uranium isotope certified reference material JAERI-U5

    Tamura, Shuzo; Hashitani, Hiroshi

    1982-06-01

    The Committee on Analytical Chemistry of Nuclear Fuels and Reactor Materials, JAERI had planned to prepare a new reference material, JAERI-U5 for uranium isotopic measurement since 1978. The reference material is composed of 6 samples of different enrichment in the range of 0.2 to 4.5 wt. percents of 235 U. The preparation includes dissolution of raw materials, blending of solutions, precipitation of ammonium diuranate, drying and ignition to U 3 O 8 . A mass-spectrometric collaborative analysis was carried out by well-trained two laboratories in this country, JAERI and PNC. The certified values were decided from the result of the collaborative work. As the measurements were based on NBS SRM's, JAERI-U5 should be called tertiary standard. The materials are packed in bottles of low-potassium-content glass for a possible use in non-destructive gamma-rays spectrometry. The reference material has been distributing from JAERI with a price of yen 140,000 per set (6 samples of 2 g of each) since 1979. (author)

  16. Report on progress of researches by common utilization of JAERI nuclear facilities, for fiscal 1988

    1989-01-01

    In 1988, this system called 'Common utilization of JAERI facilities' so far was changed to 'Joint research utilizing JAERI facilities', and by evaluating more positively the function of the General Research Center for Nuclear Energy, it has been emphasized to promote and coordinate the joint research among universities centering around the utilization of JAERI facilities. The total number of the research subjects in fiscal year 1988 reached 138, but the results of 120 of them are collected in this book. General joint research is the standard form of the utilization of various facilities that JAERI has opened to common utilization. Cooperation research is to be carried out by concluding research cooperation contracts between university researchers and JAERI researchers, and the facilities which are not opened to common utilization can be used. In the general joint research, the utilization of irradiation such as activation analysis, radiochemistry, irradiation effect, neutron diffraction and so on and the research using beams are mostly carried out, but in the cooperation research, reactor engineering, reactor materials,, nuclear physics measurement and so on are the main subjects. The total number of visitors in one year was 3829 man-day. (K.I.)

  17. Expectations of JAERI on INIS from a viewpoint of socio-economic evaluation

    Yanagisawa, K.; Takahashi, S.; Narita, O.; Yonezawa, M.

    2004-01-01

    Because the taxpayers funded basic scientific researches in JAERI, a feedback of the results to the public is strongly requested by the Japanese government. By using the concept of socio-economic effect, that is, the stimulation and promotion of social interrelations through a formation of networking in basic research, the authors tried to show a kind of feedback. For this purpose, JAERI developed computer code SOCIOECO combined with INIS was used as a main tool and database. The case study was addressed to the Material Science (MS) field in JAERI. It is revealed from the study that a significant formation and development of socio-economic networking is occurring at the emphasized basic research fields (EBRF) of ion irradiation and actinides having a strong relation to nuclear. For actinides a total of 7,237 papers were written in basic research fields, where the share of JAERI over 25 years was 25%, while 52% by public sectors (PS, namely university (U) and governmental sectors (GS)) and 17% by private organizations (PO). Numbers of co-written papers defined as an index of socio-economic networking were increased with time. The growth rate, for example, between JAERI and PS was of order of 3-4% per 25 years, while 8% per recent 5 years. The socio-economic networking described here seems to be useful for showing the feedback occurring from basic research to the public. (author)

  18. Present state of tandem superconductive booster of JAERI

    Takeuchi, Suehiro; Matsuda, Makoto; Kanazawa, Shuhei; Yoshida, Tadashi; Ouchi, Isao; Shoji, Tokio [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1996-12-01

    The superconductive booster constructed rear-stage accelerator of the tandem accelerator of the Tokai Research Establishment, JAERI (Japan Atomic Energy Research Institute), was completed in construction of its whole system on October, 1993, and through its beam accelerating test and remodulation its design characteristics were established on September, 1994. From November, 1994 to April, 1995 a repulsion-forming nuclear isolation apparatus was installed to modulate at target room, and was begun to use on June, 1995. The beam reaccelerated at the booster was used mainly for nuclear spectroscopy experiment, a collaborative research was developed using mini-crystal balls made by collecting from University of Tsukuba and so forth. The accelerating part of the booster is a phase independent setting type Linac consisting of 40 niobium superconducting holes with 1/4 wave-length type and 130 MHz in frequency, in which a hole can form 5 MV/m of accelerating electric field for 4 W of radio frequency spent power of 0.75 MV of accelerating voltage per hole, to form 30 MV of voltage in a whole. 4 holes are contained into each 10 cryostats, respectively. In accelerating tests, Si, Cl, Ni, Ge, Ag, I and Au ions are accelerated to establish 30 mV of total accelerating voltage in its design value, which reaches to their expected energy characteristics. Its used days in this year are 25 days after beginning of its use, and operating days of the cooling apparatus was 135 days in total. (G.K.)

  19. Research and Development programs for HTGRs in JAERI

    Nishiguchi, Isoharu; Saito, Sinzo [Department of HTTR Project, Japan Atomic Energy Research Institute (Japan)

    1990-07-01

    Since 1969, JAERI has conducted research and development (R and D) programs for High-Temperature Gas-Cooled Reactors (HTGR). And the High Temperature engineering Test Reactor (HTTR), which will be the first High Temperature Gas Cooled Reactor (HTGR) in Japan, is under licensing process now. In this paper, some of the results of R and D are outlined in the following fields which are closely connected with the HTTR design, that is: i) fuel; ii) nuclear design; iii) thermal-hydraulic design; iv) graphite structure and v) high temperature metal structure. In the field of fuel, extensive investigations have been performed to develop the fabrication technology of coated particle fuel (cpf). In parallel, data of coated fuel particle failure and fission product release in in- and ex-reactor experiments as well as mechanical properties data were obtained and irradiation tests have been done using the Oarai Gas Loop No.1 (OGL-1) to verify the integrity of mass-produced fuel. Concerning the nuclear design, critical experiments were conducted using the Very High-Temperature Reactor Critical Assembly (VHTRC). Also carried out were hydrodynamical and thermal experiments using the Helium Engineering Demonstration Loop (HENDEL). On the graphite structures which compose the reactor internals, design criteria have been developed based on ASME BandPV Code Section III Div.2, subsection CE and design data have been accumulated on a domestic graphite material. High temperature metal structure is also one of major subjects of R and D for HTGRs. Hastelloy XR, which is a modified version of Hastelloy X, was developed and various tests have been conducted which include creep tests, creep-fatigue tests, etc. to establish design criteria and allowables. Component tests of the Intermediate Heat Exchanger (IHX) have been also performed. (author)

  20. Research and Development programs for HTGRs in JAERI

    Nishiguchi, Isoharu; Saito, Sinzo

    1990-01-01

    Since 1969, JAERI has conducted research and development (R and D) programs for High-Temperature Gas-Cooled Reactors (HTGR). And the High Temperature engineering Test Reactor (HTTR), which will be the first High Temperature Gas Cooled Reactor (HTGR) in Japan, is under licensing process now. In this paper, some of the results of R and D are outlined in the following fields which are closely connected with the HTTR design, that is: i) fuel; ii) nuclear design; iii) thermal-hydraulic design; iv) graphite structure and v) high temperature metal structure. In the field of fuel, extensive investigations have been performed to develop the fabrication technology of coated particle fuel (cpf). In parallel, data of coated fuel particle failure and fission product release in in- and ex-reactor experiments as well as mechanical properties data were obtained and irradiation tests have been done using the Oarai Gas Loop No.1 (OGL-1) to verify the integrity of mass-produced fuel. Concerning the nuclear design, critical experiments were conducted using the Very High-Temperature Reactor Critical Assembly (VHTRC). Also carried out were hydrodynamical and thermal experiments using the Helium Engineering Demonstration Loop (HENDEL). On the graphite structures which compose the reactor internals, design criteria have been developed based on ASME BandPV Code Section III Div.2, subsection CE and design data have been accumulated on a domestic graphite material. High temperature metal structure is also one of major subjects of R and D for HTGRs. Hastelloy XR, which is a modified version of Hastelloy X, was developed and various tests have been conducted which include creep tests, creep-fatigue tests, etc. to establish design criteria and allowables. Component tests of the Intermediate Heat Exchanger (IHX) have been also performed. (author)

  1. The JAERI superconducting RF linac-based FELS and THEIR cryogenics

    Minehara, Eisuke J.

    2003-01-01

    In the 21st century, we need a powerful and efficient free-electron laser (FEL) for academic and industrial uses in almost all fields. In order to realize such a tunable, highly-efficient, high average power, high peak power and ultra-short pulse FEL, the JAERI FEL group and I have developed an industrial FEL driven by a compact, stand-alone and zero-boil off super-conducting rf linac with an energy-recovery geometry. Our discussions on the JAERI FEL and cryogenics will cover market-requirements for the industrial FELs, some answers from the JAERI compact, stand-alone and zero-boil off cryostat concept and operational experiences over these 9 years, our discovery of the new, highly-efficient, high-power, and ultra-short pulse lasing mode, and the energy-recovery geometry. (author)

  2. Present and next steps of the JAERI superconducting rf linac based FEL program

    Minehara, E.J.; Yamauchi, T.; Sugimoto, M.

    2000-01-01

    The JAERI superconducting rf linac based FEL has successfully been lased to produce a 0.3 kW FEL light and 100 kW or larger electron beam output in quasi continuous wave operation in 1999. The 1 kW class output as our present program goal will be achieved to improve the optical out coupling method in the FEL optical resonator, the electron gun, and the electron beam optics in the JAERI FEL driver. As our next 5 year program goal is the 100 kW class FEL light and a few tens MW class electron beam output in average, quasi continuous wave operation of the light and electron beam will be planned in the JAERI superconducting rf linac based FEL facility. Conceptual design options needed for such a very high power operation and shorter wavelength light sources will be discussed to improve and to upgrade the exciting facility. (author)

  3. Investigation regarding the amount of disused components and the radioactive inventory at Mutsu Establishment, JAERI

    Hatanaka, Kazuo; Ooeda, Etsurou; Watanabe, Masaaki

    2003-01-01

    About 200 tons of the disused components, which were used for fuel removal, are stored in Mutsu Establishment, Japan Atomic Energy Research Institute (JAERI). In order to settle the decommissioning plan, RANDEC made an investigation regarding the amount of disused components and the radioactive inventory in Mutsu Establishment under a contract with JAERI. This report describes the estimation results of radioactive inventory and weight of radioactive wastes regarding the disused equipment such as an ion-exchange resin tank, a injection pump and equipment for fuel removal. (author)

  4. Present status of spallation target development. JAERI/KEK Joint Project

    Hino, R.; Kaminaga, M.; Haga, K.

    2001-01-01

    The Japan Atomic Energy Research Institute (JAERI) and the High Energy Accelerator Research Organization (KEK) are promoting a plan to construct a neutron scattering facility under the JAERI/KEK Joint Project. Design and R and D works are being carried out vigorously for realizing the mercury target system consisting of the mercury target, moderators and reflectors working as a spallation neutron source, as well as a remote handling system for exchanging such components which will be highly irradiated. This report introduces an outline of the present status of design and development activities on the spallation target system. (author)

  5. Extended abstracts of the 12th JAERI workshop on high-Tc superconductors

    Hojou, Kiichi; Okayasu, Satoru; Sasase, Masato [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Ishida, Takekazu [Osaka Prefectual Univ., Sakai (JP)] (eds.)

    2001-03-01

    This workshop was held on December 7-8, 2000 at JAERI (Tokai). The research group at JAERI shares a responsibility for material modification of high-Tc superconductors by irradiation in 'the multi-core project II of the high temperature superconducting material research' organized by STA (Science and Technology Agency) of Japan. This report contains the extended abstracts of workshop presentations covering basic theories, various experimental results and material improvement studies of the superconductivity by high energy ion irradiation. The twelve presentations of the workshop were devoted to a mini symposium where the direct observations of vortices were discussed in view of the various sophisticated techniques. (author)

  6. Production of heavy element and search for new isotopes at JAERI-RMS

    Ikuta, Tomohiko [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1997-07-01

    The new neutron deficient isotope {sup 209}Th and {sup 212}Pa have been produced in heavy ion induced fusion evaporation reactions. The evaporation residues were separated in-flight by the JAERI recoil mass separator (JAERI-RMS). The {alpha}-decay energy of {sup 209}Th and {sup 212}Pa are 8.080(50) MeV and 8.270(30) MeV, respectively. The corresponding half-lives are 3.8{sub -1.5}{sup +6.9} ms and 5.1{sub -1.9}{sup +6.1} ms. (author)

  7. Extended abstracts of the 12th JAERI workshop on high-Tc superconductors

    Hojou, Kiichi; Okayasu, Satoru; Sasase, Masato

    2001-03-01

    This workshop was held on December 7-8, 2000 at JAERI (Tokai). The research group at JAERI shares a responsibility for material modification of high-Tc superconductors by irradiation in 'the multi-core project II of the high temperature superconducting material research' organized by STA (Science and Technology Agency) of Japan. This report contains the extended abstracts of workshop presentations covering basic theories, various experimental results and material improvement studies of the superconductivity by high energy ion irradiation. The twelve presentations of the workshop were devoted to a mini symposium where the direct observations of vortices were discussed in view of the various sophisticated techniques. (author)

  8. Nuclear Safety Research Reactor (NSRR) program in JAERI

    Ishikawa, M.; Hoshi, T.; Ohnishi, N.; Fujishiro, T.; Inabe, T.

    1974-01-01

    An experimental research program, named Nuclear Safety Research Reactor (NSRR) Program, has been progressing in Japan Atomic Energy Research Institute (JAERI) using a modified TRIGA-ACPR. This paper is prepared to describe the outline of the NSRR program. The purpose of the NSRR program is to examine the behaviors of fuel rods under various accidental conditions of power reactors so as to establish realistic safety criteria and to develop analytical models for prediction of fuel failures. We expect to contribute finally to the improvement of reactor design and fuel fabrication techniques based on these experimental results. The NSRR experiments will be performed in the large central experimental tube, which is one of the most excellent features of this reactor, using specially designed capsules or loops which can accommodate up to 49 BWR type test fuels. Many types of test fuels in various conditions will be examined by the NSRR program, such as BWR, PWR and FBR type fuels from the beginning of life to the end of life with and without simulated reactor internal structures. The experiments will be continued for more than 10 years divided into three phases. The first phase of the program will be devoted to the experiments pertaining to reactivity initiated accidents (RIA). In these experiments we will make use of the excellent pulsing capability of ACPR, which is expected to generate 100 MW-sec prompt energy release with 1.3 msec of minimum reactor period by 4.7 dollar reactivity insertion and to yield more than 280 cal/g-UO 2 heat deposit even in an approximately 10% enriched BWR type test fuel. (280 cal/g-UO 2 is believed enough heat deposit to cause fuel failure.) In general, heat flow behaviors from fuel meat to clad and from clad to coolant are very complex phenomena, but they are the key point in analyzing transient response of fuels. In the sudden heat transient conditions brought by pulsing, however, it will be possible to examine each phenomenon separately

  9. Nuclear Safety Research Reactor (NSRR) program in JAERI

    Ishikawa, M; Hoshi, T; Ohnishi, N; Fujishiro, T; Inabe, T [Japan Atomic Energy Research Institute (Japan)

    1974-07-01

    An experimental research program, named Nuclear Safety Research Reactor (NSRR) Program, has been progressing in Japan Atomic Energy Research Institute (JAERI) using a modified TRIGA-ACPR. This paper is prepared to describe the outline of the NSRR program. The purpose of the NSRR program is to examine the behaviors of fuel rods under various accidental conditions of power reactors so as to establish realistic safety criteria and to develop analytical models for prediction of fuel failures. We expect to contribute finally to the improvement of reactor design and fuel fabrication techniques based on these experimental results. The NSRR experiments will be performed in the large central experimental tube, which is one of the most excellent features of this reactor, using specially designed capsules or loops which can accommodate up to 49 BWR type test fuels. Many types of test fuels in various conditions will be examined by the NSRR program, such as BWR, PWR and FBR type fuels from the beginning of life to the end of life with and without simulated reactor internal structures. The experiments will be continued for more than 10 years divided into three phases. The first phase of the program will be devoted to the experiments pertaining to reactivity initiated accidents (RIA). In these experiments we will make use of the excellent pulsing capability of ACPR, which is expected to generate 100 MW-sec prompt energy release with 1.3 msec of minimum reactor period by 4.7 dollar reactivity insertion and to yield more than 280 cal/g-UO{sub 2} heat deposit even in an approximately 10% enriched BWR type test fuel. (280 cal/g-UO{sub 2} is believed enough heat deposit to cause fuel failure.) In general, heat flow behaviors from fuel meat to clad and from clad to coolant are very complex phenomena, but they are the key point in analyzing transient response of fuels. In the sudden heat transient conditions brought by pulsing, however, it will be possible to examine each phenomenon

  10. Recent progress in application of JAERI alanine/ESR dosimetry system

    Kojima, T.

    1995-01-01

    Feasibility studies of application of JAERI alanine/ESR dosimetry system were performed on radiotherapy level dosimetry, low dose-rate dosimetry for residual life estimation of cable insulators used in nuclear power facilities, and dose monitoring for electron processing. (author)

  11. JAERI TANDEM, LINAC and V.D.G. annual report 1989

    1990-09-01

    This annual report describes research activities which have been performed with the JAERI tandem accelerator, the electron linear accelerator and the Van de Graaff accelerator from April 1, 1989 to March 31, 1990. Summary reports of 49 papers, and list of publications, personnel and cooperative researches with universities are contained. (author)

  12. JAERI tandem and V.D.G. annual report 1998. April 1, 1998 - March 31, 1999

    NONE

    1999-12-01

    This annual report describes research activities which have been performed with the JAERI tandem accelerator and the Van de Graaff accelerator from April 1, 1998 to March 31, 1999. Summary reports of 38 papers, and lists of publication, personnel and cooperative research with universities and contained. (author)

  13. Historical evolution of nuclear energy systems development and related activities in JAERI. Fission, fusion, accelerator utilization

    Tone, Tatsuzo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2001-03-01

    Overview of the historical evolution of nuclear energy systems development and related activities in JAERI is given in the report. This report reviews the research and development for light water reactor, fast breeder reactor, high temperature gas reactor, fusion reactor and utilization of accelerator-based neutron source. (author)

  14. JAERI tandem annual report 2002. April 1, 2002 - March 31, 2003

    Takeuchi, Suehiro; Oshima, Masumi; Ishii, Tetsuro; Nagame, Yuichiro; Chiba, Satoshi; Sataka, Masao

    2003-11-01

    This annual report describes research activities which have been performed with the JAERI tandem accelerator and the Van de Graaff accelerator from April 1, 2002 to March 31, 2003. Summary reports of 54 papers, and lists of publication, personnel and cooperative research with universities are contained. (author)

  15. JAERI tandem and V.D.G. annual report 1997. April 1, 1997 - March 31, 1998

    Takeuchi, Suehiro; Ikezoe, Hiroshi; Chiba, Satoshi; Sataka, Masao; Nagame, Yuichiro; Takemori, Satoshi; Iwamoto, Akira

    1998-10-01

    This annual report describes research activities which have been performed with the JAERI tandem accelerator and the Van de Graaff accelerator from April 1, 1997 to March 31, 1998. Summary reports of 40 papers, and lists of publication, personnel and cooperative researches with universities are contained. (author)

  16. JAERI TANDEM and V.D.G. annual report 1992 April 1, 1992 - March 31, 1993

    1993-09-01

    This annual report describes research activities which have been performed with the JAERI tandem accelerator and the Van de Graaff accelerator from April 1, 1992 to March 31, 1993. Summary reports of 41 papers, and list of publications, personnel and cooperative researches with universities are contained. (author)

  17. JAERI tandem, linac and V.D.G. annual report 1984

    Shikazono, Naomoto; Iizumi, Masashi; Ishii, Mitsuhiko; Kawarasaki, Yuuki; Murayama, Michio; Okashita, Hiroshi; Ozawa, Kunio; Suto, Yoichi

    1985-07-01

    This annual report describes research activities which have been performed with the JAERI tandem accelerator, the electron linear accelerator and the Van de Graaff accelerator from April 1, 1984 to March 31, 1985. Summary reports of 53 papers, publications, personnel and a list of cooperative researches with universities are contained. (author)

  18. JAERI tandem, linac and V.D.G. annual report 1987

    1988-10-01

    This annual report describes research activities which have been performed with the JAERI tandem accelerator, the electron linear accelerator and the Van de Graaff accelerator from April 1, 1987 to March 31, 1988. Summary reports of 49 papers, and list of publications, personnel and cooperative researches with universities are contained. (author)

  19. JAERI TANDEM and V.D.G. annual report 1994. April 1, 1994 - March 31, 1995

    Suzuki, Yasuo; Ikezoe, Hiroshi; Iwamoto, Akira; Sataka, Masao; Shinohara, Nobuo; Takeuchi, Suehiro; Shoji, Tokio; Okabe, Takashi

    1995-10-01

    This annual report describes research activities which have been performed with the JAERI tandem accelerator and the Van de Graaff accelerator from April 1, 1994 to March 31, 1995. Summary reports of 47 papers, and list of publications, personnel and cooperative researches with universities are contained. (author)

  20. Recent activity on the post-irradiation analyses of nuclear fuels and actinide samples at JAERI

    Shinohara, Nobuo; Nakahara, Yoshinori; Kohno, Nobuaki; Tsujimoto, Kazufumi

    2003-01-01

    Radiochemical analyses of spent fuels have been carried out at JAERI for contributing to the development of nuclear technologies, where several samples from research reactors and nuclear power plants were analyzed to obtain isotopic compositions and burnups. The history and procedures of the radiochemical analyses are depicted and some recent results are given in this paper. (author)

  1. JAERI tandem annual report 2001. April 1, 2001 - March 31, 2002

    Takeuchi, Suehiro; Ikezoe, Hiroshi; Chiba, Satoshi; Nagame, Yuichiro; Sataka, Masao; Iwamoto, Akira (eds.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2002-11-01

    This annual report describes research activities which have been performed with the JAERI tandem accelerator and the Van de Graaff accelerator from April 1, 2001 to March 31, 2002. Summary reports of 48 papers, and lists of publication, personnel and cooperative research with universities are contained. (author)

  2. JAERI TANDEM annual report 2000. April 1, 2000 - March 31, 2001

    Takeuchi, Suehiro; Ikezoe, Hiroshi; Chiba, Satoshi; Nagame, Yuichiro; Sataka, Masao; Iwamoto, Akira [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] (eds.)

    2001-11-01

    This annual report describes research activities which have been performed with the JAERI tandem accelerator and the Van de Graaff accelerator from April 1, 2000 to March 31, 2001. Summary reports of 46 papers, and lists of publication, personnel and cooperative research with universities are contained. (author)

  3. JAERI TANDEM and V.D.G. annual report 1995. April 1, 1995 - March 31, 1996

    Takeuchi, Suehiro; Ikezoe, Hiroshi; Iwamoto, Akira; Sataka, Masao; Nagame, Yuichiro; Shoji, Tokio; Okabe, Takashi; Maekawa, Hiroshi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; eds.

    1996-08-01

    This annual report describes research activities which have been performed with the JAERI Tandem accelerator and the Van de Graaff accelerator from April 1, 1995 to March 31, 1996. Summary reports of 59 papers, and list of publications, personnel and cooperative researches with universities are contained. (author)

  4. JAERI tandem and V.D.G. annual report 1993. April 1, 1993 - March 31, 1994

    Suzuki, Yasuo; Ikezoe, Hiroshi; Iwamoto, Akira; Kazumata, Yukio; Shinohara, Nobuo; Takeuchi, Suehiro; Okabe, Takashi

    1994-11-01

    This annual report describes research activities which have been performed with the JAERI tandem accelerator and the Van de Graaff accelerator from April 1, 1993 to March 31, 1994. Summary reports of 43 papers, and list of publications, personnel and cooperative researches with universities are contained. (author)

  5. Annual report on neutron scattering studies in JAERI, July 1, 1977 - August 31, 1978

    Hamaguchi, Yoshikazu; Iizumi, Masashi; Endoh, Yasuo

    1978-12-01

    Neutron scattering studies carried out by Division of Physics, JAERI, and several universities with neutron beam facilities at JRR-2 and 3 in Tokai are described for the period from July, 1977 to August, 1978. Contents are 51 individual reports and list of publicatios during the period. (author)

  6. A proposal for study of ion-beam induced chemical reactions using JAERI tandem accelerator

    1985-11-01

    Problems in ion-beam induced chemical reactions using JAERI Tandem Accelerator were discussed. Research philosophy, some proposed experiments which are based on measurements during ion-beam bombardment, and main features of the experimental apparatus are briefly described in this report. (author)

  7. Present status and future directions of the JAERI superconducting RF linac-based FEL

    Minehara, EJ.; Yamauchi, T.; Sugimori, M.; Sawamura, M.; Hajima, R.; Nagai, R.; Kikuzawa, N.; Nishimori, N.; Shizuma, T.

    2000-01-01

    The JAERI superconducting rf linac based FEL has successfully been lased to produce a 2.34kW FEL light and l00kW electron beam output in quasi continuous wave operation in February 2000. Twice larger output than the present program goal of 1kW was achieved to improve the optical out coupling method in the FEL optical resonator, the electron gun, and the electron beam optics in the JAERI FEL driver. As our next 2 years program goal is the 100kW class FEL light and a few MW class electron beam output in average, quasi continuous wave operation of the light and electron beam will be planned in the JAERI superconducting rf linac based FEL facility. Conceptual and engineering design options needed for such a very high power operation will be discussed to improve and to upgrade the existing facility. Finally, several applications, table-top superconducting rf linac based FELs, and an X-ray FEL R and D will be discussed as a next-five years program at JAERI-FEL laboratory. (author)

  8. Next generation neutron scattering at Neutron Science Center project in JAERI

    Yamada, Yasusada; Watanabe, Noboru; Niimura, Nobuo; Morii, Yukio; Katano, Susumu; Aizawa, Kazuya; Suzuki, Jun-ichi; Koizumi, Satoshi; Osakabe, Toyotaka.

    1997-01-01

    Japan Atomic Energy Research Institute (JAERI) has promoted neutron scattering researches by means of research reactors in Tokai Research Establishment, and proposes 'Neutron Science Research Center' to develop the future prospect of the Tokai Research Establishment. The scientific fields which will be expected to progress by the neutron scattering experiments carried out at the proposed facility in the Center are surveyed. (author)

  9. From neutron science project to J-PARC. From the viewpoint of JAERI

    Oyama, Yukio

    2006-01-01

    Japan Atomic Energy Research Institute (JAERI), at present Japan Atomic Energy Agency (JAEA), has been developing particle accelerators since its establishment in 1956 for obtaining basic data on the neutron. Also reactor-based neutron sciences have been developed at JAERI/JAEA. Under the so-called omega project which was started in 1988, JAERI/JAEA has been conducting researches on Engineering Test Accelerator for the nuclear transmutation and has built a Basic Test Accelerator. In 1996, a special team for neutron science promotion was organized and pushed R and D works on proton accelerators, targets, neutron engineering, radiation safety and so on. Integration of proton accelerator projects at JAERI and KEK (Institute for High Energy Physics) was proposed in 1998, and both institutes agreed to establish a unified proton accelerator facility, J-PARC. JAEA is promoting the industrial application of neutrons. Also the research on nuclear transmutation at J-PARC, which is not endorsed yet, is an essential objective for JAEA. (K.Y.)

  10. JAERI Tandem, LINAC and V.D.G. annual report 1986

    1987-08-01

    This annual report describes research activities which have been performed with the JAERI tandem accelerator, the electron linear accelerator and the Van de Graaff accelerator from April 1, 1986 to March 31, 1987. Summary reports of 55 papers, and list of publications, personnel and cooperative researches with universities are contained. (author)

  11. JAERI tandem annual report 1999. April 1, 1999 - March 31, 2000

    NONE

    2000-11-01

    This annual report describes research activities which have been performed with the JAERI tandem accelerator and the Van de Graaff accelerator from April 1, 1999 to March 31, 2000. Summary reports of 49 papers, and lists of publication, personnel and cooperative research with universities are contained. (author)

  12. Annual report on neutron scattering studies in JAERI, July, 1976 - June, 1977

    Hamaguchi, Yoshikazu; Iizumi, Masashi; Endoh, Yasuo

    1977-11-01

    Neutron scattering studies carried out by Division of Physics, JAERI and by several universities utilizing facilities in Tokai are reported for the period of July, 1976 to June, 1977. The report contains 39 short papers submitted by authors on their individual studies. (auth.)

  13. JAERI tandem, LINAC and V.D.G. annual report 1988

    1989-09-01

    This annual report describes research activities which have been performed with the JAERI tandem accelerator, the electron linear accelerator and the Van de Graaff accelerator from April 1, 1988 to March 31, 1989. Summary reports of 45 papers, and list of publications, personnel and cooperative researches with universities are contained. (author)

  14. JAERI TANDEM, LINAC and V.D.G. annual report, 1985

    1986-08-01

    This annual report describes research activities which have been performed with the JAERI tandem accelerator, the electron linear accelerator and the Van de Graaff accelerator from April 1, 1985 to March 31, 1986. Summary reports of 52 papers, and list of publications, personnel and cooperative researches with universities are contained. (author)

  15. JAERI TANDEM and V.D.G. annual report 1996. April 1, 1996 - March 31, 1997

    Takeuchi, Suehiro; Ikezoe, Hiroshi; Iwamoto, Akira; Sataka, Masao; Nagame, Yuichiro; Shoji, Tokio; Okabe, Takashi; Maekawa, Hiroshi

    1997-09-01

    This annual report describes research activities which have been performed with the JAERI tandem accelerator and the Van de Graaf accelerator from April 1, 1996 to March 31, 1997. Summary reports of 48 papers, and list of publications, personnel and cooperative researches with universities are contained. (author)

  16. JAERI TANDEM and V.D.G. annual report 1994. April 1, 1994 - March 31, 1995

    Suzuki, Yasuo; Ikezoe, Hiroshi; Iwamoto, Akira; Sataka, Masao; Shinohara, Nobuo; Takeuchi, Suehiro; Shoji, Tokio; Okabe, Takashi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; eds.

    1995-10-01

    This annual report describes research activities which have been performed with the JAERI tandem accelerator and the Van de Graaff accelerator from April 1, 1994 to March 31, 1995. Summary reports of 47 papers, and list of publications, personnel and cooperative researches with universities are contained. (author).

  17. Workshop of Advanced Science Research Center, JAERI. Nuclear physics and nuclear chemistry of superheavy elements

    Nishio, Katsuhisa; Nishinaka, Ichiro; Ikezoe, Hiroshi; Nagame, Yuichiro

    2004-03-01

    A liquid drop model predicts that the fission barrier of a nucleus whose atomic number (Z) is larger than 106 disappears, so that such heavier nuclei as Z > 106 cannot exist. The shell effect, however, drastically changes structure of the fission barrier and stabilizes nucleus against fission, predicting the presence of super heavy element (SHE, Z=114-126) with measurable half-life. In the SHE region, a wave function of outermost electron of an atom, which controls chemical properties of an elements, is disturbed or changed by relativistic effects compared to the one from the non-relativistic model. This suggests that the SHEs have different chemical properties from those of lighter elements belonging to the same family. The chemistry of SHEs requires event by event analysis to reveal their chemical properties, thus is called 'atom-at-a-time chemistry'. Japan Atomic Energy Research Institute (JAERI) has been investigating fusion mechanism between heavy nuclei to find out favorable reactions to produce SHE by using JAERI-tandem and booster accelerator. In the JAERI-tandem facility, isotopes of Rf and Db are produced by using actinide targets such as 248 Cm in order to investigate their chemical properties. The present workshop was held in Advanced Science Research Center of JAERI at February 27-28 (2003) in order to discuss current status and future plans for the heavy element research. The workshop also included topics of the radioactive nuclear beam project forwarded by the JAERI-KEK cooperation and the nuclear transmutation facility of J-PARC. Also included is the nuclear fission process as a decay characteristic of heavy elements. There were sixty participants in the workshop including graduate and undergraduate eleven students. We had guests from Germany and Hungary. Through the workshop, we had a common knowledge that researches on SHE in Japan should fill an important role in the world. (author)

  18. The JAERI-KEK joint project on high intensity proton accelerator and overview of nuclear transmutation experimental facilities

    Ikeda, Yujiro

    2001-01-01

    A status of the JAERI/KEK joint project on High Intensity Proton Accelerator is overviewed. It is highlighted that Experimental facilities for development of the accelerator driven system (ADS) for nuclear transmutation technology is proposed under the project. (author)

  19. The JAERI and Universities joint project research reports on the 4th joint research project between JAERI and Universities on backend chemistry

    NONE

    2003-02-01

    In the Joint Research Project between JAERI and Universities on Backend Chemistry, the 4th-term researches of it were performed on sixteen themes from April of 1999 to March of 2001 under the four categories, i.e. Nuclear-chemistry and physical-chemistry properties of actinides', 'Solid state chemistry and nuclear fuel engineering of actinides', 'Solution chemistry and technologies for separation and analysis of actinides' and Treatment of radioactive waste and environmental chemistry'. The present report compiled the papers contributed to the Joint Research Project. (author)

  20. JAERI 200 kV electron gun with an NEA-GaAs photocathode

    Nishitani, Tomohiro; Minehara, Eisuke J.; Hajima, Ryoichi; Nagai, Ryoji; Sawamura, Masaru; Nishimori, Nobuyuki; Kikuzawa, Nobuhiro; Yamauchi, Toshihiko

    2004-01-01

    The photocathode DC-gun with high average current, low beam emittance and long operational lifetime is considered to be indispensable for ERL-FEL. We have started the development program of a 200 keV electron gun with the NEA-GaAs photocathode for the first time in JAERI. In order to long an NEA surface lifetime, the JAERI 200 kV electron gun system consists of a 200 kV DC-gun chamber on extreme high vacuum condition and an NEA activation chamber with load-lock system. We report the goal of photocathode DC-gun R and D and the schedule of a developmental program. (author)

  1. HRB-22 capsule irradiation test for HTGR fuel. JAERI/USDOE collaborative irradiation test

    Minato, Kazuo; Sawa, Kazuhiro; Fukuda, Kousaku [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; and others

    1998-03-01

    As a JAERI/USDOE collaborative irradiation test for high-temperature gas-cooled reactor fuel, JAERI fuel compacts were irradiated in the HRB-22 irradiation capsule in the High Flux Isotope Reactor at the Oak Ridge National Laboratory (ORNL). Postirradiation examinations also were performed at ORNL. This report describes 1) the preirradiation characterization of the irradiation samples of annular-shaped fuel compacts containing the Triso-coated fuel particles, 2) the irradiation conditions and fission gas releases during the irradiation to measure the performance of the coated particle fuel, 3) the postirradiation examinations of the disassembled capsule involving visual inspection, metrology, ceramography and gamma-ray spectrometry of the samples, and 4) the accident condition tests on the irradiated fuels at 1600 to 1800degC to obtain information about fuel performance and fission product release behavior under accident conditions. (author)

  2. Project of the JAERI superconducting AVF cyclotron for applications in biotechnology and materials science

    Miyawaki, Nobumasa; Kurashima, Satoshi; Okumura, Susumu; Chiba, Atsuya; Agematsu, Takashi; Kamiya, Tomihiro; Kaneko, Hirohisa; Nara, Takayuki; Saito, Yuichi; Ishii, Yasuyuki; Sakai, Takuro; Mizuhashi, Kiyoshi; Fukuda, Mitsuhiro; Yokota, Watalu; Arakawa, Kazuo

    2005-01-01

    A project for expanding TIARA (Takasaki Ion accelerators for Advanced Radiation Application) facilities of JAERI has been proposed to broaden application region of biotechnology and materials science. As a result of the investigation of TIARA facility user's request, energy increase up to more than 100 MeV/n for heavy ions and up to 300 MeV for proton are strongly required. The magnet of a superconducting AVF cyclotron with a K number of 900 has been designed to cope with acceleration of both 150 MeV/n heavy ions and 300 MeV protons. The lower limit of energies has been investigated to overlap the energy region covered by the JAERI AVF cyclotron, required to increase beam time for present users. We have designed a beam transport system to satisfy various requirements of the applications. (author)

  3. Analyses of superradiance and spiking-mode lasing observed at JAERI-FEL

    Hajima, R; Nagai, R; Minehara, E J

    2001-01-01

    Japan Atomic Energy Research Institute (JAERI)-FEL has achieved quasi-CW lasing with an average power of 1.7 kW, the initial goal of the R and D program. The FEL extraction efficiency obtained completely exceeds the well-known limit for non-bunched beam, which is determined by the number of undulator periods. We have conducted numerical studies to characterize lasing dynamics observed at JAERI-FEL. Cavity-length detuning curves numerically obtained show good agreement with experimental results. Lasing behavior numerically obtained exhibits chaotic spiking-mode and superradiance as the cavity-length detuning approaches zero. Broadening of lasing spectrum observed in the experiments is explained by these lasing dynamics. The extraction efficiency becomes maximal at the perfect synchronization of the cavity length, where the lasing is quasi-stationary superradiance. We also compare these results with analytical theory previously reported.

  4. JAERI Fuel Cleanup System (J-FCU) stand-alone tritium test at the TSTA

    Konishi, Satoshi; Hayashi, Takumi; Inoue, Masahiko

    1993-03-01

    JAERI designed, fabricated, and installed the JAERI Fuel Cleanup System (J-FCU) as a subsystem of simulated fusion fuel loop at the TSTA. The main function of the J-FCU is to purify and to recover hydrogen isotopes from simulated plasma exhaust while exhausting tritium free impurities. After a lot of deuterium tests, a first tritium test of the J-FCU was performed with one gram of tritium at the TSTA on June 1991. Main purpose of this test was to evaluate the total integrity and function of the J-FCU system with a DT mixture. Through this test, the J-FCU was operated well and its function with tritium was demonstrated. This report describes the detail test results of the J-FCU first tritium test and discuss its functions by stand-alone mode. Residual tritium inventory of the J-FCU system was also discussed. (author)

  5. Status of RF system for the JAERI energy-recovery linac FEL

    Sawamura, Masaru; Nagai, Ryoji

    2006-01-01

    The two types of the RF sources are used for the JAERI ERL-FEL. One is an all-solid state amplifier and the other is an inductive output tube (IOT). There are advantages of little failure and wide bandwidth for the all-solid state amplifier, low cost and high efficiency for IOT. The property of low cost with the IOT is suitable for a large machine like an energy recovery linac (ERL)

  6. JAERI TIARA annual report 1994. V.4. April 1994 - March 1995

    Tanaka, Ryuichi; Seguchi, Tadao; Nashiyama, Isamu [Japan Atomic Energy Research Inst., Takasaki, Gunma (Japan). Takasaki Radiation Chemistry Research Establishment; eds.; and others

    1995-10-01

    This annual report describes research activities which have been performed with the JAERI TIARA (Takasaki Ion Accelerators for Advanced Radiation Application) facilities from April 1, 1994 to March 31, 1995. Summary reports of 86 papers and briaf descriptions on status of TIARA in the period are contained. A list of publications, the type of research collaborations and organization of TIARA are also given as appendices. (author).

  7. JAERI TIARA annual report vol. 3 (1993). April 1993 - March 1994

    Ishigaki, Isao; Tanaka, Ryuichi; Seguchi, Tadao

    1994-11-01

    This annual report describes research activities which have been performed with the JAERI TIARA (Takasaki Ion Accelerators for Advanced Radiation Application) facilities from April 1, 1993 to March 31, 1994. Summary reports of 80 papers and brief descriptions on status of TIARA in the period are contained. A list of publications, the type of research collaborations and organization of TIARA are also given as appendices. (author)

  8. Development of a distributed control system for the JAERI tandem accelerator facility

    Hanashima, Susumu

    2005-01-01

    In the JAERI tandem accelerator facility, we are building accelerator complex aiming generation and acceleration of radio nuclear beam. Several accelerators, ion sources and a charge breeder are installed in the facility. We are developing a distributed control system enabling smooth operation of the facility. We report basic concepts of the control system in this article. We also describe about a control hardware using plastic optical fiber, which is developed for the control system. (author)

  9. Report of the research results with JAERI's facilities in fiscal 1975

    1976-07-01

    Results of the research works by educational institutions using facilities of the Japan Atomic Energy Research Institute in fiscal 1975 are reported in individual summaries. Facilities utilized are research reactors, Co-60 irradiation facilities, hot laboratory, Linac and electron accelerators. Fields of research are the following: nuclear physics, radiation damage/solid-state physics, positron annihilation, activation analysis/nuclear chemistry, hot atom chemistry, irradiation effects, biology, and neutron diffraction; and, cooperative works to JAERI. (Mori, K.)

  10. Status and future program of reactor physics experiments in JAERI Critical facilities, FCA and TCA

    Okajima, Shigeaki; Osugi, Toshitaka; Nakajima, Ken; Suzaki, Takenori; Miyoshi, Yoshinori

    1999-01-01

    The critical facilities in JAERI, FCA (Fast Critical Assembly) and TCA (Tank-type Critical Assembly), have been used to provide integral data for evaluation of nuclear data as well as for development of various types of reactor since they went critical in 1960's. In this paper a review is presented on the experimental programs in both facilities. And the experimental programs in next 5 years are also shown. (author)

  11. JAERI TIARA annual report 1995. V. 5. April 1995 - March 1996

    Tanaka, Ryuichi; Seguchi, Tadao; Ohmichi, Hideki

    1997-01-01

    This annual report describes research activities which have been performed with the JAERI TIARA (Takasaki Ion Accelerators for Advanced Radiation Application) facilities from April 1, 1995 to March 31, 1996. Summary reports of 84 papers and briaf descriptions on status of TIARA in the period are contained. A list of publications, the type of research collaborations and organization of TIARA are also given as appendices. (author)

  12. JAERI TIARA annual report 1994. V.4. April 1994 - March 1995

    Tanaka, Ryuichi; Seguchi, Tadao; Nashiyama, Isamu

    1995-10-01

    This annual report describes research activities which have been performed with the JAERI TIARA (Takasaki Ion Accelerators for Advanced Radiation Application) facilities from April 1, 1994 to March 31, 1995. Summary reports of 86 papers and briaf descriptions on status of TIARA in the period are contained. A list of publications, the type of research collaborations and organization of TIARA are also given as appendices. (author)

  13. Transport calculation of thermal and cold neutrons using NMTC/JAERI-MCNP4A code system

    Iga, Kiminori; Takada, Hiroshi; Nagao, Tadashi.

    1998-01-01

    In order to investigate the applicability of the NMTC/JAERI-MCNP4A code system to the neutronics design study in the neutron science research project of JAERI, transport calculations of thermal and cold neutrons are performed with the code system on a spallation neutron source composed of light water cooled tantalum target with a moderator and a reflector system. The following neutronic characteristics are studied in the calculation : the variation of the intensity of neutrons emitted from a light water moderator or a liquid hydrogen with/without the B 4 C decoupler, which are installed to produce sharp pulse, and that dependent on the position of external source neutrons in the tantalum target. The calculated neutron energy spectra are reproduced well by the semi-empirical formula with the parameter values reliable in physical meanings. It is found to be necessary to employ proper importance sampling technique in the statistics. It is confirmed from this work that the NMTC/JAERI-MCNP4A code system is applicable to the neutronics design study of spallation neutron sources proposed for the neutron science research project. (author)

  14. Transport calculation of thermal and cold neutrons using NMTC/JAERI-MCNP4A code system

    Iga, Kiminori [Kyushu Univ., Fukuoka (Japan); Takada, Hiroshi; Nagao, Tadashi

    1998-01-01

    In order to investigate the applicability of the NMTC/JAERI-MCNP4A code system to the neutronics design study in the neutron science research project of JAERI, transport calculations of thermal and cold neutrons are performed with the code system on a spallation neutron source composed of light water cooled tantalum target with a moderator and a reflector system. The following neutronic characteristics are studied in the calculation : the variation of the intensity of neutrons emitted from a light water moderator or a liquid hydrogen with/without the B{sub 4}C decoupler, which are installed to produce sharp pulse, and that dependent on the position of external source neutrons in the tantalum target. The calculated neutron energy spectra are reproduced well by the semi-empirical formula with the parameter values reliable in physical meanings. It is found to be necessary to employ proper importance sampling technique in the statistics. It is confirmed from this work that the NMTC/JAERI-MCNP4A code system is applicable to the neutronics design study of spallation neutron sources proposed for the neutron science research project. (author)

  15. Verification of the computational dosimetry system in JAERI (JCDS) for boron neutron capture therapy

    Kumada, H; Yamamoto, K; Matsumura, A; Yamamoto, T; Nakagawa, Y; Nakai, K; Kageji, T

    2004-01-01

    Clinical trials for boron neutron capture therapy (BNCT) by using the medical irradiation facility installed in Japan Research Reactor No. 4 (JRR-4) at Japan Atomic Energy Research Institute (JAERI) have been performed since 1999. To carry out the BNCT procedure based on proper treatment planning and its precise implementation, the JAERI computational dosimetry system (JCDS) which is applicable to dose planning has been developed in JAERI. The aim of this study was to verify the performance of JCDS. The experimental data with a cylindrical water phantom were compared with the calculation results using JCDS. Data of measurements obtained from IOBNCT cases at JRR-4 were also compared with retrospective evaluation data with JCDS. In comparison with phantom experiments, the calculations and the measurements for thermal neutron flux and gamma-ray dose were in a good agreement, except at the surface of the phantom. Against the measurements of clinical cases, the discrepancy of JCDS's calculations was approximately 10%. These basic and clinical verifications demonstrated that JCDS has enough performance for the BNCT dosimetry. Further investigations are recommended for precise dose distribution and faster calculation environment

  16. JAERI R & D on accelerator-based transmutation under OMEGA program

    Takizuka, T.; Nishida, T.; Mizumoto, M. [Japan Atomic Energy Research Institute, Ibaraki-ken (Japan)] [and others

    1995-10-01

    The overview of the Japanese long-term research and development program on nuclide partitioning and transmutation, called {open_quotes}OMEGA,{close_quotes} is presented. Under this national program, major R&D activities are being carried out at JAERI, PNC, and CRIEPI. Accelerator-based transmutation study at JAERI is focused on a dedicated transmutor with a subcritical actinide-fueled subcritical core coupled with a spallation target driven by a high intensity proton accelerator. Two types of system concept, solid system and molten-salt system, are discussed. The solid system consists of sodium-cooled tungsten target and metallic actinide fuel. The molten-salt system is fueled with molten actinide chloride that acts also as a target material. The proposed plant transmutes about 250 kg of minor actinide per year, and generates enough electricity to power its own accelerator. JAERI is proposing the development of an intense proton linear accelerator ETA with 1.5 GeV-10 mA beam for engineering tests of accelerator-based transmutation. Recent achievements in the accelerator development are described.

  17. Proceedings of the first JAERI-Kansai international workshop on ultrashort-pulse ultrahigh-power lasers and simulation for laser-plasma interactions

    1998-03-01

    Records of the First JAERI-Kansai International Workshop, which focused on the subject of 'Ultrashort-Pulse Ultrahigh-Power Lasers and Simulation for Laser-Plasma Interactions', are contained in this issue. The First JAERI-Kansai International Workshop was held as Joint ICFA/JAERI-Kansai International Workshop '97 with International Committee for Future Accelerators (ICFA). This report consists of 24 contributed papers. (J.P.N.)

  18. Proceedings of the first JAERI-Kansai international workshop on ultrashort-pulse ultrahigh-power lasers and simulation for laser-plasma interactions

    NONE

    1998-03-01

    Records of the First JAERI-Kansai International Workshop, which focused on the subject of `Ultrashort-Pulse Ultrahigh-Power Lasers and Simulation for Laser-Plasma Interactions`, are contained in this issue. The First JAERI-Kansai International Workshop was held as Joint ICFA/JAERI-Kansai International Workshop `97 with International Committee for Future Accelerators (ICFA). This report consists of 24 contributed papers. (J.P.N.)

  19. Ex-post evaluation. Research independency of the basic science study of JAERI

    Yanagisawa, Kazuaki; Takahashi, Shoji

    2010-06-01

    A research independency was defined here as the continuity and the development of a corresponding research field with an evolution of history. The authors took three fields as research parameters for the ex-post evaluation. They were all belonged to the basic science field studied in the Japan Atomic Energy Research Institute (JAERI). The first parameter was actinides, which was situated in the center of research networking from the viewpoint of socio-economy. The second parameter was positron, which was situated in the periphery of research networking and the third one was neutron, which had competition with other research organizations in Japan. The three were supported and promoted financially by the JAERI. The target year was covered from 1978 to 2002, a 25-years. INIS (International Nuclear Information Systems) operated by the International Atomic Energy Agency (IAEA) was used as the tool for the present bibliometric study. It was revealed that important factors that led the sustainable success of the research independency were the constant efforts to accomplish their mission, the education of their successors to instructing the explicit and tacit research findings and the construction of intellectual networking with learned circles and industries, those were in good collaboration with JAERI. These were quantitatively clarified. Conversely, main factors that impeded the development of the research independency were discontinuance of research caused by a retirement, a change of post or that of occupation, and an unexpected accident (death) of the core researchers. Among three parameters, the authors confirmed that there occurred the time-dependent stage of germination, development and declination of the research independency attributing to the interaction between the succession factors and impeded factors. For this kind of ex-post evaluation, the support of field research laboratory was inevitable. (author)

  20. Proceedings of second JAERI-JNC joint conference on nuclear safety research

    Sugimoto, Jun; Anoda, Yoshinari; Araya, Fumimasa; Yamaguchi, Toshio

    2004-08-01

    The second JAERI-JNC Joint Conference on Nuclear Safety Research was held on February 6, 2004 in Tokyo for those who are relevant to nuclear industries and regulatory organizations, and general public. The nuclear safety research has been conducted in both institutes according to the Five-Year Program for Nuclear Safety Research established periodically by the Nuclear Safety Commission (NSC) and needs from the regulatory organizations. The objectives of the conference are to present its recent results and to collect views and opinions from the participants for its future program through the discussion after each presentation and panel discussion on how to conduct efficiently the nuclear safety in the New Organization. A total of 259 people participated in the conference mainly from the nuclear industries and regulatory organizations and the number was much larger than that in the last conference of 188. The conference consisted of presentations on the safety research results, a special lecture and a panel discussion. First, the overview of safety research results was presented from each institute. Then, the results in the field of nuclear installations, environmental radioactivity and radioactive waste were presented from each institute. Then, Dr. Higashi, the Nuclear Safety Commissioner, made a special lecture on the radiation protection from the high-level radioactive waste disposal. Finally, a panel discussion was conducted with the title of ''how to conduct efficiently the nuclear safety research in the New Organization'' chaired by Prof. Kimura, the chairperson of Standing Committee on Nuclear Safety Research under the NSC. The panelists from the regulatory organizations, nuclear industry, JAERI and JNC discussed the subject together with the participants on the floor. The panelists not from JAERI and JNC expressed their views and opinions on how to conduct efficiently the nuclear safety research in the New Organization that were valuable inputs for developing

  1. Phase IIC experiments of the USDOE/JAERI collaborative program on fusion blanket neutronics

    Youssef, M.Z.

    1992-12-01

    Effort in Phase IIC of the US/JAERI Collaborative Program on Fusion Neutronics was focused on performing integral experiments and post analyses on blankets that include the actual heterogeneities found in several blanket designs. Two geometrical arrangements were considered for the blanket assembly, namely multi-layers of Li 2 O and beryllium in an edge-on, horizontally alternating configuration for a front depth of 30 cm, followed by the Li 2 O breeding zone (Be edge-on, BEO, experiment), and vertical water coolant channels arrangement (WCC experiment). The objectives are to examine the accuracy of predicting tritium production. In the BEO system, it was shown that, with the zonal method to measure tritium production from natural lithium (Tn), the calculated-to-measured values (C/E) are 0.95-1.05 (JAERI) and 0.98-0.9 (U.S.), which is consistent with the results obtained in other Phases of the Program (Phases IIA and IIb)). In the WCC experiment, there is a noticeable change in C/E values for T 6 near the coolant channels where steep gradients in T 6 production are observed. The C/E values obtained with the Li-foil detectors are on the average closer to unity than those obtained by the Li-glass method. As for T 7 , the values obtained by NE213 method are within ±15% in JAERI's calculations, but larger values (∼20-25%) are obtained in the U.S. calculations due to the differences of cross-sections data files. Around heterogeneities, the prediction accuracy for T 7 is better than for T 6 . (J.P.N.)

  2. Heat treatment of long pulse operation for the JAERI ERL-FEL

    Sawamura, Masaru; Nagai, Ryoji; Kikuzawa, Nobuhiro; Hajima, Ryoichi; Minehara, Eisuke

    2005-01-01

    RF power sources are replaced from all-solid-state amplifiers to IOT amplifiers for the superconducting accelerators (SCAs) and a vacuum tube amplifier for the SHB of the JAERI ERL-FEL. A long pulse operation increased the pressure in the cryostat of the SCA. The single-cell SCA can be operated in 9% duty according to the time constant of the pressure decay in the cryostat. SHB can be operated in 4% duty which is limited by the frequency range of the tuners. The result of the ABAQUS calculation shows the more duty operation. (author)

  3. Preliminary calculation with code CONTEMPT-LT for spray cooling tests with JAERI model containment vessel

    Tanaka, Mitsugu

    1978-01-01

    LWR plants have a containment spray system to reduce the escape of radioactive material to the environment in a loss-of-coolant accident (LOCA) by washing out fission products, especially radioiodine, and condensing the steam to lower the pressure. For carrying out the containment spray tests, pressure and temperature behaviour of the JAERI Model Containment Vessel in spray cooling has been calculated with computer program CONTEMPT-LT. The following could be studied quantitatively: (1) pressure and temperature raise rates for steam addition rate and (2) pressure fall rate for spray flow rate and spray heat transfer efficiency. (auth.)

  4. Research activities at JAERI on core material behaviour under severe accident conditions

    Uetsuka, H.; Katanashi, S.; Ishijima, K.

    1996-01-01

    At the Japan Atomic Energy Research Institute (JAERI), experimental studies on physical phenomena under the condition of a severe accident have been conducted. This paper presents the progress of the experimental studies on fuel and core materials behaviour such as the thermal shock fracture of fuel cladding due to quenching, the chemical interaction of core materials at high temperatures and the examination of TMI-2 debris. The mechanical behaviour of fuel rod with heavily embrittled cladding tube due to the thermal shock during delayed reflooding have been investigated at the Nuclear Safety Research Reactor (NSSR) of JAERI. A test fuel rod was heated in steam atmosphere by both electric and nuclear heating using the NSSR, then the rod was quenched by reflooding at the test section. Melting of core component materials having relatively low melting points and their eutectic reaction with other materials significantly influence on the degradation and melt down of fuel bundles during severe accidents. Therefore basic information on the reaction of core materials is necessary to understand and analyze the progress of core melting and relocation. Chemical interactions have been widely investigated at high temperatures for various binary systems of core component materials including absorber materials such as Zircaloy/Inconel, Zircaloy/stainless steel, Zircaloy/(Ag-In-Cd), stainless steel B 4 C and Zircaloy/B 4 C. It was found that the reaction generally obeyed a parabolic rate law and the reaction rate was determined for each reaction system. Many debris samples obtained from the degraded core of TMI-2 were transported to JAERI for numerous examinations and analyses. The microstructural examination revealed that the most part of debris was ceramic and it was not homogeneous in a microscopic sense. The thermal diffusivity data was also obtained for the temperature range up to about 1800K. The data from the large scale integral experiments were also obtained through the

  5. Sludge pasteurization and upgrading by radiation. Bilateral research cooperation between OAEP and JAERI

    1995-07-01

    The research cooperation between office of Atomic Energy for Peace, Thailand (OAEP) and Japan Atomic Energy Research Institute (JAERI) on 'Sludge Pasteurization and Upgrading by Radiation' was carried out for 4 years starting from March 1990. This cooperation was performed through information exchange meetings (Steering Committee Meeting), held in Takasaki and Bangkok, and experiments and discussions by scientist exchange, Many useful results were obtained on radiation inactivation effect of pathogen and parasites, upgrading of irradiated sludges to fertilizer, animal feeds and biological pesticides. This report includes the main results of the research cooperation reported at the First to Fifth Steering Committee Meetings as the progress reports. (author)

  6. Some considerations on a plasma in the JAERI experimental fusion reactor

    Tone, T.; Yamato, H.; Maki, K.

    1976-01-01

    The preliminary analysis of the plasma characteristics for the JAERI tokamak experimental fusion reactor is reported. In order to make the reactor compact, the self-sustaining condition has been removed. Stationary heating by 200 keV neutral deuteron beam to maintain the power balance is applied expecting the power amplification by the TCT effect. The main parameters determined are power output of 100 MW, toroidal field on axis of 6 T, aspect ratio of 4.5 and major radius of 6.75 m. The results of the plasma power balance, fueling by means of the gas blanket scheme, power stabilization with feedback and the start-up are presented

  7. Present status and future perspective of research and test reactors in JAERI

    Baba, Osamu; Kaieda, Keisuke

    1999-01-01

    Since 1957, Japan Atomic Energy Research Institute (JAERI) has constructed several research and test reactors to fulfil a major role in the study of nuclear energy and fundamental research. At present, four reactors, the Japan Research Reactor No. 3 and No. 4 (JRR-3M and JRR-4 respectively), the Japan Materials Testing Reactor (JMTR) and the Nuclear Safety Research Reactor (NSRR), are in operation, and a new High Temperature Engineering Test Reactor (HTTR) has reached first criticality and is waiting for the power-up test. This paper introduce these reactors and describe their present operational status. The recent tendency of utilization and future perspectives are also reported. (author)

  8. Design of the JAERI Fuel Cleanup System for the Tritium Systems Test Assembly

    Konishi, Satoshi; Hayashi, Takumi; Naruse, Yuji; Okuno, Kenji; Carlson, R.V.; Anderson, J.L.

    1993-03-01

    TSTA is operated under the US-Japan collaboration program for the study of fusion fuel cycle technology. A plasma exhaust processing subsystem, JAERI Fuel Cleanup (JFCU) was fabricated in Japan, and installed at the TSTA as a major subsystem of the TSTA loop under the agreement. This process is based on some Japanese developed components, and designed to meet TSTA requirements by both parties. This document describes all the technical and safety features in accordance with the LANL QA format. The process has a capability to process simulated plasma exhaust at the flow rate of 15 mol/h, that is 1/5 for ITER. (author)

  9. KEK/JAERI Joint Project on high-intensity proton accelerators

    Nagamiya, Shoji

    2003-01-01

    From JFY01, which started on April 1, 2001, a new accelerator project to provide high-intensity proton beams proceeded into a construction phase. This project is conducted under a cooperation of two institutions, KEK and JAERI. The accelerator complex will provide 1 MW proton beams at 3 GeV and 0.75 MW beams at 50 GeV. The project will be completed within 6 years. In this article I will describe (a) the project itself, (b) sciences to be pursued at this new accelerator complex and (c) the present status and future plans of the project

  10. Upgrade of a control system for the JAERI ERL-FEL

    Kikuzawa, Nobuhiro

    2004-01-01

    The accelerator control system used for the JAERI ERL-FEL is a PC-based distributed control system that has been in operation since 1992. Since an interface bus of the PCs is obsolete, interface boards for the PCs are difficult to obtain in recent years. Thus we have been developing the CAMAC controller with μITRON operating system to replace the old PCs connected with CAMAC. We will introduce a Java and CORBA environment in the new control system. The control system upgrade, including hardware upgrading and applications rewriting, is described in this paper. (author)

  11. Present status and future perspective of research and test reactors in JAERI

    Baba, Osamu [Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment; Kaieda, Keisuke

    1999-08-01

    Since 1957, Japan Atomic Energy Research Institute (JAERI) has constructed several research and test reactors to fulfil a major role in the study of nuclear energy and fundamental research. At present, four reactors, the Japan Research Reactor No. 3 and No. 4 (JRR-3M and JRR-4 respectively), the Japan Materials Testing Reactor (JMTR) and the Nuclear Safety Research Reactor (NSRR), are in operation, and a new High Temperature Engineering Test Reactor (HTTR) has reached first criticality and is waiting for the power-up test. This paper introduce these reactors and describe their present operational status. The recent tendency of utilization and future perspectives are also reported. (author)

  12. Development of in-air micro-PIXE analysis and data sharing systems in JAERI Takasaki

    Sakai, Takuro; Kamiya, Tomihiro; Oikawa, Masakazu

    2000-01-01

    An external scanning ion microbeam system has been developed for in-air micro-PIXE analysis at JAERI Takasaki. The analysis system is widely used for various researches in recent years. The system consists of the external scanning ion microbeam system, a multi-parameter data acquisition system, a file transfer protocol (FTP) server and analysis software. The software of the system provides a graphical user interface for interaction between users and an experimental setup. The server is connected to the Internet and allows remote users to access the experimental data. (author)

  13. Off-line tests of superconducting resonators of the JAERI tandem booster

    Shibata, Michihiro; Ishii, Tetsuro; Takeuchi, Suehiro

    1993-01-01

    The JAERI tandem booster linac, which consists of 46 superconducting quarter wave resonators, is under construction. Off-line tests for resonators were performed. Accelerating field levels of 7MV/m were obtained at an rf input of 4W with most resonators. A maximum field level of 12.7MV/m was obtained. The Q-value was degraded when resonators were cooled down slowly around a temperature of 120K. We investigated this phenomenon by changing the cooling rate. (author)

  14. Proceeding of the second steering conference relating to the 'agreement on the Implementation of Research at the Chernobyl Center for International Research' between CHECIR and JAERI

    Nagaoka, Toshi; Togawa, Orihiko; Moriuchi, Shigeru; Rybalko, S.I.; Sukhoruchkin, A.K.; Kazakov, S.V.

    1994-11-01

    On June, 1992, JAERI and CHECIR concluded an agreement on the Implementation of Research at the Chernobyl Center for International Research (CHECIR). Based on the agreement, JAERI started 'Study on Assessment and Analysis of Environmental Radiological Consequences and Verification of an Assessment System.' CHECIR and JAERI make it a rule to hold steering conference twice a year in order to ensure mutual understanding and exchange of opinion because it its indispensable for smooth and effective implementation of this project. The first steering conference in Japan was held in February of 1994, and three research leaders of CHECIR side were invited from Ukraine. At that time, they gave lectures concerning the environmental Headquarter of JAERI. Progress reports on subject-1 and subject-2 were given from JAERI side at the steering conference. The 5 of presented papers are indexed individually. (author)

  15. Manpower development and international cooperation in Nuclear Technology and Education Center, JAERI

    Shiba, Koreyuki; Tojo, Takao; Takada, Kazuo; Nomura, Masayuki

    1996-01-01

    Nuclear Technology and Education Center was founded in 1958 and now has two branches, Tokyo Education Center at Bunkyo-ku, Tokyo and Tokai Education Center at Tokai, Ibaraki-ken. The objective was to educate and train nuclear engineers and scientists for implementing the nation's program of atomic energy research, development and utilization. A variety of training courses have been prepared and carried out to meet the requirements of the nuclear community. In recent years, activities of getting the public acceptance have become important for nuclear energy deployment in Japan. Many short courses have been implemented at JAERI sites and cities for providing the public including high school teachers with basic knowledge on nuclear energy. International training programs of the center were started with the cooperation of the Japan International Cooperation Agency (JICA) in 1985 and of the International Atomic Energy Agency (IAEA) in 1987. International seminars were implemented for improving nuclear safety by inviting participants from the former Soviet Union, central/east European countries and the neighboring countries of Japan under the direction of the Science and Technology Agency (STA) in 1992. STA and JAERI are starting new programs of helping Asian and Pacific countries to develop nuclear manpower. (author)

  16. Technical development of high intensity proton accelerators in Japan Atomic Energy Research Institute (JAERI)

    Mizumoto, Motoharu

    1995-01-01

    Science and Technology Agency decided 'Options making extra gains of actinides and fission products (OMEGA)' and to promote the related researches. Also in JAERI, the research on the group separation method for separating transuranic elements, strontium and cesium from high level radioactive wastes has been carried out since the beginning of 1970s. Also the concept of the fast reactors using minor actinide mixture fuel is being established, and the accelerator annihilation treatment utilizing the nuclear spallation reaction by high energy protons has been examined. In this report, from the viewpoint of the application of accelerators to atomic energy field, the annihilation treatment method by the nuclear spallation reaction utilizing high intensity proton accelerators, the plan of the various engineering utilization of proton beam, and the development of accelerators in JAERI are described. The way of thinking on the annihilation treatment of radioactive waste, the system using fast neutrons, the way of thinking on the development of high intensity proton accelerator technology, the steps of the development, the research and development for constructing the basic technology accelerator, 2 MeV beam acceleration test, the basic technology accelerator utilization facility and so on are reported. (K.I.)

  17. TIT reactor laboratory course using JAERI and PNC large experimental facilities

    Sekimoto, Hiroshi; Obara, Toru; Ohtani, Nobuo.

    1995-01-01

    This report is presented on a reactor laboratory course for graduate students using large facilities in national laboratories in Japan. A reactor laboratory course is offered every summer since 1990 for all graduate students in the Nuclear Engineering Course in Tokyo Institute of Technology (TIT), where the students can choose one of the experiments prepared at Japan Atomic Energy Research Institute (JAERI), Power Reactor and Nuclear Fuel Development Corporation (PNC) and Research Reactor Institute, Kyoto University (KUR). Both JAERI and PNC belong to Science and Technology Agency (STA). This is the first university curriculum of nuclear engineering using the facilities owned by the STA laboratories. This type of collaboration is promoted in the new Long-Term Program for Research, Development and Utilization of Nuclear Energy adopted by Atomic Energy Commission. Most students taking this course reported that they could learn so much about reactor physics and engineering in this course and the experiment done in large laboratory was a very good experience for them. (author)

  18. The Universities and JAERI joint research project. The achievements and prospects

    Ohashi, Hiroshi; Nakamura, Takashi; Yamaguchi, Sadaei

    1999-01-01

    The universities and JAERI joint research project has been carried out since 13 years ago on an equivalent basis with the universities and JAERI and co-ownership of the results. This paper consists of the history and results of research project and evaluation. The significance, characteristics, themes and problems of the project are arranged. The main results and the future of the project are explained. Two large projects such as the backend chemical project and the high-degree application of radiation project have been studied. The backend chemical project consisted of four themes; the nuclear chemical researches for TRU recycle, the solid chemical research of nuclear fuel and waste, new separation method for reprocessing and waste disposal and the fundamental chemical researches for disposal waste. The high-degree application of radiation project have eight themes; effects of ion beam on organism, slow positron generation and its application to materials, ion irradiation effects on polymer materials, nuclear spectroscopy and nuclear physics of isotope using online isotope separator, shield and behavior of accelerator radiation, materials analysis by ion beam, effects of nuclear transformation product by nuclear fusion reactor radiation damage and biofunction analysis of plant using positron release nuclide. (S.Y.)

  19. Development of large scale fusion plasma simulation and storage grid on JAERI Origin3800 system

    Idomura, Yasuhiro; Wang, Xin

    2003-01-01

    Under the Numerical EXperiment of Tokamak (NEXT) research project, various fluid, particle, and hybrid codes have been developed. These codes require a computational environment which consists of high performance processors, high speed storage system, and high speed parallelized visualization system. In this paper, the performance of the JAERI Origin3800 system is examined from a point of view of these requests. In the performance tests, it is shown that the representative particle and fluid codes operate with 15 - 40% of processing efficiency up to 512 processors. A storage area network (SAN) provides high speed parallel data transfer. A parallel visualization system enables order to magnitude faster visualization of a large scale simulation data compared with the previous graphic workstations. Accordingly, an extremely advanced simulation environment is realized on the JAERI Origin3800 system. Recently, development of a storage grid is underway in order to improve a computational environment of remote users. The storage grid is constructed by a combination of SAN and a wavelength division multiplexer (WDM). The preliminary tests show that compared with the existing data transfer methods, it enables dramatically high speed data transfer ∼100 Gbps over a wide area network. (author)

  20. General activities of JAERI nuclear data center and Japanese nuclear data committee

    Fukahori, Tokio

    1999-01-01

    The nuclear data center of Japan Atomic Energy Research Institute (JAERI/NDC) is playing the role of Japanese domestic nuclear data center and gateway to foreign data centers. As the domestic nuclear data center, activities of JAERI/NDC are 1) compiling the Japanese Evaluated Nuclear Data Library (JENDL) for both general and special purposes, 2) importing and exporting nuclear data, 3) nuclear data services for the domestic users, and 4) organizing japanese Nuclear Data Committee (JNDC) as a secretariat. Compiled JENDL General Purpose Files up to now are JENDL-1, 2, 3, 3.1 and 3.2. The data for 340 nuclei in the energy range from 10 -5 eV to 20 MeV are available in JENDL-3.2. JENDL Special Purpose Files were also prepared in order to meet the requests from the specified application fields. JNDC has about 140 members. JNDC consists of Main Committee, Steering Committee, Subcommittee on Nuclear Data, Subcommittee on Reactor Constants, Subcommittee on Nuclear Fuel Cycle and Standing Groups. Above subcommittees are performing essential evaluation for the files described above, checking the JENDL files through the benchmark and integral testing as well as considering the standard group constant, and considering about evaluation of decay heat and nuclide generation/depletion and fission product yields. (author)

  1. Development of integrated models for energy-economy systems analysis at JAERI

    Yasukawa, Shigeru; Mankin, Shuichi; Sato, Osamu; Yonese, Hiromi

    1984-08-01

    This report, being a revision of the preprint for distribution to participants at IEA/ETSAP Workshop held, at JAERI, Tokyo, March 1984, describes the concept of the integrated models for energy-economy systems analysis now being carried out at JAERI. In this model system, there contains four different categories of computer codes. The first one is a series of computer codes named as E 3 -SD representatively, which are utilized to develop a dynamic scenario generation in a long-term energy economy evolution. The second one, of which the main constituents are the MARKAL, i.e. an optimal energy flow analizer, and the TRANS-I/O, i.e. a multi-sectoral economy analyzer, has been developed for the analysis of structural characteristics embodied in our energy-economy system. The third one is for a strategy analysis on nuclear power reactor installation and fuel cycle development, and its main constituent is the JALTES. The fourth one is for a cost-benefit-risk analysis including various kinds of data bases. As the model system being still under development, but the idea of application of it to such a problem as '' the role of the HTGR in the prospects of future energy supply'' is also explained in the report. (author)

  2. Development of an integrated system for nuclear material accountancy and control at JAERI

    Nishimura, Hideo; Nishizawa, Satoshi

    1993-01-01

    This paper describes the design concept and the current status of an integrated system for nuclear material accountancy and control, which is under development at JAERI. We, at JAERI, have decided to update the current system for material accountancy and control and to develop the integrated new system with a consolidated data base in order to augment transparency, credibility and promptness of the system, to materialize a prudent control of obligations required by bilateral nuclear cooperation agreements, and to give information for the physical protection, safely handling, property control and cost-effective use of nuclear material and for public relations. The system is composed of two work-stations operated by UNIX, one for implementation and the other for development, and many terminals located at the headquarters, administrative offices, and research facilities and laboratories. It is connected with a mainframe computer. There are many files on the data base to record inventory changes, book and physical inventories, and statistics on material balances. These files are controlled by a commercial data base management system which enables us to make access to data on the files with a simple query language, spread sheet type software or an application program. (author)

  3. JAERI TANDEM, LINAC and V.D.G. annual report 1991 April 1, 1991 - March 31, 1992

    1992-09-01

    This annual report describes research activities which have been performed with the JAERI tandem accelerator, the electron linear accelerator and the Van de Graaff accelerator from April 1, 1991 to March 31, 1992. Summary reports of 44 papers, and list of publications, personnel and cooperative researches with universities are contained. (author)

  4. Collaborative analysis for certification of zirconium and zirconium base alloy reference materials JAERI-Z11 to Z16

    1985-03-01

    The second Sub-Committee on Zircaloy Analysis was organized in April 1978, under the Committee on Analytical Chemistry on Nuclear Fuels and Reactor Materials, JAERI, for the renewal of zirconium and zirconium base alloy certified reference materials (CRMs). The Sub-Committee carried out collaborative analysis among 13 participating laboratories for the certification of the CRMs, JAERI-Z11 to Z18, after development, improvement and evaluation of analytical methods during the period of May 1978 to June 1982. As the result of the collaborative analysis, the certified value was given for 18 elements (Sn, Fe, Ni, Cr, B, Cd, U, Cu, Co, Mn, Pb, Al, Ti, Si, Mo, W, Hf, C) in the CRMs. The first part of this report includes general discussion, the second part principles of certification, the third part development and verification of analytical methods, and the fourth part evaluation of analytical results on 17 elements. Preparation of Z11 to Z18, and certification for carbon in JAERI-Z17 and Z18 were reported separately in JAERI-M 83-241 and M 83-035, respectively. (author)

  5. JAERI TANDEM, LINAC and V.D.G. annual report 1990. April 1, 1990 - March 31, 1991

    1991-10-01

    This annual report describes research activities which have been performed with the JAERI tandem accelerator, the electron linear accelerator and the Van de Graaff accelerator from April 1, 1990 to March 31, 1990. Summary reports of 38 papers, and list of publications, personnel and cooperative researches with universities are contained. (author)

  6. Proceedings of third JAERI-JNC joint conference on nuclear safety research

    Anoda, Yoshinari; Oikawa, Tetsukuni; Araya, Fumimasa; Suzuki, Tsugio

    2006-03-01

    The present report is the proceedings of the third JAERI-JNC joint conference on nuclear safety research held on July 29, 2005 in Tokyo before integration of JAERI and JNC to JAEA. The conference was held for those who are relevant to nuclear industries and regulatory organizations, and general public. The nuclear safety research has been conducted in both institutes according to the Five-Year Program for Nuclear Safety Research established periodically by the Nuclear Safety Commission (NSC) and needs from the regulatory organizations. The objectives of the conference are to present its recent results and to collect views and opinions from the participants for its future program through the discussion after each presentation and panel discussion on how to conduct efficiently the nuclear safety research in the new organization. A total of 234 people participated in the conference mainly from the nuclear industries and regulatory organizations. The conference consisted of presentations on the safety research results, a special lecture and a panel discussion. First, the overview of safety research results was presented from each institute. Then, the results in the field of nuclear installations, environmental radioactivity and radioactive waste were presented from each institute. Then, Dr. Suzuki, deputy chairperson of NSC, made a special lecture on recent trends in nuclear safety regulation and expectation for the new organization. Finally, a panel discussion was conducted with the title of 'how to conduct efficiently the nuclear safety research in the new organization' chaired by Prof. Kimura, the chairperson of Standing Committee on Nuclear Safety Research under the NSC. The panelists from JAERI and JNC presented and discussed the subject together with the participants on the floor. Through vigorous exchange of views in the panel discussion and descriptions on the questionnaires, it was obviously expressed that expectation to the safety research of the new

  7. Report of the third seminar on nuclear physics at the energy region of the JAERI tandem-booster accelerator February 27-28, 1992, Tokai, Japan

    Iwamoto, Akira; Oshima, Masumi; Ikezoe, Hiroshi; Nagame, Yuichiro; Shinohara, Nobuo

    1992-09-01

    A seminar on new experiments to be studied and new experimental apparatus suitable for the JAERI tandem-booster accelerator being under construction was held at Tokai Research Establishment of JAERI in the period from February 27 to 28, 1992. Sixty eight participants from universities and from JAERI attended to discuss the following items: 1. Physics at low temperature, 2. Nuclear structure at high spin and at high excitation energy, 3. Application of unstable beam and their spectroscopy, 4. Nuclear reaction at intermediate energy, 5. New facilities. (author)

  8. Status of fusion technology development in JAERI stressing steady-state operation for future reactors

    Matsuda, Shinzaburo

    2000-01-01

    This paper reports on the progress of the fusion reactor technologies developed at the Japan Atomic Energy Research Institute (JAERI) and expected to lead to a future steady state operation reactor. In particular, superconducting coil technology for plasma confinement, NBI and RF systems technology for plasma control and current drive, fueling and pumping systems technology for particle control, heat removal technology, and development of long life materials are highlighted as the important key elements for the future steady state operation. It will be discussed how these key technologies have already been developed by the ITER (International Thermonuclear Experimental Reactor) technology R and D as well as by the Japanese domestic program, and which technologies are planned for the near future

  9. An automated single ion hit at JAERI heavy ion microbeam to observe individual radiation damage

    Kamiya, Tomihiro; Sakai, Takuro; Naitoh, Yutaka; Hamano, Tsuyoshi; Hirao, Toshio

    1999-01-01

    Microbeam scanning and a single ion hit technique have been combined to establish an automated beam positioning and single ion hit system at the JAERI Takasaki heavy ion microbeam system. Single ion irradiation on preset points of a sample in various patterns can be performed automatically in a short period. The reliability of the system was demonstrated using CR-39 nuclear track detectors. Single ion hit patterns were achieved with a positioning accuracy of 2 μm or less. In measurement of single event transient current using this system, the reduction of the pulse height by accumulation of radiation damages was observed by single ion injection to the same local areas. This technique showed a possibility to get some quantitative information about the lateral displacement of an individual radiation effect in silicon PIN photodiodes. This paper will give details of the irradiation system and present results from several experiments

  10. The muon science facility at the JAERI/KEK joint project

    Miyake, Y.; Nishiyama, K.; Makimura, S.; Kawamura, N.; Shimomura, K.; Kadono, R.; Higemoto, W.; Fukuchi, K.; Beveridge, J.L.; Ishida, K.; Matsuzaki, T.; Watanabe, I.; Matsuda, Y.; Sakamoto, S.; Nakamura, S.N.; Nagamine, K.

    2003-01-01

    The Muon Science Facility is one of the experimental arenas of the JAERI/KEK Joint Project, which also includes neutron science, particle and nuclear physics, neutrino physics and nuclear transmutation science. Following the recommendations by the review committees, the Joint Project was finally approved for construction at the end of December, 2000. The approval is for Phase 1 of 1335 Oku Yen out of the total project cost of 1890 Oku Yen. It is planned to locate the muon science experimental area together with the neutron facility in an integrated building, as a facility for materials and life science studies. Because its construction will be started in April 2003, we are now working to complete the detailed design of the building structure, shielding, electrical services, cooling water, primary proton beam line, one muon target and secondary beam lines

  11. Design and R and D activities on ceramic breeder blanket for fusion experimental reactors in JAERI

    Kurasawa, T.; Takatsu, H.; Sato, S.; Nakahira, M.; Furuya, K.; Hashimoto, T.; Kawamura, H.; Kuroda, T.; Tsunematsu, T.; Seki, M.

    1995-01-01

    Design and R and D activities on ceramic breeder blanket of a fusion experimental reactor have been progressed in JAERI. A layered pebble bed type ceramic breeder blanket with water cooling is a prime candidate concept. Design activities have been concentrated on improvement of the design by conducting detailed analyses and also by fabrication procedure consideration based on the current technologies. A wide variety of R and Ds have also been conducted in accordance with the design activities. Development of fabrication technology of the blanket box structure and its mechanical testing, elementary testing on thermal performances of the pebble bed, and engineering-oriented material tests of breeder and beryllium pebbles are the main achievements during the last two years. (orig.)

  12. Proceedings of the 7th symposium on JAERI's Reimei Research Program

    Shibata, Takemasa

    2004-02-01

    The Reimei (Dawn) Research Program is a research project based on public application to be conducted within the framework of the Reimei Research Promotion Project of Japan Atomic Energy Research Institute. The objective of the system is to encourage often vague or unique ideas in the field of fundamental nuclear science and nuclear energy. The symposium on JAERI's Reimei Research Program carried out at the 2002 fiscal year was held at Tokai Research Establishment on 1st and 2nd of July 2003. Each report of 51 papers was carried out by short presentation and poster, and the active discussion was carried out by about 120 attendees. Those presented papers are compiled in the proceedings. We hope that many new researches grow and develop by the help of Reimei Research Promotion Project. The 36 of the presented papers are indexed individually. (J.P.N.)

  13. FURNACE-J, 2-D Diffusion Burnup for Fast Reactors from JAERI Fast-Set

    Ikawa, Koji

    1984-01-01

    1 - Nature of physical problem solved: FURNACEJ is a two-dimensional diffusion-burnup code for use in the detailed burnup analysis of fast reactors. The code is an extension code of the FURNACE. There exists no essential difference between FURNACE and FURNACEJ. However, the latter can deal with JAERI-Fast-Set as its cross section library, while the former is designed to use ABBN set. Additionally, in FURNACEJ, group-dependent and -independent transverse buckling of each region can be computed and punched on cards, if desired. This is prepared for users so as to use them as input data for detailed two-dimensional x-y calculations. 2 - Restrictions on the complexity of the problem: Only r-z geometry is available

  14. Free-electron laser research-and-development and utilization program at Tokai, JAERI

    Kawarasaki, Yuuki

    1992-01-01

    The free-electron laser (FEL) research and development (R and D) and utilization program now underway at the Linac Laboratory, Tokai Research Establishment, JAERI, is presented together with the current status of the R and D. Specific feature of this program is at the points that the R and D period will range over a long time, around a decade, tentatively divided into three developmental phases, aiming at the final utilization in a field of nuclear energy industry and the FEL here under R and D is based on a superconducting (SC) linear accelerator (linac) which will in later phases be incorporated with addition of more SC-cavity modules for beam energy increase and with adoption of rather novel accelerator technique: beam recirculation both for further energy increase and for power economy by beam energy recovery. Application scheme is additionally discussed. (author)

  15. JAERI thermal reactor standard code system for reactor design and analysis SRAC

    Tsuchihashi, Keichiro

    1985-01-01

    SRAC, JAERI thermal reactor standard code system for reactor design and analysis, developed in Japan Atomic Energy Research Institute, is for all types of thermal neutron nuclear design and analysis. The code system has undergone extensive verifications to confirm its functions, and has been used in core modification of the research reactor, detailed design of the multi-purpose high temperature gas reactor and analysis of the experiment with a critical assembly. In nuclear calculation with the code system, multi-group lattice calculation is first made with the libraries. Then, with the resultant homogeneous equivalent group constants, reactor core calculation is made. Described are the following: purpose and development of the code system, functions of the SRAC system, bench mark tests and usage state and future development. (Mori, K.)

  16. JAERI TANDEM annual report 2003. April 1, 2003 - March 31, 2004

    Ishii, Tetsuro; Takeuchi, Suehiro; Oshima, Masumi; Nagame, Yuichiro; Chiba, Satoshi; Sataka, Masao

    2004-12-01

    This annual report describes research activities, which have been performed with the JAERI tandem accelerator and its energy booster from April 1, 2003 to March 31, 2004. Summary reports of 42 papers, and lists of publication, personnel and cooperative research with universities are contained. The following are some of the highlights in FY 2003. The JAERI-KEK joint project of developing an ISOL-based radioactive-nuclear beam facility has been running since FY2001. In FY2003, the accelerators (split-coaxial RFQ, IH linac) in KEK were moved to a remodeled room in the tandem accelerator facility. The ion source in the ISOL was developed for the use of a UC 2 target. The ISOL was connected to an ECR charge breeder operating at 18 GHz. An ECR ion source for stable-nuclear beams was also installed. This facility accelerates heavy-ions with A/q 47 K was carried out by deep-inelastic collisions with a 48 Ca beam. The electromagnetic properties of low-lying states in 66,68Z n, 78 Se isotopes were determined by projectile Coulomb excitation. High-spin states in 169,172,187 Re, 145,146 Tb and 179 Au, and a high-spin isomer of 136 Ba were identified by the γ-ray detector array, GEMINI-II. In one of the heaviest nuclei 257 No, the spin-parity of its ground state was determined by α-decay spectroscopy using the ISOL and a He gas-jet system. In research of nuclear reactions, fusion cross sections of 64 Ni + 154 Sm and 86 Kr + 134,138 Ba reactions were measured by using the recoil mass separator JAERI-RMS in order to investigate the dependence of sub-barrier fusion on the nuclear deformation and shell structure. The exclusive cross section of 8 Li (α, n) reaction was measured with high statistics in the energy region, E cm = 0.9-2.8 MeV, of astrophysical interest by using a highly pure low-energy beam of unstable 8 Li nuclei from the JAERI-RMS. In research of nuclear chemistry, fluoride complexation of element 104, rutherfordium (Rf), produced in the 248 Cm ( 18 O, 5n) 261 Rf

  17. Proceedings of the 8th symposium on JAERI's Reimei research program

    Shibata, Takemasa

    2004-12-01

    The Reimei (Dawn) Research Program is a research project based on public application to be conducted within the framework of the Reimei Research Promotion Project of the Japan Atomic Energy Research Institute. The objective of the system is to encourage often vague and/or unique ideas in the field of fundamental nuclear science and nuclear energy. The symposium on JAERI's Reimei Research Program carried out in the 2003 fiscal year was held at Tokai Research Establishment on 29th and 30th of June 2004. 42 papers were reported through the short presentation followed by the poster presentation, and the active discussions was carried out by about 120 attendees. Those presented papers are compiled in the proceedings. We hope that new researches will be grown and developed by the help of Reimei Research Promotion Project. The 40 of the presented papers are indexed individually. (J.P.N.)

  18. Future perspective of nuclear energy utilization and expected role of HTGR. JAERI's energy systems analysis research

    Sato, Osamu

    1996-01-01

    Studies have been made in JAERI in order to assess the possibility of using nuclear energy symbiotically with fossil and biomass fuels, and to evaluate its implications for the environment. The application system of high temperature nuclear heat has been designed for this purpose with various technology options. The core of the system is a set of technologies for hydrogen production and its application to produce clean and convenient fuels from fossil or biomass sources. The results of analytical studies using the MARKAL model have indicated sufficient possibilities of combining nuclear energy effectively with fossil or biomass fuels via hydrogen produced by high temperature nuclear heat. In addition to providing clean and convenient liquid fuels on a large scale, the combined system will contribute to the substantial reduction of long-term CO 2 emissions. The relatively high cost of this system will be well justified when CO 2 emission penalties are taken into account. (J.P.N.)

  19. Advanced dust monitoring system applied to new TRU handling facility of JAERI

    Yabuta, H.; Shigeta, Y.; Sawahata, K.; Hasegawa, K.

    1993-01-01

    In JAERI, a large, scale multipurpose facility is under construction, which consists of a TRU waste management testing installation, a solution fuel treatment installation and critical assemblies with uranium and/or plutonium solution fuel. The facility is also equipped with a lot of gloveboxes for handling and treatment of solution fuel and hot cells for research on reprocessing process. As there may be a relatively high potential of air contamination, it is important to monitor air contamination effectively and efficiently. An advanced dust monitoring system was introduced for convenience of handling and automatical measurement of filter papers, by developing a filter-holder with an IC memory and a radioactivity measuring device with an automatic filter-holder changing mechanism as a part of a centralized monitoring system with a computer

  20. Electron beam flue gas treatment. Research cooperation among JAERI, IAEA and INCT

    NONE

    1996-10-01

    The research co-operation is conducted among Japan Atomic Energy Research Institute (JAERI), International Atomic Energy Agency (IAEA) and Institute of Nuclear Chemistry and Technology in Poland (INCT) on Electron Beam Flue Gas Treatment from January 1993 to March 1997. The first phase of the cooperation was carried out for 3 years from January 1993 to March 1995. This cooperation was performed through information exchange meetings (Coordination Meetings), held in Takasaki and Warsaw, and experiments and discussions by exchange scientists. Many useful results were obtained on electron beam treatment of flue gas from coal-combustion heat generation plant in Kaweczyn within the frame work of the research co-operation. This report includes the main results of the tripartite research cooperation. (author)

  1. Development of a multi-ampere H- ion source at JAERI

    Inoue, T.; Hanada, M.; Mizuno, M.; Ohara, Y.; Okumura, Y.; Suzuki, Y.; Tanaka, M.; Watanabe, K.

    1992-01-01

    Recent results of R ampersand D on high current negative ion source at JAERI are presented. After succeeding in ten ampere H - ion beam production, the R ampersand D work has been progressed toward longer pulse beam production and the beam optics. A long pulse operation for 24 hours was demonstrated stably with a small cesiated volume source. It was confirmed that the heat load in the source is a modest level allowable for the long pulse operation. The cesium effect lasted for 24 hours, once the cesium was seeded before operation. In beam optics study, we have produced a beam with very small divergent angle of 1.5 mrad. To take this advantage for a design of compact neutral beam system, beamlet focusing technique by aperture displacement was applied in the H - beam extractor

  2. A study of nuclei far from stability by using the JAERI ISOL

    Ichikawa, Shin-ichi

    1988-01-01

    Since a mass separator was installed at the JAERI tandem accelerator facilities, a high-temperature ion source, a tape transport system, a radiation detection system and a data acquisition system have been constructed for online experiments. Although the ion source can ionize effectively alkali, alkaline-earth and rare-earth elements, further we have developed a new technique applying the favoured formation of monoxide ions of La and Ce to strengthen elemental selectivity. Taking advantage of the technique and heavy-ion fusion-nucleon evaporation reactions, we are studying nuclei in the light rare-earth region. So far, decays of odd-odd nuclei such as 122,124 , 126 La and 128,130 Pr have been studied, and the isotope 121 La has been newly identified with a half-life of 5.2 ± 0.2 s. (author)

  3. Thermal-hydraulic analysis code development and application to passive safety reactor at JAERI

    Araya, F.

    1995-01-01

    After a brief overview of safety assessment process, the author describes the LOCA analysis code system developed in JAERI. It comprises audit calculation code (WREM, WREM-J2, Japanese own code and BE codes (2D/3D, ICAP, ROSA). The codes are applied to development of Japanese passive safety reactor concept JPSR. Special attention is paid to the passive heat removal system and phenomena considered to occur under loss of heat sink event. Examples of LOCA analysis based on operation of JPSR for the cases of heat removal by upper RHR and heat removal from core to atmosphere are given. Experiments for multi-dimensional flow field in RPV and steam condensation in water pool are used for understanding the phenomena in passive safety reactors. The report is in a poster form only. 1 tab., 13 figs

  4. Joint operation of the TSTA under the collaboration between JAERI and U.S.-DOE

    Hayashi, Takumi; Konishi, Satoshi; Nakamura, Hirofumi

    1993-03-01

    A first complete integrated test of the J-FCU (JAERI Fuel Cleanup System) and the ISS (Isotope Separation System) with full four cryogenic distillation columns was performed successfully with 100 grams of tritium. This test was performed as a part of a 25 day TSTA extended loop run on April - May 1992. Through this operation, the J-FCU operated stably and safely. No significant problems was caused on the interaction between the J-FCU and the ISS. J-FCU processed more than 5 N1/min of simulated fusion-fuel exhaust with wide range of impurities and transferred pure hydrogen isotopes to the ISS and exhausted tritium free impurities to the TWT (Tritium Waste Treatment System) continuously. This report describes the detail result of the J-FCU part test under a 25 day TSTA extended loop run and discuss the JFCU performance. (author)

  5. Lattice design of 3 GeV synchrotron for JAERI-KEK joint project

    Noda, F. [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2001-03-01

    This paper summarizes the Lattice of 3 GeV proton synchrotron for JAERI-KEK joint project. This 3 GeV ring provides 3 GeV proton beam for neutron science, muon science, exotic nuclear science facility and 50 GeV ring. The output beam power of this ring is 1 MW with 25 Hz operation. This beam power is a few times higher than that of the existing accelerators. To achieve this goal, it is important to cure an uncontrolled beam loss. A power of uncontrolled beam loss must be smaller than 1 W/m for hands-on maintenance. This uncontrolled beam loss is caused by beam injection, space-charge force, extraction and some known or unknown instability. The precise painting system, adequate aperture of ring and extraction line, and secure collimation systems are essential issues of this 3 GeV ring. (author)

  6. Proceedings of the 9th symposium on JAERI's Reimei Research Program

    Yamashita, Toshiyuki

    2005-09-01

    The Reimei (Dawn) Research Program is a research project based on public application to be conducted within the framework of the Reimei Research Promotion project of the Japan Atomic Energy Research Institute. The objective of the program is to encourage original and/or unique ideas in the field of fundamental nuclear science and nuclear energy. The Symposium on JAERI's Reimei Research Program carried out in the 2004 fiscal year was held at Tokai Research Establishment on 28th and 29th of June 2005. 38 papers were reported through the short presentation followed by the poster presentation, and animated discussions were carried out by about 120 attendees. These presented papers were compiled in the proceedings. We hope that new researches will be grown and developed by the help of Reimei Research Promotion project. The 37 of the presented papers are indexed individually. (J.P.N.)

  7. The specification and the operation characteristics of the low energy accelerator in JAERI-TRCRE

    Haruyama, Yasuyuki; Yotsumoto, Keiichi; Okamoto, Jiro

    1993-06-01

    The low energy accelerator system of JAERI TRCRE is of a non scanned type electron accelerator, manufactured by NISSIN HIGH VOLTAGE Co., LTD. The system consists of an oil filled d.c.high voltage generator, semicylindrical acceleration chamber in which a linear cathode is supported coaxially, and the products handling conveyor. The high voltage generator and the acceleration chamber are connected by a flexible cable. A batch irradiation can be carried out using the conveyor in inert gases. The output of the accelerator is 300 kV, 100 mA and the beam width is 60 cm. The specification, the operation procedure, and the operation characteristics of the system are described. (author)

  8. Stability of nuclei in peripheral collisions in the JAERI quantum molecular dynamics model

    Mancusi, Davide; Niita, Koji; Maruyama, Tomoyuki; Sihver, Lembit

    2009-01-01

    The JAERI quantum molecular dynamics (JQMD) model has been successfully used for a long time now to describe many different aspects of nuclear reactions in a unified way. In some cases, however, the JQMD model cannot produce consistent results: First, it lacks a fully relativistically covariant approach to the problem of molecular dynamics; second, the quantum-mechanical ground state of nuclei cannot be faithfully reproduced in a semiclassical framework. Therefore, we introduce R-JQMD, an improved version of JQMD that also features a new ground-state initialization algorithm for nuclei. We compare the structure of the two codes and discuss whether R-JQMD can be adjusted to improve JQMD's agreement with measured heavy-ion fragmentation cross sections

  9. Present status of the negative ion sources and injectors at JAERI tandem accelerator facility

    Minehara, E.; Yoshida, T.; Abe, S.

    1988-01-01

    The JAERI tandem accelerator began regular operation with the 350 kV negative ion jnjector and 3 kinds of nagative ion sources (Direct Extraction Duoplasmatron Ion Source, Heinickie Penning Ion Source, Negative Ion Sputter Source (Refocus-UNIS)) since 1982. An extension with the injector was constructed in 1984, (1) to increase reliability of all devices in the injector, (2) to exclude completely any unsafe operation in the injector, and (3) to tune several ion sources simultaneously, while a certain ion source is in operation. After the extended injector became available, we have been able to run the whole injector system very safely, steadily and effectively, and have had few troubles. Currently, the second injector has been constructed in order to obtain a full strength of resistance against any sudden troubles in the injector. Several other operational and developmental items will be discussed in the text briefly. (author)

  10. Search for unknown isotopes using the TIARA-ISOL and the JAERI-ISOL

    Asai, Masato [Nagoya Univ. (Japan). School of Engineering

    1997-07-01

    The new neutron-deficient isotopes {sup 127}Pr and {sup 125}Pr, and the new neutron-rich isotopes {sup 166}Tb, {sup 165}Gd and {sup 161}Sm were identified using the TIARA-ISOL with {sup 36}Ar + {sup 92,94}Mo reactions, and the gas-jet coupled JAERI-ISOL with a proton-induced fission of {sup 238}U, respectively. The element-selective oxidation technique was used to reduce large contamination from isobars and molecular ions with production cross sections about one or two orders of magnitude as large as those of the new isotopes. The good signal-to-noise ratios achieved in the present measurements were essential to observe and identify weak X/{gamma} rays from the new isotopes. (author)

  11. Design study of superconducting coils for the fusion DEMO plant at JAERI

    Isono, T.; Koizumi, N.; Okuno, K.; Kurihara, R.; Nishio, S.; Tobita, K.

    2006-01-01

    A design study of the TF coil for the fusion DEMO plant at JAERI is in progress. A major issue is to estimate the maximum fields generated by the TF coils for three tokamak options and two conductor options. Three tokamak options are proposed varying the aspect ratio and the role of the CS coil. Two kinds of conductors using advanced superconducting materials are candidates for the TF coils: Nb 3 Al and high temperature superconductor (HTS). In order to evaluate achievable magnetic fields, a simple method was adopted to calculate mechanical properties. The estimated maximum fields are 17-20 T by the HTS conductor and 16-17 T by the Nb 3 Al conductor. There is a possibility of a 0.7 T enhancement using grading of Nb 3 Al winding

  12. Progress of neutral beam R and D for plasma heating and current drive at JAERI

    Ohara, Y.

    1995-01-01

    Recent progress and future plans regarding development of a high power negative ion source at the Japan Atomic Energy Research Institute (JAERI) are described. The neutral beam injection system, which is expected to play an important role not only in plasma heating but also in the plasma current drive in the fusion reactor, requires a high power negative ion source which can produce negative deuterium ion beams with current of order 20A at energy above 1MeV. In order to realize such a high power negative ion beam, intensive research and development has been carried out at JAERI since 1984. The negative hydrogen ion beam current of 10A achieved in recent years almost equals the value required for the fusion reactor. With regard to the negative ion acceleration, a high current negative ion beam of 0.2A has been accelerated up to 350keV electrostatically. On the basis of this recent progress, two development plans have been initiated as an intermediate step towards the fusion reactor. One is to develop a 500keV, 10MW negative ion based neutral beam injection system for JT-60U to demonstrate the neutral beam current drive in a high density plasma. The other is to develop a 1MeV, 1A ion source to demonstrate high current negative ion acceleration up to 1MeV. On the basis of this research and development, an efficient and reactor relevant neutral beam injection system will be developed for an experimental fusion reactor such as the International Thermonuclear Experimental Reactor. ((orig.))

  13. Proceedings of JAERI-JNC joint conference on nuclear safety research. March 7, 2003, Tokyo

    Sugimoto, Jun; Anoda, Yoshinari; Araya, Fumimasa; Yamaguchi, Toshio

    2003-08-01

    The JAERI-JNC Joint Conference on Nuclear Safety Research was held on March 7, 2003 in Tokyo with 188 participants, ahead of planned unification of JAERI and JNC in 2005. The objectives of the conference are to present recent results of safety research conducted in both institutes in accordance with the Five-Year Safety Research Plan by the Nuclear Safety Commission (NSC), and to reflect suggestions from the participants for future research program. Prof. Matsubara, Vice Chairperson of NSC, first presented a special lecture entitled 'Expectation on Future Nuclear Safety Research in Japan'. Twelve papers were then presented on the overview of research results and those of individual research activities in the fields of nuclear facilities, radioactive waste and environmental radioactivity. In the final session, a panel discussion was conducted with a title of 'Expectation on Future Nuclear Safety Research' chaired by Prof. Kimura, Chairperson of Special Committee on Nuclear Safety Research under NSC. Through the presentations and discussions, consensus has almost been obtained among participants for several key issues on safety research to be conducted by a unified new organization, such as giving priority to safety research as one of major missions, assurance of independence of safety research with the governmental funds, assurance of transparency of the planning process of safety research, separation and harmonization between safety research and developmental research, importance of maintaining fundamental research and research facilities, promotion of cooperation with relevant organizations considering the needs from industries, and importance of dissemination of research results and personnel training. The present report compiles the summaries of special lecture, papers, questions and comments, panel discussions, and OHPs presented in the conference. (author)

  14. Study on burnup credit evaluation method at JAERI towards securing criticality safety rationale for management of spent fuel

    Nomura, Y.

    1998-01-01

    Lately, due to massive accumulation of spent fuel discharged from light water reactors in Japan, it is gradually demanded to introduce the so-called burnup credit methodology into criticality safety design for nuclear fuel cycle facilities, such as spent fuel storage pools and transport casks. In order to save space in the spent fuel storage pool of the Rokkasho Reprocessing Plant, the burnup credit design has been firstly implemented for its criticality safety evaluation. Here, its design conditions and operational control procedures are briefly shown and research using burned fuel at JAERI is explained to support its licensing safety review, focusing on the relevant content of the Nuclear Criticality Safety Handbook of Japan, which has been prepared so far and planned in the near future. Finally, international co-operation for study on burnup credit issues practiced by JAERI is addressed. (author)

  15. Report to the 238U discrepancy task force on SIOB fits to the ORNL, CBNM, and JAERI transmission data

    Olsen, D.K.

    1984-05-01

    The computer code SIOB has been used to obtain least-squares simultaneous-sample shape fits to the recent 238 U transmission data of ORNL, CBNM, and JAERI over the energy regions 1460 to 1820 eV, 2470 to 2740 eV, and 3820 to 4000 eV. The fits indicate that much of the systematic discrepancy in the published neutron widths from these data arose in the data analysis procedure. Except for the 3820- to 4000-eV JAERI data, the systematic differences in the resulting neutron widths from the present widths are larger than those contained in any existing evaluation. These fits were performed as part of the work for the NEANDC ad hoc 238 U Discrepancy Task Force. 20 references

  16. Search for EC-decayed neutron-deficient actinide isotopes using gas-jet coupled JAERI-ISOL

    Tsukada, Kazuaki [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1997-07-01

    To study the nuclear properties of unknown neutron deficient actinide isotopes which decay mainly via orbital electron capture (EC), we have developed a composite system consisting of a gas-jet transport apparatus and a thermal ion-source at the JAERI-ISOL. With this system, search for {sup 236}Am produced in the {sup 235}U({sup 6}Li, 5n) reaction has been performed. Pu KX-rays associated with the EC decay of {sup 236}Am are observed at the mass-236 fraction. The half-life of {sup 236}Am is evaluated to be 4.4min. The outline of the gas-jet coupled JAERI-ISOL system and typical performance are given. (author)

  17. JNC-JAERI united research report. A study on degradation of structural materials under irradiation environment in nuclear reactors

    Hoshiya, Taiji; Takaya, Shigeru; Nagae, Yuji; Aoto, Kazumi; Abe, Yasuhiro; Nakamura, Yasuo; Ueno, Fumiyoshi; Nemoto, Yoshiyuki; Miwa, Yukio; Tsukada, Takashi; Ohmi, Masao; Saito, Junichi; Shimizu, Michio

    2004-10-01

    Japan Nuclear Cycle Development Institute (JNC) and Japan Atomic Energy Research Institute (JAERI) have started a JNC-JAERI united research program cooperatively in fiscal year 2003, which has been aimed for efficient progress and synergistic effect on the research activities of both Institutes in order to lead the facing task of unification between JNC and JAERI. This study has been chosen one of the united research themes because it has been common objective for both Institutes in the research field of structural materials such as Fast Breeder Reactor and Light Water Reactors components. The purpose of the study is to clarify damage mechanism of structural materials under irradiation, and then to develop the methods for damage evaluation and detection in earlier stage of progressing process of damage along grain boundaries. In fiscal year 2003, magnetic flux density distribution (JNC) and micro-corrosion (JAERI) measurement apparatus were newly developed and equipped in Hot Facilities in two Institutes, respectively. The former apparatus, supersensitive Flux Gate sensor was installed, could detector leaked magnetic flux from material damaged by neutron irradiation. The latter one, Atomic Force Microscope was installed, could detect grain boundary corrosion loss after an electrochemical corrosion test of irradiated material. These apparatus were designed and produced in consideration of radiation resistance and remote-controlled operation to equip in hot cells. As the results of preliminary studies using Ni ion irradiated specimen, damage detection by corrosion property in grain boundary was possible but magnetic property change could not detect. We will start the study on neutron irradiation damage by employing the two apparatus as the next step. (author)

  18. Proceedings of the 2nd JAERI symposium on HTGR technologies October 21 ∼ 23, 1992, Oarai, Japan

    1993-01-01

    The Japan Atomic Energy Research Institute (JAERI) held the 2nd JAERI Symposium on HTGR Technologies on October 21 to 23, 1992, at Oarai Park Hotel at Oarai-machi, Ibaraki-ken, Japan, with support of International Atomic Energy Agency (IAEA), Science and Technology Agency of Japan and the Atomic Energy Society of Japan on the occasion that the construction of the High Temperature Engineering Test Reactor (HTTR), which is the first high temperature gas-cooled reactor (HTGR) in Japan, is now being proceeded smoothly. In this symposium, the worldwide present status of research and development (R and D) of the HTGRs and the future perspectives of the HTGR development were discussed with 47 papers including 3 invited lectures, focusing on the present status of HTGR projects and perspectives of HTGR Development, Safety, Operation Experience, Fuel and Heat Utilization. A panel discussion was also organized on how the HTGRs can contribute to the preservation of global environment. About 280 participants attended the symposium from Japan, Bangladesh, Germany, France, Indonesia, People's Republic of China, Poland, Russia, Switzerland, United Kingdom, United States of America, Venezuela and the IAEA. This paper was edited as the proceedings of the 2nd JAERI Symposium on HTGR Technologies, collecting the 47 papers presented in the oral and poster sessions along with 11 panel exhibitions on the results of research and development associated to the HTTR. (author)

  19. Options for a next generation neutron source for neutron scattering based on the projected linac facility at JAERI

    Mezei, F.; Watanabe, Noboru; Niimura, Nobuo; Morii, Yukio; Aizawa, Kazuya; Suzuki, Jun-ichi.

    1997-03-01

    Japan Atomic Energy Research Institute (JAERI) has a project to construct a high intensity proton accelerator to promote wide basic science using neutrons and nuclear power technologies such as radioactive nuclide transmutation. One of the most important field for utilization of neutron beam is neutron scattering. The energy and the averaged current obtained by the proton accelerator are 1.5 GeV and 4-5.3 mA, respectively and these provide 6-8 MW power. The repetition frequency is 50-60 Hz. Evaluation of options for the use of accelerators for neutron production for neutron scattering research and investigation of the neutron research opportunities offered by sharing the superconducting linac planned at JAERI were discussed. There are two ways of the utilization of proton beams for neutron scattering experiment. One is for long pulse spallation source (LPSS) and the other is for short pulse spallation source (SPSS). Quantitative evaluation of instrument performance with LPSS and SPSS was examined in the intensive discussion, calculations, workshop on this topics with Prof. F. Mezei who stayed at JAERI from October 24 to November 6, 1996. A report of the collaborative workshop will be also published separately. (author)

  20. Levels of tritium concentration in the environmental samples around JAERI TOKAI

    Matsuura, K.; Sasa, Y.; Nakamura, C.; Katagiri, H.

    1995-01-01

    By the operation of research reactors, tritium-handling facilities, nuclear power plants, and a reprocessing facility around JAERI TOKAI, tritium is released into the environment in compliance with the regulatory standards. To investigate the levels of tritium concentration in environmental samples around JAERI, rain, air (vapor and hydrogen gas), and tissue-free water of pine needles were measured and analyzed from 1984 to 1993. Sampling locations were determined by taking into consideration wind direction, distance from nuclear facilities, and population distribution. The NAKA site (about 6 km west-northwest from the Tokai site) was also selected as a reference point. Rain and tissue-free water of pine needles were sampled monthly. For air samples, sampling was carried out for two weeks by using the continuous tritium sampler. After the pretreatment of samples, tritium concentrations were measured by a low background liquid scintillation counter (detection limit 0.8 Bq/l). Annual mean tritium concentrations in rain observed at six points for 10 years was 0.8 to 8.9 Bq/l, which decreased with distance from the nuclear facilities. Tritium concentrations in rain obtained at Chiba City were around 0.8 Bq/l (1987-1988) and those at the NAKA site were 0.8 to 3.8 Bq/l. Annual mean HTO concentrations in air at three points for 10 years were 9.2 x 10 -2 to 1.1 Bq/m 3 , although HT concentrations in air, ranging from 1.7 x 10 -2 to 5.8 x 10 -2 Bq/m 3 , were not influenced by the operation of the nuclear facilities. Annual mean tritium concentrations in tissue-free water of pine needles at four points for 10 years were 1.4 to 31 Bq/l. Those at the NAKA site ranging from 1.4 to 6.2 Bq/l were in good agreement with the reported value by Takashima of 0.78 to 3.0 Bq/l at twenty-one locations in Japan. Monthly mean HTO concentrations in air for 10 years showed a good correlation with absolute humidity, while other samples showed no seasonal variation. Higher level tritium

  1. A conceptual design of the RF system for the NSP high intensity proton accelerator at JAERI

    Chishiro, Etsuji; Kusano, Joichi; Mizumoto, Motoharu; Touchi, Yutaka; Kaneko, Hiroshi; Takado, Hiroshi; Sawada, Junichi

    1999-03-01

    JAERI has been proposing the Neutron Science Project which aims at exploring the fields of basic science and nuclear technology using a high power spallation neutron source. The neutron source will be driven by a high intensity linear accelerator with an energy of 1.5 GeV and an average beam current of 5.33 mA and beam power of 8 MW. The RF system for the accelerator consists of a high-energy accelerator part and a low energy accelerator part. The maximum RF power requirements at the high and low energy accelerator parts are 25 MW and 8.3 MW, respectively. In this report, we describe the conceptual design of the RF system. In the low energy accelerator part, we estimated the requirement for the high-power amplifier tube and made the basis design for RF components. In the high energy accelerator part, we studied the effect of tuning errors, Lorentz forces and microphonics in the superconducting cavity. We calculated the klystron efficiency and supply power in the arrangement of where one klystron distributes the RF power to four cavities. We also considered an IOT RF system. Finally, we describe the electrical capacity and quantity of cooling water in the RF system. (author)

  2. Development of control and data processing system for JAERI ERL-FEL

    Kikuzawa, Nobuhiro

    2005-03-01

    A personal computer (PC) based distributed control system has been developed for Free Electron Laser (FEL) at Japan Atomic Energy Research Institute (JAERI) and operated since 1992. The control system was implemented on Ethernet LAN of PCs, Nippon Electric Company (NEC Corp.) PC-9800 series 32 bit personal computers. It became troublesome to maintain the control system, because many application programs did not work on outdated hardware interfaces and operating system. Furthermore, since security updates of the operating system (OS) were no longer provided, the problem was in network security when many PCs were connected with the LAN. We have to solve these problems and to improve the reliability and the safety of the control system, an ITRON-based controller was developed. In Japan, the ITRON is very popular and embedded in many products such as industrial instruments or household appliances that are demanded of its high reliability. When the local controller was installed, a new control program was developed by Java language which had high compatibility on many platforms so that replacement of the computer for consoles might become easy in future. High reliability and interchangeability have been successfully realized by them, and the control system made long continuous operation possible. (author)

  3. Establishment of a clean chemistry laboratory at JAERI. Clean laboratory for environmental analysis and research (CLEAR)

    Hanzawa, Yukiko; Magara, Masaaki; Watanabe, Kazuo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; and others

    2003-02-01

    The JAERI has established a facility with a cleanroom: the Clean Laboratory for Environmental Analysis and Research (CLEAR). This report is an overview of the design, construction and performance evaluation of the CLEAR in the initial stage of the laboratory operation in June 2001. The CLEAR is a facility to be used for analyses of ultra trace amounts of nuclear materials in environmental samples for the safeguards, for the CTBT verification and for researches on environmental sciences. One of the special features of the CLEAR is that it meets double requirements of a cleanroom and for handling of nuclear materials. As another feature of the CLEAR, much attention was paid to the construction materials of the cleanroom for trace analysis of metal elements using considerable amounts of corrosive acids. The air conditioning and purification system, specially designed experimental equipment to provide clean work surfaces, utilities and safety systems are also demonstrated. The potential contamination from the completed cleanroom atmosphere during the analytical procedure was evaluated. It can be concluded that the CLEAR has provided a suitable condition for reliable analysis of ultra trace amounts of nuclear materials and other heavy elements in environmental samples. (author)

  4. Target-moderator-reflector optimization for JAERI 5 MW pulsed spallation neutron source

    Watanabe, Noboru; Teshigawara, Makoto; Kai, Tetsuya

    1999-01-01

    Optimization studies on the target-moderator-reflector neutronics for the projected intense pulsed-spallation-neutron-source in JAERI are reported. In order to obtain the highest possible performance of the source a new target-moderator-reflector system has been proposed and effects of various parameters, such as material and the shape/dimensions of the target, the profile/distribution of the proton beam, material and dimensions of the reflector, the coupling scheme of the target-moderator, moderator parameters, etc., on slow neutron performance and energy deposition in cryogenic moderators have extensively been studied by neutronic calculations. A cold neutron moderator for high-resolution together with high-intensity experiments has newly been proposed. It was found that, by adopting a flat target with a flat beam profile, the slow neutron intensities from the moderators could be rather insensitive to the target/beam dimensions, providing more flexibility to the engineering design of the target and the moderators. The moderator position relative to the target is another important issue to be optimized. It was confirmed that the proposed target-moderator-reflector layout made it possible to put all the moderators almost at the best position (It has not been possible so far), resulting in a higher performance. The predicted performance obtained with nearly optimized parameters was compared with those of similar projects in the world to justify the present concept. (author)

  5. Thermal fluid flow analysis in downcomer of JAERI passive safety light water reactor (JPSR)

    Kunii, K.; Iwamura, T.; Murao, Y.

    1995-01-01

    The residual heat for the JPSR (JAERI Passive Safety Light Water Reactor) is removed by a natural-circulation of coolant flowing through downcomer. The numerical analysis has been performed taking account of the downcomer being a three-dimensional annulus flow pass with the purposes to confirm the abilities of (1) approximation of three-dimensional thermal fluid flow in downcomer to simple one-dimensional one assumed on the preliminary design of the passive residual heat removal system and (2) achievement of an enough driving-force of the natural circulation to remove the residual heat. The following results were obtained : (1) Flow pattern in downcomer shows remarkable three-dimensionality (multi-dimensionality) at lower inlet flow rate not to be able to approximate to one-dimensional flow field. However, the temperature distribution does not deviate from uniform one so much even if the multi-dimensional flow such as large vortex arises. (2) It can be expected to obtain the required enough driving-force at a steady state in any case of inlet flow rate where multi-dimensional flow pattern appears. (3) The increase ratio of the driving-force with the time-integrated coolant amount can be estimated as two functional curves in case of higher and other lower inlet flow rates not dependent only on the respective inlet flow rate. (Author)

  6. Shielding design study for the JAERI/KEK spallation neutron source

    Maekawa, Fujio; Teshigawara, Makoto; Konno, Chikara; Ikeda, Yujiro; Watanabe, Noboru

    2001-01-01

    Shielding design for the JAERI/KEK spallation neutron source was studied. Bulk shielding characteristics and optimization of a beam shutter were investigated by using Monte Carlo calculation code NMTC/JAM and MCNP with LA-150 neutron cross-section library. The following remarks were derived. (1) Neutron dose outside of the concrete shield at 6.6 m from the center is ∼10 μSv/hr regardless of angles with respect to the proton beam axis. The neutron dose can be reduced more than a factor of 30 by adding natural boron of 5 wt% in the concrete. (2) When a beam shutter position just outside the void vessel and the shutter length of 2 m are assumed, a shutter made of copper (1.7 m) with polyethylene (0.3 m) is the optimum in terms of shielding performance as well as cost merit. A shutter made of tungsten is not so effective. (3) Further studies are needed for optimization of beam shutter position. (author)

  7. Report on the progress of researches using JAERI facilities in common, fiscal 1979

    1980-01-01

    The utilization of the facilities in the Japan Atomic Energy Research Institute in common in 1979 has finished in active state, and the results of the researches have reached the stage of publication. The subjects of the researches spread over wide fields, and in 1979 also, extremely diversified researches were carried out. In this report, these results were collected in one book, and it is desirable to utilize it actively. It is expected that the research activities using the JAERI facilities in common will be promoted more and more widely and powerfully, but there are many problems in the manpower, equipment, space and so on required for maintaining and promoting such activities, and it is necessary to improve and strengthen the environment of researches. The number of the research themes is 125. In the field of general researches, the researches on radio-chemistry, the utilization of radiation and the effects of irradiation were mostly carried out, while in cooperative researches, the researches were mainly concerned with nuclear reactor engineering and nuclear reactor materials. The total number of visitors was 3863. The facilities offered to the common utilization were JRR-2, JRR-3, JRR-4, Co-60 irradiation facility, hot laboratory, linear accelerator, No. 1 and No. 2 electron accelerators. The abstracts of the papers are reported. (Kako, I.)

  8. A conceptual design of the DTL-SDTL for the JAERI high intensity proton accelerator

    Ino, Hiroshi; Kabeya, Zenzaburo [Mitsubishi Heavy Industries Ltd., Tokyo (Japan); Chishiro, Etsuji; Ouchi, Nobuo; Hasegawa, Kazuo; Mizumoto, Motoharu

    1998-08-01

    A high intensity proton linear accelerator with an energy of 1.5 GeV and an average beam power of 8 MW has been proposed for the Neutron Science Project (NSP) at JAERI. This linac starts with radio-frequency quadrupole (RFQ) linac, which is followed by a drift-tube linac (DTL), separated-type DTL (SDTL), and a superconducting structure. In this report, we focus on the DTL and SDTL part of the accelerator. The DTL accelerates the beam from 2 to 51 MeV, and SDTL accelerates the beam from 51 to 10 MeV. Since the main features of the requirement for the DTL-SDTL are high peak current ({approx}30 mA) and a high-duty factor ({approx}CW), the conceptual design should be determined not only based on the result of a beam-dynamics calculation, but by careful study of the cooling problems. The design processes of the DTL-SDTL and the matching sections (RFQ to DTL, CW-Pulse merge section, and SDTL to SCC) and the result of a heat transfer analysis of DTL are described. (author)

  9. Subcriticality of accelerator driven system by AESJ/JAERI working party

    Iwasaki, Tomohiko

    2002-01-01

    Under Atomic Energy Society of Japan (AESJ) and Japan Atomic Energy Research Institute (JAERI), a Working Party on Reactor Physics of Accelerator-Driven System (ADS-WP) has been set since March 1999 to review and investigate special subjects related to reactor physics research of Accelerator-Driven System (ADS). In the ADS-WP, the extensive and aggressive activity is being made by 25 professional members in the field of reactor physics in Japan. The ADS is now studying three subjects related to subcriticality of ADS; (1) calculation accuracy of subcriticality on ADS, (2) critical safety issues of ADS, and (3) theoretical review of subcriticality and its measurement methods. This paper describes two topics related to the subjects (1) and (2); one is an analysis of maximum reactivity potentially inserted to a subcritical core and the other is a benchmark proposal for checking calculation accuracy of subcriticality on ADS. The full specification of the calculation benchmark will be supplied by June 2002. Researchers from overseas, especially from Korea, are welcome to join this benchmark

  10. Development of Cyclotron Beam Technology for Applications in Materials Science and Biotechnology at JAERI-TIARA

    Ohara, Y.; Arakawa, K.; Fukuda, M.; Kamiya, T.; Kurashima, S.; Nakamura, Y.; Okumura, S.; Saidoh, M.; Tajima, S.

    2003-01-01

    Recent progress of cyclotron ion beam development for applications in materials science and biotechnology at the ion-irradiation research facility TIARA of the Japan Atomic Energy Research Institute(JAERI) is overviewed. The AVF cyclotron in TIARA can accelerate protons and heavy ions up to 90 MeV and 27.5 MeV/n, respectively. In order to conform to the requirement of a reliable tuning of microbeam formation, the cyclotron beam current has been stabilized by controlling the temperature of the magnet yoke and pole within +/-0.5 deg. and hence by decreasing the variation of the magnetic field ΔB/B below 10-5. A heavy ion microbeam with energy of hundreds MeV is a significantly useful probe for researches on biofunctional elucidation in biotechnology. Production of the microbeam with spot size as small as 1μm by quadrupole lenses requires the energy spread of the beam ΔE/E < 2 x 10-4. In order to minimize the energy spread of the cyclotron beam, the fifth-harmonic voltage waveform has been successfully superposed on the fundamental one to make energy gain uniform

  11. Design study of a neutral beam injection system for the JAERI Experimental Fusion Reactor (JXFR)

    1977-10-01

    Design study has been made of a 200 kV, 45 MW D 0 neutral beam injection system for the JAERI Experimental Fusion Reactor (JXFR) covering the following: determination of the ion source specifications, design of components such as ion source with extraction electrodes, energy converter, cryopump and cooling system, and estimations of the energy conversion efficiency, overall power efficiency and total power required for operation of the NBI system, and also a hydrogen isotope separation method using cryo-sorption pumps. Optimizations and parameter studies of the neutralizing cell length, gas flow rate, operating pressure of ion sources, total pumping speed and pressure of energy converters are made in the design study based on reactor plasma requirements. Hollow cathode ion sources are proposed because of the extended operation time at low gas pressure (about 4.5 x 10 -3 Torr) and the high gas efficiency (40%). Life of the extraction electrodes is determined by blistering due to deuterium ions. Fast neutron radiation damage is relatively small. In-line direct converters with grounded recovery electrodes and neutralizing cells floated at negative potential -190 kV are used to recover residual deuterium ion energy without interrupting the neutral beam trajectories. Energy conversion efficiency of 80% and overall power efficiency of about 40% are obtained. (auth.)

  12. Implementation of JAERI's reflood model into TRAC-PF1/MOD1 code

    Akimoto, Hajime; Ohnuki, Akira; Murao, Yoshio

    1993-02-01

    Selected physical models of REFLA code, that is a reflood analysis code developed at JAERI, were implemented into the TRAC-PF1/MOD1 code in order to improve the predictive capability of the TRAC-PF1/MOD1 code for the core thermal hydraulic behaviors during the reflood phase in a PWR LOCA. Through comparisons of physical models between both codes, (1) Murao-Iguchi void fraction correlation, (2) the drag coefficient correlation acting to drops, (3) the correlation for wall heat transfer coefficient in the film boiling regime, (4) the quench velocity correlation and (5) heat transfer correlations for the dispersed flow regime were selected from the REFLA code to be implemented into the TRAC-PF1/MOD1 code. A method for the transformation of the void fraction correlation to the equivalent interfacial friction model was developed and the effect of the transformation method on the stability of the solution was discussed. Through assessment calculation using data from CCTF (Cylindrical Core Test Facility) flat power test, it was confirmed that the predictive capability of the TRAC code for the core thermal hydraulic behaviors during the reflood can be improved by the implementation of selected physical models of the REFLA code. Several user guidelines for the modified TRAC code were proposed based on the sensitivity studies on fluid cell number in the hydraulic calculation and on node number and effect of axial heat conduction in the heat conduction calculation of fuel rod. (author)

  13. Research and development plan of fusion technologies in JAERI toward DEMO reactors

    Nishitani, Takeo; Hayashi, Takumi; Abe, Tetsuya; Akiba, Masato; Isono, Takaaki; Inoue, Takashi; Enoeda, Mikio; Okuno, Kiyoshi; Koizumi, Norikiyo; Sakamoto, Keishi; Sato, Satoshi; Jitsukawa, Shiro; Sugimoto, Masayoshi; Suzuki, Satoshi; Seki, Shogo; Takatsu, Hideyuki; Tanzawa, Sadamitsu; Tsuchiya, Kunihiko; Nishi, Masataka; Hayashi, Kimio; Matsui, Hideki; Yamanishi, Toshihiko; Watanabe, Kazuhiro

    2005-03-01

    In accordance with the 'Third Phase Basic Program on Fusion Research and Development' established by the Fusion Council of the Japan Atomic Energy Commission, research and development (R and D) of fusion technologies aim at realization of two elements: development of ITER key components and their improvement for higher performances; and construction of sound technical basis of fusion nuclear technologies essential for fusion energy utilization. JAERI has been assigned in the Third Phase Basic Program as a responsible institute for developing the above two elements, and accordingly has been implementing technology R and Ds categorized in the following three areas: R and D for ITER construction and operation; R and D for ITER utilization (blanket testing in ITER) and toward DEMO; and R and D on basic fusion technologies. The present report reviews the status and the plan of fusion technology R and Ds in the latter two areas, and presents the technical objectives, technical issues, status of R and D and near-term R and D plans for: breeding blankets; structural materials; the IFMIF program; improvements of the key ITER components for higher performances toward DEMO; and basic fusion technologies. (author)

  14. Plan and progress of a cooperative research program on field migration test between CIRP and JAERI

    Li Shushen; Wang Zhiming; Li Zhentang

    1999-01-01

    As the main parts of a cooperative research project on safety assessment method for shallow land disposal of low level radioactive wastes between the China Institute for radiation Protection (CIRP) and the Japan Atomic Energy Research Institute (JAERI), field migration tests investigating the migration of radionuclides 90 Sr, 237 Np and 238 Pu and stable elements Sr, Ce, and Nd in both aerated zone and aquifer are carried out. 3 H and Br are used as tracers to obtain the water flow velocity in the aquifer and the movement of moisture water in the aerated zone for radioactive and non-radioactive tests, respectively. The aerated zone migration tests are carried out with media including soil, bentonite, cement block and mortar in both natural rainfall condition and artificial rainfall condition. The aquifer migration tests are carried out with assemblies (Type I), experimental frame (Type II) and injection tube (Type III), respectively, in and Underground Research Facility (URF). The aerated zone migration tests were started in May, 1997, while the aquifer migration tests started in August 1997. (author)

  15. Rupture disc opening property for using pipe rupture test in JAERI

    Kato, Rokuro

    1983-03-01

    In the Mechanical Strength and Structure Lab of JAERI there are being performed pipe break tests which are a postulated instantaneous guillotine break of the primary coolant piping in nuclear power plants. The test being performed are pipe whip tests and jet discharging tests. The bursting of the rupture disc is initiated by an electrical arc and is concluded by the internal pressure. Because the time characteristics during the opening of the rupture disc affects the dynamic thrust force of the pipe, it is necessary to measure these time characteristics. However, it is difficult to measure the conditions during this continuous opening because at the same time of the opening the high temperature and high pressure water is flashing. Therefore, the rupture disc opening was postulated on the measuring of the effective opening characteristics with electric contraction terminals which were attached to the inner surface of the test pipe downstream of the rupture disc and were extended toward the pipe centerline in a ring whose area is about 60 % of the area of the pipe flow sectional area. The measurement voltage was recorded when the data recorder was started in sequence with the electrical arc release from a trigger signal. As a result, it is evident that under high temperature and high pressure water the effective opening time is delayed by a few milliseconds. (author)

  16. Joint operation of the TSTA under the collaboration between JAERI and U.S.-DOE

    Hayashi, Takumi; Nakamura, Hirofumi; Konishi, Satoshi

    1993-03-01

    An extended loop operation of the TSTA with the J-FCU was performed successfully with 100 grams of tritium on April-May 1992. One of the major purposes of this extended loop operation was to demonstrate stable control and safe operation of the entire TSTA during 25 days. This is one of the major milestones of the Collaborative Program on technology for fusion-fuel processing under the Annex IV between JAERI and US-DOE. From a technical point of view, this extended loop operation produced many highlights. Specially, it was noteworthy that the ISS with full four columns was controlled stably for 22 days. It was also noteworthy that the TSTA-FCU with magnesium bed and the J-FCU were first operated under the complete integrated TSTA loop with full (4) columns ISS and that both FCUs were processed simulated fusion-fuel exhaust with a various range of impurities stably and safely. This report describes the entire test plan and the brief test results. (author)

  17. R and D status of an integral type small reactor MRX in JAERI

    Hoshi, Tsutao; Ochiai, Masaaki; Iida, Hiromasa; Yamaji, Akio; Shimazaki, Junya

    1995-01-01

    JAERI is conducting a design study on an integral type small reactor MRX for the use of nuclear ships. The basic concept of the reactor system is the integral type reactor with in-vessel steam generators and control rod drive systems, however, such new technologies as the water-filled containment, the passive decay heat removal system, the advanced automatic system, etc., are adopted to satisfy the essential requirements for the next generation ship reactors, i.e. compact, light, highly safe and easy operation. Research and development (R and D) works have being progressed on the peculiar components, the advanced automatic operation systems and the safety study of the thermal hydraulic phenomena as well as the feasibility study of the applicability to merchant ships. The experiments and analysis of the safety carried out so far are proving that the passive safety features applied into the MRX are sufficient functions in the safety point of view. The MRX is a typical small type reactor realizing the easy operation by simplifying the reactor systems adopting the passive safety systems, therefore, it has wide variety of use as energy supply systems. This paper summarizes the present status on the design study of the MRX and the research and development activities as well as the results of feasibility study. (author)

  18. Development of the JAERI computational dosimetry system (JCDS) for boron neutron capture therapy. Cooperative research

    Kumada, H; Matsumura, A; Nakagawa, Y; Nose, T; Torii, Y; Uchiyama, J; Yamamoto, K; Yamamoto, T

    2003-01-01

    The Neutron Beam Facility at JRR-4 enables us to carry out boron neutron capture therapy with epithermal neutron beam. In order to make treatment plans for performing the epithermal neutron beam BNCT, it is necessary to estimate radiation doses in a patient's head in advance. The JAERI Computational Dosimetry System (JCDS), which can estimate distributions of radiation doses in a patient's head by simulating in order to support the treatment planning for epithermal neutron beam BNCT, was developed. JCDS is a software that creates a 3-dimentional head model of a patient by using CT and MRI images, and that generates a input data file automatically for calculation of neutron flux and gamma-ray dose distributions in the brain with the Monte Carlo code MCNP, and that displays these dose distributions on the head model for dosimetry by using the MCNP calculation results. JCDS has any advantages as follows; By using CT data and MRI data which are medical images, a detail three-dimensional model of patient's head is...

  19. Measurement of thermal neutron spectra using LINAC in Japan Atomic Energy Research Institute (JAERI)

    Akino, Fujiyoshi

    1982-01-01

    The exact grasp of thermal neutron spectra in a core region is very important for obtaining accurate thermal neutron group constants in the calculation for the nuclear design of a reactor core. For the accurate grasp of thermal neutron spectra, the capability of thermal neutron spectra to describe the moderator cross-sections for thermal neutron scattering is a key factor. Accordingly, 0 deg angular thermal neutron spectra were measured by the time of flight (TOF) method using the JAERI LINAC as a pulsed neutron source, for light water system added with Cd and In, high temperature graphite system added with boron, and light water-natural uranium heterogeneous multiplication system among the reactor moderators of light water or graphite systems. First, the equations to give the time of flight and neutron flux by TOF method were analyzed, and several corrections were investigated, such as those for detector efficiency, background, the transmission coefficient of air and the Al window of a flight tube, mean emission time of neutrons, and the distortion effect of re-entrant hole on thermal neutron spectra. Then, the experimental system, results and calculation were reported for the experiments on the above three moderator systems. Finally, the measurement of fast neutron spectra in natural uranium system and that of the efficiency of a 6 Li glass scintillator detector are described. (Wakatsuki, Y.)

  20. Phase-IIC experiments of the JAERI/USDOE collaborative program on fusion blanket neutronics

    Oyama, Yukio

    1992-12-01

    Neutronics experiments on two types of heterogeneous blankets have been performed as the Phase-IIC experiment of JAERI/USDOE collaborative program on fusion blanket neutronics. The experimental system was used in the same geometry as the previous Phase-IIA series which was a closed geometry using neutron source enclosure of lithium carbonate. The heterogeneous blankets selected here are the beryllium edge-on and the water coolant channel assemblies. In the former the beryllium and lithium-oxide layers are piled up alternately in the front part of test blanket. In the latter, the three simulated water cooling channels are settled in the Li 2 O blanket. These are producing steep gradient of neutron flux around material boundary. The calculation accuracy and measurement method for these features is a key of interest in the experiments. The measurements were performed for tritium production rate and the other nuclear parameters as well as the previous experiments. This report describes the experimental detail and the results enough to use for the benchmark data for testing the data and method of design calculation of fusion reactors. (author)

  1. Report on progress of researches by common utilization of JAERI nuclear facilities, for fiscal, 1991

    1992-08-01

    The results of the joint researches by utilizing the facilities of JAERI in 1991 fiscal year were summarized, and this report was able to be completed. Many researchers in whole Japan took part in many themes, and the very significant results were obtained. Now this joint research has reached the great turnabout period. The reconstructed JRR-3M was offered for joint utilization since April, 1991, and the utilization for neutron diffraction and scattering increased largely. As for the ion irradiation facility in Takasaki Research Establishment, the partial operation will be started in the next year, and the joint utilization is expected to begin. Accompanying the diversification of the utilization of facilities, in order to properly meet the needs of users, the thorough revision of the system seems necessary. The number of research themes in 1991 was 222 cases. JRR-3M accomplished the joint utilization operation of 8 cycles as expected, but JRR-2 caused a trouble during 5th cycle, and the operation thereafter was canceled. In this book, 159 reports are collected. (K.I.)

  2. Radiation processing of silk protein (Bilateral research cooperation OAEP and JAERI. December 1998 - December 2002)

    2003-01-01

    Thailand's production of silk, about 1,200 ton per year, also gives about 10% of silk waste which is expected to be recycled into new material (non-textile application) and to avoid environmental pollution. For this purpose, cooperative program 'radiation processing of silk protein' was conducted between OAEP (Thailand) and JAERI. Among the results already obtained are: radiation degradation of silk protein (fibroin) with gamma rays at 160 kGy, production of fine silk milled powder (<90 microns) by electron beam irradiation at 250-1000 kGy (dry method) using electron accelerator (1 MeV, 1 mA), use of antioxidant effect of silk protein on lipid peroxidation and antibacterial activity of irradiated silk protein powder, and wound dressing hydrogel mixed with silk protein and use of antibacterial activity of cross-linked silk protein/PVA hydrogel. Other topics of interest are gamma irradiation of anionic natural polymer solution for use as latex protein scavenger and gamma radiation degradation of chitosan for use as plant growth promoter and fungicide. (S. Ohno)

  3. Status of development - An integral type small reactor MRX in JAERI

    Hoschi, T.; Ochiai, M.; Shimazaki, J.

    1998-01-01

    JAERI is conducting a design study on an integral type small reactor MRX for the use of nuclear ships. The basic concept of the reactor system is the integral type reactor with in-vessel steam generators and control rod drive systems, however, such new technologies as the water-filled containment, the passive decay heat removal system, the advanced automatic system, etc., are adopted to satisfy the essential requirements for the next generation ship reactors, i.e. compact, light, highly safe and easy operation. Research and development (R and D) works have being progressed on the peculiar components, the advanced automatic operation systems and the safety systems. Feasibility study and the economical evaluation of nuclear merchant ships have also being performed. The experiments and analysis of the safety carried out so far are proving that the passive safety features applied into the MRX are sufficient functions in the safety point of view. The MRX is a typical small type reactor realizing the easy operation by simplifying the reactor systems adopting the passive safety systems, therefore, it has wide variety of use as energy supply systems. This paper summarizes the present status on the design study of the MRX and the research and development activities as well as the some results of feasibility study. (author)

  4. System of the advanced volume reduction facilities for LLW at JAERI

    Higuchi, Hidekazu; Monma, Toshiyuki; Nakashio, Nobuyuki; Kozawa, Kazushige; Touhei, Toshio; Sudou, Tomoyuki; Mitsuda, Motoyuki; Kurosawa, Shigenobu; Henmi, Kou; Ishikawa, Joji; Kato, Mitsugu; Sato, Motoaki

    2005-01-01

    The Japan Atomic Energy Research Institute (JAERI) constructed the Advanced Volume Reduction Facilities (AVRF), in which volume reduction techniques are applied and achieved high volume reduction ratio, homogenization and stabilization by means of melting or super compaction processes for low level solid wastes. It will be able to produce waste packages for final disposal and to reduce the amount of the wastes by operating the AVRF. The AVRF consist of the Waste Size Reduction and Storage Facilities (WSRSF) and the Waste Volume Reduction Facilities (WVRF); the former have cutting installations for large size wastes and the latter have melting units and a super compactor. Cutting installations in the WSRSF have been operating since June 1999. Radioactive wastes treated so far amount to 600 m 3 and the volume reduction ratio is from 1/2 to 1/3. The WVRF have been operating with non-radioactive wastes since February 2003 for the training and the homogeneity investigation in the melting processes. The operation with radioactive wastes will start in FY2005. (author)

  5. Summary of the works on blistering and related erosion phenomena in JAERI

    Kamada, Kohji

    1980-01-01

    The works in JAERI on the blistering and related erosion phenomena on material surfaces have been made theoretically and experimentally. The theoretical studies were concerned with the blistering and flaking mechanisms from the standpoint of pressure driven model. A condition for blistering was introduced as a result of the theoretical work. Assuming ductile crack propagation in an ion-irradiated subsurface layer due to the presence of small spherical bubbles, blistering and flaking are reasonably discriminated on the basis of a single mechanism of gas driven model. Experimentally, the in-situ observations of blistered surfaces were carried out with a scanning electron microscope connected to a 2 MeV Van de Graaff accelerator. Targets were single crystals of Nb, Mo, Cu and Al. The flaking in pyrolytic graphite due to He + , Ne + , Ar + and N + ion bombardments, and the hole-formation in glassy carbon by Ne + ion bombardment were also studied. The theoretical explanation gave satisfactory agreements with the experimental results. The in-situ observation of blistering and subsequent exfoliation during 100 keV He + bombardment on a polycrystalline Mo surface was carried with a 400 keV Cockcroft-Walton type ion accelerator. It was found by scanning electron microscopy that the surface erosion due to blistering was effectively reduced by the multi-groove structure. The phenomena named grain ejection were found by bombardment with pulsed intense beam of 25 keV H + , as well as H 2 + , in the temperature range of 150 to 250 degree C. (Kato, T.)

  6. Development of the JAERI computational dosimetry system (JCDS) for boron neutron capture therapy. Cooperative research

    Kumada, Hiroaki; Yamamoto, Kazuyoshi; Torii, Yoshiya; Uchiyama, Junzo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Matsumura, Akira; Yamamoto, Tetsuya; Nose, Tadao [Tsukuba Univ., Tsukuba, Ibaraki (Japan); Nakagawa, Yoshinobu [National Sanatorium Kagawa-Children' s Hospital, Kagawa (Japan); Kageji, Teruyoshi [Tokushima Univ., Tokushima (Japan)

    2003-03-01

    The Neutron Beam Facility at JRR-4 enables us to carry out boron neutron capture therapy with epithermal neutron beam. In order to make treatment plans for performing the epithermal neutron beam BNCT, it is necessary to estimate radiation doses in a patient's head in advance. The JAERI Computational Dosimetry System (JCDS), which can estimate distributions of radiation doses in a patient's head by simulating in order to support the treatment planning for epithermal neutron beam BNCT, was developed. JCDS is a software that creates a 3-dimentional head model of a patient by using CT and MRI images, and that generates a input data file automatically for calculation of neutron flux and gamma-ray dose distributions in the brain with the Monte Carlo code MCNP, and that displays these dose distributions on the head model for dosimetry by using the MCNP calculation results. JCDS has any advantages as follows; By using CT data and MRI data which are medical images, a detail three-dimensional model of patient's head is able to be made easily. The three-dimensional head image is editable to simulate the state of a head after its surgical processes such as skin flap opening and bone removal in the BNCT with craniotomy that are being performed in Japan. JCDS can provide information for the Patient Setting System which can support to set the patient to an actual irradiation position swiftly and accurately. This report describes basic design of JCDS and functions in several processing, calculation methods, characteristics and performance of JCDS. (author)

  7. Present status of research activities conducted by research group for heavy elements microbiology in JAERI

    Ohnuki, Toshihiko; Ozaki, Takuo; Yoshida, Takahiro

    2004-01-01

    It has been recognized that microbial transformations of radionuclides and toxic metals could be significant in the environment, but there is a paucity of information on the mechanisms of biotransformation of radionuclides by the microorganisms. An understanding at the fundamental level the mechanisms of mobilization, immobilization and bioavailability of radioactive elements in particular the actinides is important from the standpoint of mobility of actinides in the environment, disposal of radioactive wastes in deep geological formation, remediation of contaminated soils and materials, and development of strategies for the long-term stewardship of the contaminated sites. The microbiology research group in Japan Atomic Energy Research Institute (JAERI) is conducting basic scientific research on microbial interactions with actinides. Fundamental research on microbial transformations of actinides include elucidation of the mechanisms of dissolution and precipitation of various chemical forms such as ionic, oxides, organic and inorganic complexes of actinides by aerobic or anaerobic microorganisms under relevant microbial process conditions. State-of-the-art analytical techniques are used to determine the interaction of actinides with microorganisms at the molecular level to understand the structure function relationship. These techniques include time-resolved laser fluorescence spectroscopy (TRLFS) to determine the coordination number, oxidation states and the nearest neighbor by X-ray absorption near-edge structure (XANES) and extended X-ray absorption fine structure (EXAFS) at the Synchrotron Light Source, identification of functional groups by nuclear magnetic resonance (NMR), determination of chemical forms by transmission electron microscopy (TEM), and genomic (DNA) manipulation by molecular techniques. We here report the present status of our research activities on accumulation of lanthanides(III) by microorganisms, application of micro-particle induced X

  8. A concept of JAERI passive safety light water reactor system (JPSR)

    Murao, Y.; Araya, F.; Iwamura, T. [Japan Atomic Energy Research Institute, Tokai-mura (Japan)

    1995-09-01

    The Japan Atomic Energy Research Institute (JAERI) proposed a passive safety reactor system concept, JPSR, which was developed for reducing manpower in operation and maintenance and influence of human errors on reactor safety. In the concept the system was extremely simplified. The inherent matching nature of core generation and heat removal rate within a small volume change of the primary coolant is introduced by eliminating chemical shim and adopting in-vessel control rod drive mechanism units, a low power density core and once-through steam generators. In order to simplify the system, a large pressurizer, canned pumps, passive engineered-safety-features-system (residual heat removal system and coolant injection system) are adopted and the total system can be significantly simplified. The residual heat removal system is completely passively actuated in non-LOCAs and is also used for depressurization of the primary coolant system to actuate accumulators in small break LOCAs and reactor shutdown cooling system in normal operation. All of systems for nuclear steam supply system are built in the containment except for the air coolers as a the final heat sink of the passive residual heat removal system. Accordingly the reliability of the safety system and the normal operation system is improved, since most of residual heat removal system is always working and a heat sink for normal operation system is {open_quotes}safety class{close_quotes}. In the passive coolant injection system, depressurization of the primary cooling system by residual heat removal system initiates injection from accumulators designed for the MS-600 in medium pressure and initiates injection from the gravity driven coolant injection pool at low pressure. Analysis with RETRAN-02/MOD3 code demonstrated the capability of passive load-following, self-power-controllability, cooling and depressurization.

  9. Safety demonstration analyses for severe accident of fresh nuclear fuel transport packages at JAERI

    Yamada, K.; Watanabe, K.; Nomura, Y.; Okuno, H.; Miyoshi, Y.

    2004-01-01

    It is expected in the near future that more and more fresh nuclear fuel will be transported in a variety of transport packages to cope with increasing demand from nuclear fuel cycle facilities. Accordingly, safety demonstration analyses of these methods are planned and conducted at JAERI under contract with the Ministry of Economy, Trade and Industry of Japan. These analyses are conducted part of a four year plan from 2001 to 2004 to verify integrity of packaging against leakage of radioactive material in the case of a severe accident envisioned to occur during transportation, for the purpose of gaining public acceptance of such nuclear fuel activities. In order to create the accident scenarios, actual transportation routes were surveyed, accident or incident records were tracked, international radioactive material transport regulations such as IAEA rules were investigated and, thus, accident conditions leading to mechanical damage and thermal failure were selected for inclusion in the scenario. As a result, the worst-case conditions of run-off-the-road accidents were incorporated, where there is impact against a concrete or asphalt surface. Fire accidents were assumed to occur after collision with a tank truck carrying lots of inflammable material or destruction by fire after collision inside a tunnel. The impact analyses were performed by using three-dimensional elements according to the general purpose impact analysis code LS-DYNA. Leak-tightness of the package was maintained even in the severe impact accident scenario. In addition, the thermal analyses were performed by using two-dimensional elements according to the general purpose finite element method computer code ABAQUS. As a result of these analyses, the integrity of the inside packaging component was found to be sufficient to maintain a leak-tight state, confirming its safety

  10. A review of JAERI R and D activities on the negative-ion-based neutral beam injection system

    Ohara, Yoshihiro; Akiba, Masato; Araki, Masanori

    1990-08-01

    R and D efforts to realize a negative-ion-based neutral beam injection system have been made intensively at JAERI for the past several years. Concerning a high current negative ion source which is one of the most important R and D items, a 10 A, 50 keV negative hydrogen ion beam has been produced successfully. The negative ion beam current and the current density correspond already to the value required for the negative-ion-based NBI system. In order to increase the beam energy further, a 350 keV, 0.1 A test stand has been constructed, and the test of a high energy negative ion accelerator has started. Concerning a high energy acceleration power supply, an inverter type power supply which has a high speed AC switch was proposed and applied to the 100 kV, 5 A power supply for JAERI Electron Beam Irradiation Stand. The reliable operation indicates that the concept of this system can be applied for a MV class acceleration power supply. As one of the promising candidates for a beam dump cooling element, an externally-finned swirl tube was proposed and tested to have a high burnout heat flux of 4.1 kW/cm 2 , which is high enough for the next NBI system. The R and Ds on the negative-ion-based NBI system have made great progress at JAERI in recent years. The construction of a 500 keV class NBI system has become realistic from the engineering point of view. (author)

  11. Report of the International Review Committee of the joint proposal of the Japan Hadron Facility (KEK) and the Neutron Science Project (JAERI)

    1999-08-01

    The International Review Committee composed of twelve Japanese and foreign experts was set up under the Research Evaluation Committee of JAERI, and has reviewed the proposed joint project combining JAERI's Neutron Science Project and KEK's Japan Hadron Facility into one major facility. The review meeting took place on April 26-27, 1999, at JAERI Head quarters, Tokyo. According to the points of review given in advance, the review was implemented based on the joint project report submitted and presentations of both institutions. The Research Evaluation Committee received the review report and its explanations from the Review Committee on July 5. The Research Evaluation Committee has acknowledged appropriateness of the review results. This report describes the review results. (author)

  12. Development of several data bases related to reactor safety research including probabilistic safety assessment and incident analysis at JAERI

    Kobayashi, Kensuke; Oikawa, Tetsukuni; Watanabe, Norio; Izumi, Fumio; Higuchi, Suminori

    1986-01-01

    Presented are several databases developed at JAERI for reactor safety research including probabilistic safety assessment and incident analysis. First described are the recent developments of the databases such as 1) the component failure rate database, 2) the OECD/NEA/IRS information retrieval system, 3) the nuclear power plant database and so on. Then several issues are discussed referring mostly to the operation of the database (data input and transcoding) and to the retrieval and utilization of the information. Finally, emphasis is given to the increasing role which artifitial intelligence techniques such as natural language treatment and expert systems may play in improving the future capabilities of the databases. (author)

  13. Practice of producing cement packages for sea dumping and their quality control in Tokai Research Establishment, JAERI

    Hattori, Yoshiro; Fujisaki, Setsuo; Usami, Jun; Morishita, Satoru; Komatsu, Shigeru

    1980-07-01

    The production of cement packages for the exploratory sea dumping has been carried out at Waste Disposal and Decontamination Section, Tokai Research Establishment, JAERI. And around 1,000 packages were completed until 1979. The production practice were conducted based on NEA guideline and domestic regulation. In order to meet the guideline and regulation, consistent quality control is necessary to the production procedure. This Report describes about the procedure and quality control that were practiced from 1977 to 1979 in Tokai Research Establishment. (author)

  14. Test of the palladium diffuser in the JAERI Fuel Cleanup System in the Tritium Systems Test Assembly

    Konishi, Satoshi; Hayashi, Takumi; O-hira, Shigeru

    1993-03-01

    The JAERI Fuel Cleanup System (JFCU) is a major subsystem of the TSTA simulated fusion fuel loop. The palladium diffuser, that accepts simulated plasma exhaust and purifies the hydrogen isotopes mixture for the feed to the Isotope Separation System, was tested with deuterium to investigate the characteristics of the components. Permeation flow rate is a linear function of the difference of the square root of the pressure across the palladium alloy membrane. However at the low pressure region, an impediment on the permeation was observed. It was suspected to be caused by the impurity adsorbed on the surface of the permeated side of the membrane and was reduced by oxidation treatment. (author)

  15. ARGO, 1-D Neutron Diffusion in Slab, Cylindrical, Spherical Geometry from JAERI Fast-Set, ABBN, RCBN

    Ikawa, Koji

    1971-01-01

    1 - Nature of physical problem solved: ARGO is a one-dimensional (slab, cylinder or sphere), multigroup diffusion code for use in fast reactor criticality and kinetic parameter analysis. Three cross section sets, i.e., JAERI-Fast-Set, ABBN-Set and RCBN-Set, of 25 groups are prepared for the code as its library tapes. 2 - Method of solution: Eigenvalues are computed by ordinary source-iteration techniques with ordinary acceleration methods for convergence. 3 - Restrictions on the complexity of the problem: Sphere geometry

  16. JAERI 10kW High Power ERL-FEL and Its Applications in Nuclear Energy Industries

    Minehara, E J; Iijima, H; Kikuzawa, N; Nagai, R; Nishimori, N; Nishitani, T; Sawamura, M; Yamauchi, T

    2005-01-01

    The JAERI high power ERL-FEL has been extended to the more powerful and efficient free-electron laser (FEL) than 10kW for nuclear energy industries, and other heavy industries like defense, shipbuilding, chemical industries, environmental sciences, space-debris, and power beaming and so on. In order to realize such a tunable, highly-efficient, high average power, high peak power and ultra-short pulse FEL, we need the efficient and powerful FEL driven by the JAERI compact, stand-alone and zero boil-off super-conducting RF linac with an energy-recovery geometry. Our discussions on the ERL-FEL will cover the current status of the 10kW upgrading and its applications of non-thermal peeling, cutting, and drilling to decommission the nuclear power plants, and to demonstrate successfully the proof of principle prevention of cold-worked stress-corrosion cracking failures in nuclear power reactors under routine operation using small cubic low-Carbon stainless steel samples.

  17. Cylindrical core reflood test facility (CCTF) and slab core reflood test facility (SCTF) for Japan Atomic Energy Research Institute (JAERI)

    1981-01-01

    IHI has designed and constructed the CCTF at JAERI to be used in the safety analysis research on the loss of coolant accident in a PWR plant. This test facility is planned so that reflood phenomenon in the PWR plant (a phenomenon is that the bared and overheated core is reflooded by the emergency core cooling system when the coolant loss accident occurred) is simulated under various test conditions. The CCTF is the largest-scale test plant in the world, composed of approximately 2000 simulated fuel rods (electric heaters), 1 simulated pressure vessel, 4 primary cooling loops, 2 simulated steam generators, emergency core cooling system, and so on. The test conditions are controlled, and the test steps are sequentially progressed by the computing system, and test data are collected by the data acquisition system. Furthermore, IHI is now designing and constructing the SCTF in accordance with the JAERI research plan. The SCTF is similar to the CCTF in scale. Main feature of the SCTF is the form of the simulated core and the simulated pressure vessel, which is of slab construction to be representative of the radial section of the PWR reactor. Reliable and various data for safety analysis are expected by the CCTF and the SCTF. (author)

  18. Safety demonstration analyses at JAERI for severe accident during overland transport of fresh nuclear fuel

    Nomura, Yasushi; Kitao, Kohichi; Karasawa, Kiyonori; Yamada, Kenji; Takahashi, Satoshi; Watanabe, Kohji; Okuno, Hiroshi; Miyoshi, Yoshinori

    2005-01-01

    It is expected in the near future that more and more fresh nuclear fuel will be transported in a variety of transport packages to cope with increasing demand from nuclear fuel cycle facilities. Accordingly, safety demonstration analyses are planned and conducted at JAERI under contract with the Ministry of Economy, Trade and Industry of Japan. These analyses are conducted in a four year plan from 2001 to 2004 to verify integrity of packaging against leakage of radioactive material in the case of a severe accident postulated to occur during transportation, for the purpose of gaining acceptance of such nuclear fuel activities. In order to create the accident scenarios, actual transportation routes were surveyed, accident or incident records were tracked, international radioactive material transport regulations such as IAEA rules were investigated and thus, accident conditions leading to mechanical damages and thermal failure were determined to characterize the scenarios. As a result, the worst-case conditions of run-off-the-road accidents were set up to define the impact against a concrete or asphalt surface. For fire accident scenarios to be set up, collisions were assumed to occur with an oil tanker carrying lots of inflammable material in open air, or with a commonly used two-ton-truck inside a tunnel without ventilation. Then the cask models were determined for these safety demonstration analyses to represent those commonly used for fresh nuclear fuel transported throughout Japan. Following the postulated accident scenarios, the mechanical damages were analyzed by using the general-purpose finite element code LS-DYNA with three-dimensional elements. It was found that leak tightness of the package be maintained even in the severe impact scenario. Then the thermal safety was analyzed by using the general-purpose finite element code ABAOUS with three-dimensional elements to describe cask geometry. As a result of the thermal analyses, the integrity of the containment

  19. Analysis for thermal fluid dynamics in downcomer of JAERI passive safety reactor (JPSR)

    Kunii, Katsuhiko; Iwamura, Takamichi; Murao, Yoshio

    1995-01-01

    The driving-force of the natural circulation in the residual heat removal system for the JPSR (JAERI Passive Safety Reactor) under a steady condition is given as a gravity force based on the density (temperature) difference between hotter coolant in core and upper plenum and cooler coolant in downcomer. The downcomer is a very important flow pass in the system to obtain the enough driving-force because the flow pass has a three-dimensional annulus geometry long in vertical and circumference directions respectively and narrow in radius direction so that the thermal fluid flow pattern in downcomer directly relates to generation of the density difference. The density difference could naturally become smaller unless the coolant flowing into downcomer spreads widely in the whole region of it. The numerical analysis has been performed taking account of the downcomer being a three-dimensional annulus flow pass with the purposes to investigate the possibilities of the followings: (1) promotion of making the flow pattern and temperature distribution uniform in downcomer by applying a mechanical device at the inlet part of downcomer (installing a baffle) to increase the driving-force of the natural circulation, (2) achievement of an enough driving-force of the natural circulation to remove the residual heat, (3) approximation of three-dimensional thermal fluid flow in downcomer to simple one-dimensional one assumed on the preliminary design of the passive residual heat removal system. The following conclusions were obtained: (1) The effect of the baffle on the driving-force of natural circulation is little being considered due to the enhancing of mixing on thermal fluid flow in case with baffle, (2) Though the flow pattern becomes three-dimensional in some case such as large vortex flow not to be able to approximate simply to one-dimensional, the required driving-force can be obtained, (3) The driving-force can be estimated as the almost same functional value for time

  20. Report of evaluation on socio-economic effects of R and D results in Japan Atomic Energy Research Institute (JAERI)

    2002-08-01

    Japan Atomic Energy Research Institute (JAERI), as a core organization devoted to comprehensive nuclear energy research, has steadily promoted nuclear energy research aiming at long-term and stable supply of energy supporting the basis of national existence, advanced nuclear science and engineering leading to increase in Japanese industrial competitive power, etc. Through these undertaking, JAERI has produced a lot of remarkable achievements to contribute the national requests mentioned above. In total, about 1.8 trillion-yen of national funds and over 60,000 person · years of researchers and technical staffs have been invested in the R and D's for the past 45 years. Recently it has been argued and recognized to evaluate how the profits of R and D results in public research institutes supported by national funds are returned to the Japanese people as taxpayers and society as part of an administrative and financial reform. Then, seeing its 45th anniversary, JAERI has tried to evaluate the effects of the R and D achievements on the Japanese society and economy apart from the reviews on the management of the organization and research results by the ex-house experts from the viewpoints of specialty and technical aspects. In order to execute the aforementioned evaluation, JAERI established the in-house Ad hoc Committee for Evaluation of R and D Achievements where decision of the evaluation plan is made, in July 2001, and executed the evaluation followed by assembling the necessary database collected from individual branches. Results obtained from these activities were finally summarized in the Ad hoc Committee. Because a methodology for quantitative evaluation of the economical effects, i.e. cost-benefit effects of R and D's was not established yet, the evaluation was prudently carried out with the assistance of three think tanks and under advices by three ex-house experts. R and D's in JAERI are not limited to the ones where benefits corresponding to profits can be

  1. Long-term nuclear knowledge management (NKM) of innovative nuclear energy systems (INES). A case study of the Japan Atomic Energy Research Institute (JAERI)

    Yanagisawa, Kazuaki; Bezdek, Roger H.; Sawada, Tetsuo

    2008-01-01

    Within JAERI, funds invested in a 45-year study of LWR totaled 4.2b$ for research and 3.4b$ (34,718 man years) for personnel. The benefits to taxpayers from this JAERI work were estimated to be about 6.3b$ , resulting in a favorable cost-benefit ratio of 1.5 (6.3/4.2). JAERI is a national research institute and this figure may be regarded as sufficiently high, and many high risk and complex tasks were completed successfully. Funds invested in the 32-year study of HTGR were 1.5b$ for R and D and 0.3b$ (2966 man years) for personnel. Commercialized HTGR will result in a cost reduction of electricity during power generation. Retail cost is 0.36b$/year and the share of JAERI (MCP) is 0.018b$/year. Funds invested in the 32-year study of FR were 5.4b$ for R and D and 0.6b$ (6331 man years) for personnel. Estimate is that after commercialization in 2050, a FR will generate revenue from electricity as high as 1687b$ during the period 2050-2100, or 34b$/year - which is greater than that of LWR. However, there is substantial uncertainty in these estimates. To achieve long-term INES, it is necessary to develop the sustainable scenarios and the long-term robust NKM, as shown in the present study. (author)

  2. Present state of control system of tandem accelerator in JAERI. Accidents frequently occurred in 1995 fiscal year

    Hanashima, Susumu [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1996-12-01

    Tandem accelerator in JAERI (Japan Atomic Energy Research Institute) has been controlled by parallel processing control system using plural microprocessors and parallel processing programming since 1992. As the control system has been smoothly operated since beginning of its usage, many system downs have been experienced at later half of 1995. After each system down, original damage has not been found and it has been recovered by usual restarting operation. Some found remarkable defects were corrected by correction of electric circuit. As a result, frequency of the system down was decreased remarkably but its level could not be reduced to a level before occurring this phenomenon. As operation of the accelerator is preferable without control line for urgent measure, fundamental determination method is planned by controlling humidity of the control room and replacing serial highway driver with a new type producing now. (G.K.)

  3. Measurement of concentrations of {gamma}-ray emitters induced in the concrete shield of the JAERI electron linac facility

    Endo, Akira; Kawasaki, Katsuya; Kikuchi, Masamitsu [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Harada, Yasunori

    1997-07-01

    Measurement has been made to study distributions of {gamma}-ray emitters induced in the concrete shield of the JAERI electron linac facility. Core boring was carried out at seven positions to take samples from the concrete shield, and {gamma}-ray counting rates and {gamma}-ray spectra of these samples were measured with a NaI(Tl) detector and a Ge semiconductor detector, respectively. The following radionuclides were detected in the concrete samples: {sup 60}Co, {sup 134}Cs, {sup 152}Eu and {sup 154}Eu generated through thermal neutron capture reaction, and {sup 22}Na and {sup 54}Mn generated through nuclear reactions by bremsstrahlung and fast neutrons. The relation between the distributions of {gamma}-ray emitters, as a function of the depth of concrete, and the positions of core boring is discussed. (author)

  4. Research on radionuclide migration under subsurface geochemical conditions. JAERI/AECL Phase II Collaborative Program Year 1 (joint research)

    1998-11-01

    A radionuclide migration experiment program for fractured rocks was performed under the JAERI/AECL Phase-II Collaborative Program on research and development in radioactive waste management. The program started in the fiscal year 1993, as a five-year program consists of Quarried block radionuclide migration program, Speciation of long-lived radionuclides in groundwater, Isotopic hydrogeology and Groundwater flow model development. During the first year of the program (Program Year 1: March 18, 1994 - September 30, 1994), a plan was developed to take out granite blocks containing part of natural water-bearing fracture from the wall of the experimental gallery at the depth of 240 m, and literature reviews were done in the area of the speciation of long-lived radionuclides in groundwater, isotopic hydrogeology and the groundwater flow model development to proceed further work for the Program Year 2. (author)

  5. Summary report for IAEA CRP on lifetime prediction for the first wall of a fusion machine (JAERI contribution)

    Suzuki, Satoshi; Araki, Masanori; Akiba, Masato

    1993-03-01

    IAEA Coordinated Research Program (CRP) on 'Lifetime Prediction for the First Wall of a Fusion Machine' was started in 1989. Five participants, Joint Research Centre (JRC-Ispra), The NET team, Kernforschungszentrum Karlsruhe (KfK), Russian Research Center and Japan Atomic Energy Research Institute, contributed in this activity. The purpose of the CRP is to evaluate the thermal fatigue behavior of the first wall of a next generation fusion machine by means of numerical methods and also to contribute the design activities for ITER (International Thermonuclear Experimental Reactor). Thermal fatigue experiments of a first wall mock-up which were carried out in JRC-Ispra were selected as a first benchmark exercise model. All participants performed finite element analyses with various analytical codes to predict the lifetime of the simulated first wall. The first benchmark exercise has successfully been finished in 1992. This report summarizes a JAERI's contribution for this first benchmark exercise. (author)

  6. Statistical analyses of variability/reproducibility of environmentally assisted cyclic crack growth rate data utilizing JAERI Material Performance Database (JMPD)

    Tsuji, Hirokazu; Yokoyama, Norio; Nakajima, Hajime; Kondo, Tatsuo

    1993-05-01

    Statistical analyses were conducted by using the cyclic crack growth rate data for pressure vessel steels stored in the JAERI Material Performance Database (JMPD), and comparisons were made on variability and/or reproducibility of the data between obtained by ΔK-increasing and by ΔK-constant type tests. Based on the results of the statistical analyses, it was concluded that ΔK-constant type tests are generally superior to the commonly used ΔK-increasing type ones from the viewpoint of variability and/or reproducibility of the data. Such a tendency was more pronounced in the tests conducted in simulated LWR primary coolants than those in air. (author)

  7. Studies on groundwater flow and radionuclide migration at underground environments. Final report of collaboration research between JAERI and AECL

    Ogawa, Hiromichi; Nagao, Seiya; Yamaguchi, Tetsuji

    2001-01-01

    The Japan Atomic Energy Research Institute (JAERI) conducted a collaboration program Phase II with the Atomic Energy of Canada Limited (AECL) from 1994 to 1998. The program was started to contribute the establishment of safety assessment methodology for the geological disposal of high-level radioactive wastes on the basis of the results from the Phase I program (1987-1993). The Phase II program consisted of following experimental items: (1) radionuclide migration experiments for quarried blocks (1m x 1m x 1m) of granite with natural fracture under in-situ geochemical conditions at 240 m level of Underground Research Laboratory of AECL; (2) study on the effects of dissolved organic materials extracted from natural groundwaters on radionuclide migration; (3) study on groundwater flow using environmental isotopes at two different geologic environments; (4) development of groundwater flow and radionuclide transport model for heterogeneous geological media. The mobility of radionuclides was retarded in the fracture by the deep geological conditions and the fracture paths. The groundwater humic substances with high molecular size were enhanced for the mobility of radionuclides in the sand and granitic media due to the complexation. The application of 36 Cl and 129 I for the analysis on the long-term groundwater flow can be validated on the basis of investigation at the URL site. Moreover, the geostatistical model for the analysis on groundwater flow and radionuclide migration was developed, and was able to describe the groundwater flow and the migration of environmental tracers at AECL sites. This report summaries the results of the Phase II program between JAERI and AECL. (author)

  8. Studies on groundwater flow and radionuclide migration at underground environments. Final report of collaboration research between JAERI and AECL

    Ogawa, Hiromichi; Nagao, Seiya; Yamaguchi, Tetsuji [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] [and others

    2001-01-01

    The Japan Atomic Energy Research Institute (JAERI) conducted a collaboration program Phase II with the Atomic Energy of Canada Limited (AECL) from 1994 to 1998. The program was started to contribute the establishment of safety assessment methodology for the geological disposal of high-level radioactive wastes on the basis of the results from the Phase I program (1987-1993). The Phase II program consisted of following experimental items: (1) radionuclide migration experiments for quarried blocks (1m x 1m x 1m) of granite with natural fracture under in-situ geochemical conditions at 240 m level of Underground Research Laboratory of AECL; (2) study on the effects of dissolved organic materials extracted from natural groundwaters on radionuclide migration; (3) study on groundwater flow using environmental isotopes at two different geologic environments; (4) development of groundwater flow and radionuclide transport model for heterogeneous geological media. The mobility of radionuclides was retarded in the fracture by the deep geological conditions and the fracture paths. The groundwater humic substances with high molecular size were enhanced for the mobility of radionuclides in the sand and granitic media due to the complexation. The application of {sup 36}Cl and {sup 129}I for the analysis on the long-term groundwater flow can be validated on the basis of investigation at the URL site. Moreover, the geostatistical model for the analysis on groundwater flow and radionuclide migration was developed, and was able to describe the groundwater flow and the migration of environmental tracers at AECL sites. This report summaries the results of the Phase II program between JAERI and AECL. (author)

  9. Evaluation of socio-economic effects of R and D results at Japan Atomic Energy Research Institute. 2. Socio-economic evaluation of the basic research at JAERI

    2003-11-01

    The Japan Atomic Energy Research Institute (JAERI), as a core organization devoted to comprehensive nuclear energy research, has steadily promoted various types of research and development (R and D) studies since its establishment in June 1956. Research activities are aimed at performing (1) R and D for nuclear energy, (2) the utilization and application of radiation-based technologies, and (3) the establishment of basic and fundamental research in the nuclear field. Last year, the socio-economic effects on items (1) and (2) were qualitatively and quantitatively evaluated. The quantitative evaluation of item (3) from the viewpoint of a socio-economic effect, however, calls for a different concept and methodology than previously used cost-benefit approach. Achievements obtained from the activities conducted over the last 10 years implied that socio-economics in basic research funded by the public could contribute to the (1) increase in useful intellectual stocks, (2) upbringing of highly skilled college graduates, (3) construction of new scientific facilities and creation of methodologies, (4) stimulation and promotion of social interrelations by networking, (5) increase of one's ability to solve scientific problems, and (6) establishment of venture companies. In this study, we focused on item (4) for the analysis because it assumed that the external economic effect has a link with the socio-economic effects accompanying the networking formation. For the criteria of socio-economic effects we assume that the external effect becomes significant in proportion to the width of networking and/or the magnitude of cooperation measured by numbers of co-writing studies between JAERI and the research bodies, namely private and governmental sectors and universities. Taking these criteria into consideration, the subsequent four items are prepared for quantitative study. They are (1) to clarify the basic research fields where JAERI has been established a significant effort to

  10. Preparation and certification of certified reference materials JAERI-Z21, Z22 and Z23 for analysis of zirconium and its alloys

    Takashima, Kyoichiro

    1991-03-01

    The Sub-Committee on Chemical Analysis of Nuclear Materials was organized in April 1987, under the Committee on Analytical Chemistry of Nuclear Fuels and Reactor Materials, JAERI, for renewal of certified reference materials of zirconium base alloys and zirconium metal. Collaborative analysis was carried out among ten participating laboratories for the certification of the JAERI CRMs Z21 to Z23. As a results of the collaborative works, the certified values for sixteen elements (Sn, Fe, Ni, Cr, Hf, Al, Si, Co, Cu, Ti, Mn, Pb, U, Cd, B and W) in the CRMs were given. In this report, preparation of raw materials, homogeneity test, chemical analysis for certification by collaborative works during April 1987 to March 1990 are described. (author)

  11. Investigation of environmental radioactivity in waste dumping areas of the far eastern seas. JAERI's activities in the 1st Japanese-Korean-Russian joint expedition 1994

    Amano, Hikaru; Matsunaga, Takeshi; Yabuuchi, Noriaki.

    1996-10-01

    Large quantities of radioactive waste have been dumped in the Far Eastern Sea by the former USSR and Russia. In order to survey marine radioactive contamination in the Far Eastern Sea, the first Japanese-Korean-Russian joint expedition was conducted according to the governmental agreement. The joint expedition was conducted at the areas of the Russian radioactive waste dumping site from March 18 1994 to April 6, 1994. JAERI participated in this expedition according to the request from STA Japan, and conducted mainly on-board measurement of marine radioactivities. The results showed that the radionuclides concentrations in seawater and seabed sediment samples from the study site were not different from those in the western North Pacific. This report summarises JAERI's activities in the expedition. Final report by Japanese-Korean-Russian government and IAEA is annexed. (author)

  12. Intraoperative boron neutron capture therapy for malignant gliomas. First clinical results of Tsukuba phase I/II trial using JAERI mixed thermal-epithermal beam

    Matsumura, A.; Yamamoto, T.; Shibata, Y.

    2000-01-01

    Since October 1999, a clinical trial of intraoperative boron neutron capture therapy (IOBNCT) is in progress at JRR-4 (Japan Research Reactor-4) in Japan Atomic Energy Research Institute (JAERI) using mixed thermal-epithermal beam (thermal neutron beam I: TNB-I). Compared to pure thermal beam (thermal neutron beam II: TNB-II), TNB-I has an improved neutron delivery into the deep region than TNB-II. The clinical protocol and the preliminary results will be discussed. (author)

  13. Current status of JAERI program on development of ultra-trace-analytical technology for safeguards environmental samples

    Adachi, T.; Usuda, S.; Watanabe, K.

    2001-01-01

    Full text: In order to contribute to the strengthened safeguards system based on the Program 93+2 of the IAEA, Japan Atomic Energy Research Institute (JAERI) is developing analytical technology for ultra-trace amounts of nuclear materials in environmental samples, and constructed the CLEAR facility (Clean Laboratory for Environmental Analysis and Research) for this purpose. The development of the technology is carried out, at existing laboratories for time being, in the following fields: screening, bulk analysis and particle analysis. The screening aims at estimating the amounts of nuclear materials in environmental samples to be introduced into the clean rooms, and is the first step to avoid cross-contamination among the samples and contamination of the clean rooms themselves. In addition to ordinary radiation spectrometry, Compton suppression technique was applied to low energy γ- and X-ray measurements, and sufficient reduction in background level has been demonstrated. Another technique in examination is imaging-plate method, which is a kind of autoradiography and suitable for determination of radioactive-particle distribution in the samples as well as for semiquantitative determination. As for the bulk analysis, the efforts are temporally made on uranium in swipe samples. Preliminary examination for optimization of sample pre-treatment conditions is in progress. At present, ashing by low-temperature-plasma method gives better results than high-temperature ashing or acid leaching. For the isotopic ratio measurement, instrumental performance of inductively-coupled plasma mass spectrometry (ICP-MS) are mainly examined because sample preparation for ICP-MS is simpler than that for thermal ionization mass spectrometry (TIMS). It was found by our measurement that the swipe material (TexWipe TX304, usually used by IAEA) contains un-negligible uranium blank with large deviation (2-6 ng/sheet). This would introduce significant uncertainty in the trace analysis. JAERI

  14. Development of authentication system for the fast critical assembly (FCA) portal monitor (P/M) and penetration monitor (PN/M) systems of JAERI

    Ogawa, Hironobu; Mukaiyama, Takehiko

    1999-05-01

    The advanced comprehensive containment and surveillance system for the Fast Critical Assembly facility (FCA) of the Japan Atomic Energy Research Institute (JAERI) consists of a Portal monitor (P/M) and a Penetration Monitor (PN/M) systems. The development of these systems was completed in 1988 for alleviating the burdens of manpower and radiation problems in the frequent NDA inspections. After the completion of the field trial test (Phase III), in 1990, the International Atomic Energy Agency (IAEA) accepted the system on condition that an independent IAEA authentication equipment would be provided. The development of the authentication measures was carried out jointly by both the Japan Support Programme for Agency Safeguards (JASPAS) and the U.S. Program of Technical Assistance to IAEA Safeguards (POTAS), and also under the research agreement for the safeguards research and development between JAERI and the US Department of Energy (USDOE). The concept and design requirements of the authentication system were developed by IAEA, but the design and development of the authentication equipment were jointly funded both by JASPAS and POTAS, and also the fund of JAERI was provided for the Sandia National Laboratories (SNL) through USDOE. SNL developed and constructed the authentication system in two phase as Phase I and Phase II. JAERI financed the development of the Phase I and Phase II hardware and software, and the installation of the authentication equipment at the FCA facility, and also carried out the modification of the circuitry and devices for both the P/M and the PN/M systems as well as the reconstruction of the PN/M Junction Unit for compatibility with the implementation of the authentication measures. After the completion of consecutive field trial test of the P/M, the PN/M and the authentication system, IAEA accepted the entire system as an effective and efficient routine inspection measures in 1996. This report describes the modification and reconstruction of

  15. Present status of nuclear power safety studies in JAERI, 1996; Genshiryoku anzensei kenkyu no genjo, heisei-8-nen

    NONE

    1996-10-01

    Japan Atomic Energy Research Institute has promoted the research on the engineering safety for nuclear reactors and nuclear fuel cycle facilities, the research on environmental safety for the objects of environmental radiation and radioactivity and the treatment and disposal of radioactive waste, and the development of the future technology related to the heightening of safety, according to the long term plan on the research, development and utilization of atomic energy that the state decided and the annual plan of various safety researches. It is an internationally important responsibility to ensure the safety, and JAERI has positively promoted bilateral and multilateral international cooperation and the exchange of information. In fiscal year 1995, the criticality experiment facility, the back end research facility, the waste disposal research facility and so on started the operation, and the researches on the soundness of high burnup fuel, the severe accidents of LERs, the abnormal chemical reaction in a fuel reprocessing plant, and the evaluation of environment radioactivity around Chernobyl were carried out. In this book, the results of the research on the safety carried out in fiscal year 1995 are reported synthetically. (K.I.)

  16. Thermal-hydraulic design of cross-flow type mercury target for JAERI/KEK joint project

    Kaminaga, Masanori; Terada, Atsuhiko; Haga, Katsuhiro; Kinoshita, Hidetaka; Hino, Ryutaro

    2001-01-01

    The Japan Atomic Energy Research Institute (JAERI) and the High Energy Accelerator Research Organization (KEK) are promoting a plan to construct a neutron scattering facility. In the facility, 1 MW pulsed proton beam from a high-intensity proton accelerator will be injected into a mercury target in order to produce high-intensity neutrons for use in the fields of life and material sciences. In the spallation mercury target system design, an integrated structure of target vessel with a safety hull was proposed to ensure the safety and to collect mercury in case of mercury leakage caused by the target beam window failure. The inner structure arrangement of the mercury target vessel was determined based on the thermal hydraulic analytical results of 3 GeV, 1 MW proton beam injection. The safety hull consists of vessels for helium and heavy water. The vessels for mercury target, helium and heavy water will be connected each other by reinforcement ribs mounted on the surface of each vessel. From the structural analyses, the structural integrity of the safety hull would be maintained under the static pressure of 0.5 MPa. (author)

  17. A proposal of a beam injection device for the proton storage ring of JAERI neutron science project

    Suzuki, Yasuo

    1998-01-01

    A new injection device (a charge-exchange device) with light and magnetic field, is proposed for a proton storage ring of JAERI Neutron Science Project. This injection device is composed of a neutralizer and an ionizer. The neutralizer strips electrons of H 0 beam into H - one with the undulator magnetic field. The ionizer which is composed of undulator magnets and an optical resonator placed along a straight part in the storage ring, can ionize effectively the H 0 beam excited to n=3 level by a laser beam into H + one. Adopting the 2nd harmonics of Nd : YAG laser, the powerful laser on the market can be used, and the required items of the technological development can be minimized. The energy of the particle beam, however, should be accelerated up to 1.587 GeV by 6% increase from 1.5 GeV. In this device, the non-charge-exchange rate and beam-spill can be minimized by decreasing the deflection angle of the beam which occurs at the charge-exchange process. This method can be realized with exiting technologies and there are not any effects on the trajectory of the ring-circulating proton beam due to scatterings by the foil as the usual charge-exchange devices. This device, therefore, will be an optimal and highly effective method of the least beam-spill as the injector of the high power proton storage ring. (author)

  18. Annual report of the activities of health physics in JAERI in 1999. April 1, 1999 - March 31, 2000

    NONE

    2001-03-01

    This annual report summarizes the activities in fiscal year 1999 concerned with radiation protection which cover environmental monitoring of the facilities, radiation protection of workplace and workers, individual monitoring, maintenance of monitoring instruments, and their technical development, carried out at the establishments of Tokai, Naka, Takasaki, Oarai, Kansai and Mutsu of JAERI. The report also covers the research activities of 4 research laboratories for Radiation Risk Analysis, Internal Dosimetry, External Dosimetry and Calibration Standards and Measurement which were authorized in Department of Health Physics in Tokai Establishment in April 1999. There are no occupational exposure and effluent release recorded exceeding the prescribed limits for effective dose equivalent and radioactive concentrations for gaseous release and liquid waste. In September 30 in 1999, the JCO criticality accident occurred in Tokai village and the Department of Health Physics of Tokai Establishment, Radiation Protection Division of Oarai Establishment and Safety Division of Naka Establishment took cooperative activities for surveying the level of radiation and radioactivity in the environment, radiation protection in terminating the criticality, sending specialists for the consultant of radiation protection to local government and others, surveying the radioactive contamination of the evacuated public, play ground of schools and others. The estimations of dose for the public and total fissions from the measurement of neutron activated samples collected near JCO were carried out at External Dosimetry Laboratory and Calibration Standards and Measurement Division respectively in Department of Health Physics of Tokai Establishment. (author)

  19. Establishment of the observing system for boron in steels by alpha-particle track etching method using JAERI reactor

    Asakura, Kentaro; Shibata, Koji; Sawahata, Hiroyuki; Kawate, Minoru; Harasawa, Susumu

    2003-01-01

    Alpha-particle track etching (ATE) method is most effective in observing boron distribution in steels. Previously, in Japan, neutron irradiation for this method was carried out in the reactor at the Institute of Atomic Energy, Rikkyo University. This reactor, however, was shut down in 1999. Therefore, the establishment of a new system for ATE method has been required and experimental research was performed using the reactor at the Japan Atomic Energy Research Institute (JAERI). It was clarified that the irradiation equipment for medical treatment of the reactor JRR-4 was most suitable for ATE method. The specimen trestle for low radioactive exposure was newly-developed. ATE image obtained by 12h irradiation using this trestle showed a good quality similar to that obtained using Rikkyo's reactor and that obtained using the trestle of the old model. Using this new trestle, the amount of neutron which the worker suffers during the operation at the irradiation equipment decreases from 4μSv/h to 0-1 μSv/h compared with the trestle of the old model. The total amount of thermal neutron after 12 h irradiation was almost same as that under the recommended condition of the reactor at Rikkyo University, 6.5 x 10 14 n cm -2 . (author)

  20. Phase IIA and IIB experiments of JAERI/U.S.DOE collaborative program on fusion blanket neutronics

    Oyama, Yukio

    1989-12-01

    Phase IIA and IIB experiments on fusion blanket neutronics has been performed on a basis of JAERI/USDOE collaborative program. In the Phase II experimental series, a D-T neutron source and a test blanket were contained by a lithium-carbonate enclosure to adjust the incident neutron spectrum to the test blanket so as to simulate that of a fusion reactor. First two series of the Phase II, IIA and IIB, focused especially on influences of beryllium configurations for neutron multiplying zone to neutronic parameters. Measured parameters were tritium production rate using Li-glass and NE213 scintillators, and Li-metal foil and Lithium-oxide block with liquid scintillation technique; neutron spectrum using NE213 scintillator and proton recoil proportional counter; reaction rate using foil activation technique. These parameters were compared among six different beryllium configurations of the experimental system. Consistency between different techniques for each measured parameter was also tested among different experimental systems and confirmed to be within experimental errors. This report describes, in detail, experimental conditions, assemblies, equipments and neutron source in Part I. The part II compiles all information required for a calculational analysis of this experiment, e.g., dimensions of the target room, target assembly, experimental assembly, their material densities and numerical data of experimental results. This compilation provides benchmark data to test calculation models and computing code systems used for a nuclear design of a fusion reactor. (author)

  1. User's manual of a supporting system for treatment planning in boron neutron capture therapy. JAERI computational dosimetry system

    Kumada, Hiroaki; Torii, Yoshiya

    2002-09-01

    A boron neutron capture therapy (BNCT) with epithermal neutron beam is expected to treat effectively for malignant tumor that is located deeply in the brain. It is indispensable to estimate preliminarily the irradiation dose in the brain of a patient in order to perform the epithermal neutron beam BNCT. Thus, the JAERI Computational Dosimetry System (JCDS), which can calculate the dose distributions in the brain, has been developed. JCDS is a software that creates a 3-dimensional head model of a patient by using CT and MRI images and that generates a input data file automatically for calculation neutron flux and gamma-ray dose distribution in the brain by the Monte Carlo code: MCNP, and that displays the dose distribution on the head model for dosimetry by using the MCNP calculation results. JCDS has any advantages as follows; By treating CT data and MRI data which are medical images, a detail three-dimensional model of patient's head is able to be made easily. The three-dimensional head image is editable to simulate the state of a head after its surgical processes such as skin flap opening and bone removal for the BNCT with craniotomy that are being performed in Japan. JCDS can provide information for the Patient Setting System to set the patient in an actual irradiation position swiftly and accurately. This report describes basic design and procedure of dosimetry, operation manual, data and library structure for JCDS (ver.1.0). (author)

  2. Annual report of the activities of health physics in JAERI in 2001. April 1, 2001 - March 31, 2002

    NONE

    2002-12-01

    This annual report summarizes the activities in fiscal year 2001 concerned with radiation protection which cover environmental monitoring of the facilities, radiation protection of workplace and workers, individual monitoring, maintenance of monitoring instruments, and their technical development, carried out at the establishments of Tokai, Naka, Takasaki, Oarai, Kansai and Mutsu of JAERI. The report also covers the research activities of 4 research laboratories, i.e., Radiation Risk Analysis, Internal Dosimetry, External Dosimetry and Calibration Standards and Measurement, in the Department of Health Physics in Tokai Research Establishment. There are no occupational exposure and effluent release recorded exceeding the prescribed limits for effective dose and radioactivity concentrations for gaseous release and liquid waste. As for the R and D activities at the Department of Health Physics in Tokai Research Establishment, studies were conducted focusing mainly on the themes concerning elucidation of low-dose radiation effect and radiation risk assessment, dose estimations and radiation protection on external and internal exposures for high-energy accelerator utilization, and establishment of neutron calibration fields using an accelerator and the measurement techniques related to their traceability. (author)

  3. User's manual of a supporting system for treatment planning in boron neutron capture therapy. JAERI computational dosimetry system

    Kumada, H

    2002-01-01

    A boron neutron capture therapy (BNCT) with epithermal neutron beam is expected to treat effectively for malignant tumor that is located deeply in the brain. It is indispensable to estimate preliminarily the irradiation dose in the brain of a patient in order to perform the epithermal neutron beam BNCT. Thus, the JAERI Computational Dosimetry System (JCDS), which can calculate the dose distributions in the brain, has been developed. JCDS is a software that creates a 3-dimensional head model of a patient by using CT and MRI images and that generates a input data file automatically for calculation neutron flux and gamma-ray dose distribution in the brain by the Monte Carlo code: MCNP, and that displays the dose distribution on the head model for dosimetry by using the MCNP calculation results. JCDS has any advantages as follows; By treating CT data and MRI data which are medical images, a detail three-dimensional model of patient's head is able to be made easily. The three-dimensional head image is editable to ...

  4. Construction of 144, 565 keV and 5.0 MeV monoenergetic neutron calibration fields at JAERI.

    Tanimura, Y; Yoshizawa, M; Saegusa, J; Fujii, K; Shimizu, S; Yoshida, M; Shibata, Y; Uritani, A; Kudo, K

    2004-01-01

    Monoenergetic neutron calibration fields of 144, 565 keV and 5.0 MeV have been developed at the Facility of Radiation Standards of JAERI using a 4 MV Pelletron accelerator. The 7Li(p,n)7Be and 2H(d,n)3He reactions are employed for neutron production. The neutron energy was measured by the time-of-flight method with a liquid scintillation detector and calculated with the MCNP-ANT code. A long counter is employed as a neutron monitor because of the flat response. The monitor is set up where the influence of inscattered neutrons from devices and their supporting materials at a calibration point is as small as possible. The calibration coefficients from the monitor counts to the neutron fluence at a calibration point were obtained from the reference fluence measured with the transfer instrument of the primary standard laboratory (AIST), a 24.13 cm phi Bonner sphere counter. The traceability of the fields to AIST was established through the calibration.

  5. Accounting control of tritium at the tritium process laboratory (TPL) of JAERI. Results of 15-year operation and research activity

    Nishi, Masataka; Yamanishi, Toshihiko; Hayashi, Takumi; Yamada, Masayuki; Suzuki, Takumi

    2003-01-01

    Research and development work of fuel processing technology and tritium safe-handling technology necessary for fusion reactors has been performed at the Tritium Process Laboratory (TPL) of JAERI. TPL is the first facility in Japan permitted to handle tritium of more than 1g (about 0.36PBq), and its operation itself is also important for the development of fusion reactor facility in the viewpoint of tritium control. Various experiments have been carried out at TPL safely since 1988 controlling 22PBq of tritium as the maximum observing regulations. In addition to the regulatory accounting and control, detailed independent control in TPL was planned and was established through its 15-year safe-operation. For future fusion fuel facility where kilo-grams of tritium will be handled, method of tritium accounting has been researched and some new technologies have been developed at TPL. Results of TPL operation and of the research activity in it contributed the completion of the engineering design of ITER. Further research activity on tritium accounting and control is in progress in TPL for the future fusion reactors. (author)

  6. The development of divertor and first wall armour parts at JAERI, Sandia N.L. and KFA Juelich

    Akiba, M.; Bolt, H.; Watson, R.; Kneringer, G.; Linke, J.

    1991-01-01

    The development of new armour materials, and fabrication and testings of the divertor and first wall mock-ups have worldwidely been carried out during the Conceptual Design Activites (CDA) of ITER. This paper is a review of the activities on the divertor and first wall armour components which has been performed by JAERI, Sandia National Laboratory, and KFA Juelich. The design requirements have instantly been reflected in material development. For instance, carbon fiber composites (CFCs) have already been developed to have a thermal conductivity as high as copper at room temperature. Further modification of CFC's has been made. Based on the extensive progress in armour materials, the fabrication and testings of mock-ups have been started. Divertor mock-ups which are able to endure a stationary heat flux of 8 to 15 MW/m 2 have already been developed. Some new high heat flux test facilities have been constructed and are able to simulate a heat load of plasma disruption. Extensive understanding on disruption erosion of the armour materials has been obtained by experiments with these facilities. Some mock-up tests and disruption simulating tests have been performed under international collaboration. (orig.)

  7. Annual report of the activities of health physics in JAERI in 2000. April 1, 2000 - March 31, 2001

    NONE

    2001-12-01

    This annual report summarizes the activities in fiscal year 2000 concerned with radiation protection which cover environmental monitoring of the facilities, radiation protection of workplace and workers, individual monitoring, maintenance of monitoring instruments, and their technical development, carried out at the establishments of Tokai, Naka, Takasaki, Oarai, Kansai and Mutsu of JAERI. The report also covers the research activities of 4 research laboratories, i.e., Radiation Risk analysis, Internal Dosimetry, External Dosimetry and Calibration Standards and Measurement, in Department of Health Physics in Tokai Research Establishment. There are no occupational exposure and effluent release recorded exceeding the prescribed limits for effective dose equivalent and radioactive concentrations for gaseous release and liquid waste. 10th International Conference of the International Radiation Protection Association (IRPA) was held in May in 2000, and lots of cooperative activities for supporting the conference, such as presentations, attending the organizing or executive committees, etc. were made. Cooperative works concerning measurement of radiation dose and air concentration of large amount of monazite found in Saitama and Nagano prefectures were carried out and also for advice for the measures. The data such as radioactive air concentration or shielding factors obtained by the research and development for internal dosimetry and external dosimetry was adopted in the prescriptions of the regulations concerning prevention from radiation hazard in Japan. (author)

  8. Simulation study of intentional tritium release experiments in the caisson assembly for tritium safety at the TPL/JAERI

    Iwai, Y.; Hayashi, T.; Kobayashi, K.; Nishi, M.

    2001-01-01

    At the Tritium Process Laboratory (TPL) in Japan Atomic Energy Research Institute (JAERI), Caisson assembly for tritium safety study (CATS) with 12 m 3 of large airtight vessel (Caisson) was fabricated for confirmation and enhancement of fusion reactor safety to estimate the tritium behavior in the case, where the tritium leak accident should happen. One of the principal objectives of the present studies is the establishment of simulation method to predict the tritium behavior after the tritium leak accident should happen in a ventilated room. As for the understanding of initial tritium behavior until the tritium concentration become steady, the precise estimation of local flow rate in a room and time-dependent release behavior from the leak point are essential to predict the tritium behavior by simulation code. The three-dimensional eddy flow model considering, tritium-related phenomena was adopted to estimate the local flow rate in the 50 m 3 /h ventilated Caisson. The time-dependent tritium release behavior from the sample container was calculated by residence time distribution function. The calculated tritium concentrations were in good agreement with the experimental observations. The primary removal tritium behavior was also investigated by another code. Tritium gas concentrations decreased logarithmically to the time by ventilation. These observations were understandable by the reason that the flow in the ventilated Caisson was regarded as the perfectly mixing flow. The concentrations of tritiated water measured, and indications of tritium concentration by tritium monitors became gradually flat. This phenomena called 'tritium soaking effect' was found to be reasonably explained by considering the contribution of the exhaustion velocity by ventilation system, and the adsorption and desorption reaction rate of tritiated water on the wall material which is SUS 304. The calculated tritium concentrations were in good agreement with the experimental observations

  9. A review of research and development on accelerator-driven system for transmutation of long-lived nuclear waste at JAERI

    Oigawa, H.

    2004-01-01

    The dedicated transmutation system using the accelerator driven subcritical system (ADS) has been studied in the Japan Atomic Energy Research Institute (JAERI) to reduce the burden of the final disposal of the nuclear waste. A subcritical reactor with the thermal power of 800 MW is proposed, where 250 kg of minor actinide (MA) can be transmuted annually. A superconducting linear accelerator (LINAC) with the beam power of 20-30 MW is necessary for this ADS. Lead-bismuth eutectic (LBE) is used for both the spallation target and the core coolant. Many research and development activities including the design study are under way and planned at JAERI to examine the feasibility of the ADS. In the design study, optimization of the ADS design is under way in terms of neutronics and structural feasibility. In the field of the proton accelerator, a superconducting LINAC is being developed. In the field of the LBE technology, material compatibility, thermal-hydraulics and polonium behavior are being studied. The irradiation effect of structural material to be used for the beam window is also being studied. In the field of the reactor physics of the subcritical core fueled with MA, the reliability of nuclear data is examined and the subcriticality monitoring technique is being investigated. Moreover, in the framework of J-PARC project (Japan Proton Accelerator Research Complex), JAERI plans to construct the Transmutation Experimental Facility (TEF) to demonstrate the feasibility of the ADS with using high-energy proton beam, to accumulate valuable knowledge about reactor physics and operation of ADS, and to establish a database for LBE spallation target and relevant materials. (author)

  10. Proceeding of the workshop on the results of the cooperative research between JAERI and CHESCIR concerning the study on assessment and analysis of environmental radiological consequences and verification of an assessment system

    Amano, Hikaru; Saito, Kimiaki (eds.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2001-03-01

    This workshop was organized and sponsored by the Japan Atomic Energy Research Institute (JAERI) and Chernobyl Science and Technology Center for International Research (CHESCIR). JAERI and CHESCIR have conducted 8 years research cooperation from 1992 to 1999 concerning the study on assessment and analysis of environmental radiological consequences and verification of an assessment system, focusing on the Chernobyl contaminated area. It contained 3 research subjects. Subject-1 initiated at 1992 and focused the study on measurements and evaluation of environmental external exposure after nuclear accident. Subject-2 initiated at 1992 and focused the study on the validation of assessment models in an environmental consequence assessment methodology for nuclear accidents. Subject-3 initiated at 1995 and focused on the study on migration of radionuclides released into terrestrial and aquatic environment after nuclear accidents. This workshop was held to summarize the research cooperation between JAERI and CHESCIR, and to discuss future research needs in this field. (author)

  11. Environmental monitoring data around the Chernobyl nuclear power plant used in the cooperative research project between JAERI and CHESCIR (Ukraine). Cooperative research

    Ueno, Takashi; Matsunaga, Takeshi; Amano, Hikaru

    2003-01-01

    This report is a compilation of the shared data derived from the environmental monitoring by RADEK (The state Enterprise for Region Monitoring of Environment and Dosimetric Control of Ukraine) and the record of environmental characteristics derived from field observations during a research project (1992-1999) between JAERI (Japan Atomic Energy Research Institute) and CHESCIR (Chernobyl Science and Technology Centre for International Research). The compiled data in this report are especially related to one particular research subject (Subject-3) of the project on the migration of radionuclides released into the terrestrial and aquatic environments after a nuclear accident. The present report shows the basis of published works concerning Subject-3. (author)

  12. The JAERI program for development of safety assessment models and acquisition of data needed for assessment of geological disposal of high-level radioactive wastes

    Matsuzuru, H.

    1991-01-01

    The JAERI is conducting R and D program for the development of safety assessment methodologies and the acquisition of data needed for the assessment of geologic disposal of high-level radioactive wastes, aiming at the elucidation of feasibility of geologic disposal in Japan. The paper describes current R and D activities to develop interim versions of both a deterministic and a probabilistic methodologies based on a normal evolution scenario, to collect data concerning engineered barriers and geologic media through field and laboratory experiments, and to validate the models used in the methodologies. 2 figs., 2 refs

  13. Development of an optical resonator with high-efficient output coupler for the JAERI far-infrared free-electron laser

    Nagai, Ryoji; Hajima, Ryoichi; Nishimori, Nobuyuki; Sawamura, Masaru; Kikuzawa, Nobuhiro; Shizuma, Toshiyuki; Minehara, Eisuke

    2001-01-01

    An optical resonator with a high-efficient output coupler was developed for the JAERI far-infrared free-electron laser. The optical resonator is symmetrical near-concentric geometry with an insertable scraper output coupler. As a result of the development of the optical resonator, the JAERI-FEL has been successfully, lased with averaged power over 1 kW. Performance of the optical resonator with the output coupler was evaluated at optical wavelength of 22 μm by using an optical mode calculation code. The output coupling and diffractive loss with a dominant eigen-mode of the resonator were calculated using an iterative computation called Fox-Li procedure. An efficiency factor of the optical resonator was introduced for the evaluation of the optical resonator performance. The efficiency factor was derived by the amount of the output coupling and diffractive loss of the optical resonator. It was found that the optical resonator with the insertable scraper coupler was the most suitable to a high-power and high-efficient far-infrared free-electron laser. (author)

  14. Fuel irradiation research of Japan at OECD Halden Reactor Project. Achievement of joint researches between JAERI and other organizations in the period from 1994 to 1996

    Uetsuka, Hiroshi; Nakamura, Jinichi; Kinoshita, Motoyasu

    1998-01-01

    JAERI has performed cooperative researches with many Japanese agencies and companies by means of the Halden Boiling Heavy Water Reactor (HBWR) which is located at Halden in Norway. These cooperative researches are carried out based on the contracts of the cooperative researches, which are revised every three years, in accordance with the renewal of the participation of JAERI to the OECD Halden Reactor Project. This report summaries the objectives, contents and the outlines of the achievements of the cooperative researches during the three years from 1994 January to 1996 December. During the period, ten cooperative researches had been carried out, and two of them had finished during the period and other eight researches has been continued to the next three year period. There are many research items, and most of them are irradiation test researches of advanced fuel and cladding concerned with the high burnup utilization of LWR fuel or MOX fuel irradiation researches to prepare for the introduction of Plutonium utilization in LWRs. The researches of fuel irradiation usually take long time because of the characteristics of these kind of research work, and three years are usually not enough to obtain some achievements from the irradiation tests. Therefore, eight tests have been continued after the three year period. In this report, the achievements of the continued researches to the next three year period are not final one but a kind of progress report. (author) kind of progress report. (author)

  15. Fuel irradiation research of Japan at Halden reactor. Achievement of cooperative researches between JAERI and several organizations in the period from 2000 to 2002 (Joint research)

    2004-03-01

    JAERI has performed cooperative researches with several Japanese organizations utilizing the Halden Boiling Heavy Water Reactor(HBWR) which is located at Halden in Norway. These researches are carried out based on the contracts of the cooperative researches, which are revised every three years, in accordance with the renewal of the participation of JAERI to the OECD Halden Reactor Project. This report summarizes the objectives, contents and outlines of the achievements of the cooperative researches during the three years from 2000 January to 2002 December. During the period, seven cooperative researches had been carried out. Two of them had been completed and other five researches have been continued to the next three-year period. Most of them are irradiation test researches of advanced fuel and cladding in order to prepare the higher burnup utilization and introduction of LWR fuel and MOX fuel in LWRs of Japan. As the researches of fuel irradiation usually take long time for preparing test and irradiation, three years are usually not enough to obtain some achievements from the irradiation tests. Therefore, five cooperative researches have been continued to the next three-year period. In this report, the achievements of the researches continued to the next period are not final one but a kind of progress report. (author)

  16. Long-Term Nuclear Knowledge Management (NKM) on Nuclear Production of Hydrogen - A Case Study of the Japan Atomic Energy Research Institute (JAERI)

    Yanagisawa, Kazuaki

    2007-01-01

    In Japan, so-called a formal nuclear policy; The Framework for Nuclear Energy Policy is built up by Japan Atomic Energy Commission at every 5-year, in which not only a conventional light water reactor (LWR) but also a fast breeder reactor (FBR), HTGR and a fusion reactor (FR) is referred as a prominent candidate of long-term (<100 years) nuclear energy source. The policy makers might have multi-purpose scenarios for a future of innovated nuclear energy systems through results of various discussions at their level. According to long-term nuclear knowledge management, the author made ex ante evaluation of HTGR known as the intellectual assets of JAERI 1, from the viewpoint of hypothetical benefits under conditions of substantial uncertainty. Nuclear knowledge management (NKM) is an integrated, systematic approach to identifying, managing and sharing an organization's nuclear knowledge, and enabling persons to create new nuclear knowledge collectively and thereby helping achieve the objectives. NKM identifies, optimizes, and actively manages intellectual assets either in the form of explicit knowledge held in intangible products or tacit knowledge possessed by individuals or communities in the nuclear fields. In the present study the authors wish not only to show the validity of long-term NKM as a key factor of HTGR but also to assess their hypothetical benefits through the year 2050 under conditions of substantial uncertainty. It should be stressed that those factors are important intellectual assets of JAERI developed to date. Additionally, in the Framework for Nuclear Energy Policy constructed up by the Japan Atomic Energy Commission, a LWR, a fast breeder reactor (FBR), a HTGR, and a fusion reactor (FR) are all defined as eligible and prominent candidates for long-term nuclear energy sources. In this sense, we estimate here a direct market creation of (1) hydrogen energy production and (2) electricity generation, by commercialized HTGR through the year 2050 with

  17. Proceedings of the seminar on the joint research project between JAERI and Universities. 'Actinide researches for 21st century - fusion between chemistry and engineering'. August 20-21, 1999, Japan Atomic Energy Research Inst., Tokai, Japan

    NONE

    2000-06-01

    The Seminar on the Joint Research Project between JAERI and Universities was held in Tokai, August 20-21, 1999, to discuss future perspectives of the actinide researches for the nuclear fuel cycle. The papers related to the Joint Research Project on the Backend Chemistry were presented and discussed. The present report complies the papers contributed to the Seminar. (author)

  18. Proceedings of the seminar on the joint research project between JAERI and Universities. 'Actinide researches for 21st century - fusion between chemistry and engineering'. August 20-21, 1999, Japan Atomic Energy Research Inst., Tokai, Japan

    2000-06-01

    The Seminar on the Joint Research Project between JAERI and Universities was held in Tokai, August 20-21, 1999, to discuss future perspectives of the actinide researches for the nuclear fuel cycle. The papers related to the Joint Research Project on the Backend Chemistry were presented and discussed. The present report complies the papers contributed to the Seminar. (author)

  19. The second eddy current testing of zircaloy tube samples from the OECD Halden reactor project at Reactor Fuel Examination Facility, Tokai, JAERI

    Ohwada, Isao; Nishino, Yasuharu

    1986-07-01

    The Reactor Fuel Examination Facility in Tokai/JAERI (Japan Atomic Energy Research Institute) joined to the second round robin programme on eddy current test of the Halden/IFE. In the programme, two zircaloy tube samples with some artificial defects were provided for measurements. To clarify the locations in axial and azimuthal directions, types and dimensions of the provided artificial defects, measured signals from eddy current test were analysed in comparison with the known defects on the calibration tube. As a result, fourteen defects were determined from the measurements. Then, the location, the type and the relative dimension of them were also revealed. The results of those eddy current test are described in this paper. (author)

  20. Present status of reactor physics in the United States and Japan-I. 5. Development of the MVP Monte Carlo Code at JAERI

    Mori, T.; Okumura, K.; Nagaya, Y.

    2001-01-01

    The MVP general-purpose continuous-energy Monte Carlo code for neutron and photon transport calculations, together with its multigroup version GMVP, has been developed since the late 1980's at Japan Atomic Energy Research Institute (JAERI). These two codes were designed for vector supercomputers at the first stage, and then a parallel processing capability was added for several computers including workstation clusters. The first versions of the codes were released for domestic use in 1994, with cross-section libraries based on JENDL, ENDF/B, etc. Since then, many functions have been added for production use. Special features and main capabilities are as follows: 1. vectorization and parallelization; 2. combinatorial geometry with multiple-lattice capability and the statistical geometry model; 3. the probability table method for unresolved resonance; 4. realistic calculations of power reactors at arbitrary temperatures; 5. depletion calculations; 6. perturbation calculations for an eigenvalue (k eff ) problem; 7. useful tallies for improvement of the multigroup method such as effective macroscopic and/or microscopic cross sections, and so on. The MVP code is widely used in Japan, especially in the field of reactor physics analyses. Recently, the development work has concentrated on capabilities of applying the code to accelerator-driven subcritical reactors. For this purpose, we have been adding functions for the high-energy particle transport capability and simulations of the Feynman-α experiment (noise analysis). As a first step of extension of energy range and particles treated in MVP, the physics model of neutron reactions was modified to treat the (z, anything) reaction (MT = 5) in the ENDF-6 format. For a benchmark test of the modified MVP code, the TIARA shielding experiment on iron with quasi-mono-energetic p- 7 Li neutrons for E p 5 68 MeV was analyzed by using the LA- 150 cross-section library. In all the calculations, the measured spectrum of the source

  1. NMTC/JAERI-MCNP4Aコードシステムによる熱・冷中性子輸送計算

    伊賀 公紀; 高田 弘; 永尾 忠司

    1998-01-01

    水冷タンタルターゲット・減速材・反射体体系について、NMTC/JAERI-MCNP4Aコードシステムを用いた熱・冷中性子輸送計算を行い、核破砕中性子源の核設計への本コードシステムの適用性を調べた。計算では、減速材に軽水及び液体水素を用いた場合に放出される中性子のエネルギースペクトルについて、B4Cデカップラーの有無による強度変化、外部中性子線源位置による強度変化等の計算結果が実験結果に基づく半実験式に物理的に妥当な値のパラメータを用いて再現できることを確認した。しかし、放出中性子の時間スペクトルを精度良く評価するためには、MCNP4Aによる計算で反射体やデカップラー領域に適当なインポータンスを設定する工夫が必要であることがわかった。本計算によって、今後の核破砕値源の核設計にNMTC/JAERI-MCNP4Aコードシステムを適用できることを確認した。...

  2. Modeling of fuel performance and fission product release behavior during HTTR normal operation. A comparative study of the FZJ and JAERI modeling approach

    Verfondern, Karl; Sumita, Junya; Ueta, Shohei; Sawa, Kazuhiro

    2001-03-01

    For the prediction of fuel performance and fission product release behavior in the High Temperature Engineering Test Reactor, HTTR of the Japan Atomic Energy Research Institute(JAERI), during its normal operation, calculation tools were applied as have been used at the Research Center Juelich (FZJ) in safety analyses for pebble-bed HTGR designs. Calculations were made assuming the HTTR operation with a nominal operation time of 660 efpd including a 110 efpd period with elevated fuel temperatures. Fuel performance calculations by the PANAMA code with given fuel temperature distribution in the core have shown that the additional failure level of about 5x10 -6 is expected which is about twice as much as the as-fabricated through-coatings failure level. Under the extreme safety design conditions, the predicted particle failure fraction in the core increases to about 1x10 -3 in maximum. The diffusive release of metallic fission products from the fuel primarily occurs in the core layer with the maximum fuel temperature (layer 3) whereas there is hardly any contribution from layer 1 except for the recoil fraction. Silver most easily escapes the fuel; the predicted release fractions from the fuel compacts are 10% (expected) and 50% (safety design). The figures for strontium (expected: 1.5x10 -3 ), safety design: 3.1x10 -2 ) and cesium (5.6x10 -4 , 2.9x10 -2 ) reveal as well a significant fraction to originate already from intact particles. Comparison with the calculation based on JAERI's diffusion model for cesium shows a good agreement for the release behavior from the particles. The differences in the results can be explained mainly by the different diffusion coefficients applied. The release into the coolant can not modelled because of the influence of the gap between compact and graphite sleeve lowering the release by a factor of 3 to 10. For the prediction of performance and fission product release behavior of advanced ZrC TRISO particles, more experimental work is

  3. Evaluation on driving force of natural circulation in downcomer for passive residual heat removal system in JAERI passive safety reactor JPSR

    Kunii, Katsuhiko; Iwamura, Takamichi; Murao, Yoshio

    1997-01-01

    The driving-force of the natural circulation in the residual heat removal (RHR) system for the JPSR (JAERI Passive Safety Reactor) is given as a gravity force of the density difference between hotter coolant in core and upper plenum and cooler coolant in downcomer. The amount of density difference and time to achieve the enough density difference for the RHR system change directly dependent on the thermal fluid flow pattern in downcomer of annulus flow pass. The purposes of the present study are to investigate the possibilities of the followings by evaluating the three-dimensional thermal fluid flow in downcomer by numerical analysis using the STREAM code; 1) promotion of making the flow pattern uniform in downcomer by installing a baffle, 2) achievement of an enough driving-force of the natural circulation, 3) validity of one-point assumption, that is, complete mixing down-flow assumption for the three-dimensional thermal fluid flow in downcomer to evaluate the function of the passive RHR system. The following conclusions were obtained: (1) The effect of baffle on the thermal fluid flow and driving-force is little, (2) The driving-force required for natural circulation cooling can be obtained in wide range of inlet velocity even if the flow is multi-dimensional, (3) Both in initial transient stage and in steady-state, the one-point assumption can be applied to evaluate the driving-force of natural circulation in the passive RHR system. (author)

  4. Proceedings of the symposium on the joint research project between JAERI and Universities. Status and perspective of the advanced radiation technology project

    NONE

    2000-06-01

    This report describes the Proceedings of the Symposium on the Joint Research Project between JAERI and Universities -Status and Perspective of the Advanced Radiation Technology Project-, held at Tokyo on January 27, 1999. After a series of conferences which had been held at the second or third year to present the main activities of this unique collaborative project system, the symposium was particularly focused on critical reviewing of the project and on its future. The scientific papers presented were the recent achievements in the themes: 1) nuclear spectroscopy and nuclear materials science with an isotope separator on-line; 2) radiation shielding and nuclear data for use of accelerators; 3) materials analysis methods using ion beams; 4) microstructure in polymer materials irradiated with ions; 5) effects of transmutation products in fusion-reactor materials; 6) physiological study of plants using positron-emitting isotopes. The new theme titled 'Development and application of micro PIXE analysis in the atmospheric pressure' was proposed. Eight panelists discussed the future of the project. The 17 papers are indexed individually. (J.P.N.)

  5. User's manual of a supporting system for treatment planning in boron neutron capture therapy. JAERI computational dosimetry system

    Kumada, Hiroaki; Torii, Yoshiya [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2002-09-01

    A boron neutron capture therapy (BNCT) with epithermal neutron beam is expected to treat effectively for malignant tumor that is located deeply in the brain. It is indispensable to estimate preliminarily the irradiation dose in the brain of a patient in order to perform the epithermal neutron beam BNCT. Thus, the JAERI Computational Dosimetry System (JCDS), which can calculate the dose distributions in the brain, has been developed. JCDS is a software that creates a 3-dimensional head model of a patient by using CT and MRI images and that generates a input data file automatically for calculation neutron flux and gamma-ray dose distribution in the brain by the Monte Carlo code: MCNP, and that displays the dose distribution on the head model for dosimetry by using the MCNP calculation results. JCDS has any advantages as follows; By treating CT data and MRI data which are medical images, a detail three-dimensional model of patient's head is able to be made easily. The three-dimensional head image is editable to simulate the state of a head after its surgical processes such as skin flap opening and bone removal for the BNCT with craniotomy that are being performed in Japan. JCDS can provide information for the Patient Setting System to set the patient in an actual irradiation position swiftly and accurately. This report describes basic design and procedure of dosimetry, operation manual, data and library structure for JCDS (ver.1.0). (author)

  6. Accounting and Control of Tritium at the Tritium Process Laboratory (TPL) of JAERI - Results of 15-year Operation and Research Activity -

    Nishi, Masataka; Yamanishi, Toshihiko; Hayashi, Takumi; Yamada, Masayuki; Suzuki, Takumi

    Research and development work of fuel processing technology and tritium safe-handling technology necessary for fusion reactors has been performed at the Tritium Process Laboratory (TPL) of JAERI. TPL is the first facility in Japan permitted to handle tritium of more than 1g (about 0.36PBq), and its operation itself is also important for the development of fusion reactor facility in the viewpoint of tritium control. Various experiments have been carried out at TPL safely since 1988 controlling 22PBq of tritium as the maximum observing regulations. In addition to the regulatory accounting and control, detailed independent control in TPL was planned and was established throughits15-yearsafe-operation. For future fusion fuel facility where kilograms of tritium will be handled, method of tritium accounting has been researched and some new technologies have been developed at TPL. Results of TPL operation and of the research activity in it contributed the completion of the engineering design of ITER. Further research activity on tritium accounting and control is in progress in TPL for the future fusion reactors.

  7. Key achievements in elementary R&D on water-cooled solid breeder blanket for ITER test blanket module in JAERI

    Suzuki, S.; Enoeda, M.; Hatano, T.; Hirose, T.; Hayashi, K.; Tanigawa, H.; Ochiai, K.; Nishitani, T.; Tobita, K.; Akiba, M.

    2006-02-01

    This paper presents the significant progress made in the research and development (R&D) of key technologies on the water-cooled solid breeder blanket for the ITER test blanket modules in JAERI. Development of module fabrication technology, bonding technology of armours, measurement of thermo-mechanical properties of pebble beds, neutronics studies on a blanket module mockup and tritium release behaviour from a Li2TiO3 pebble bed under neutron-pulsed operation conditions are summarized. With the improvement of the heat treatment process for blanket module fabrication, a fine-grained microstructure of F82H can be obtained by homogenizing it at 1150 °C followed by normalizing it at 930 °C after the hot isostatic pressing process. Moreover, a promising bonding process for a tungsten armour and an F82H structural material was developed using a solid-state bonding method based on uniaxial hot compression without any artificial compliant layer. As a result of high heat flux tests of F82H first wall mockups, it has been confirmed that a fatigue lifetime correlation, which was developed for the ITER divertor, can be made applicable for the F82H first wall mockup. As for R&D on the breeder material, Li2TiO3, the effect of compression loads on effective thermal conductivity of pebble beds has been clarified for the Li2TiO3 pebble bed. The tritium breeding ratio of a simulated multi-layer blanket structure has successfully been measured using 14 MeV neutrons with an accuracy of 10%. The tritium release rate from the Li2TiO3 pebble has also been successfully measured with pulsed neutron irradiation, which simulates ITER operation.

  8. Key achievements in elementary R and D on water-cooled solid breeder blanket for ITER test blanket module in JAERI

    Suzuki, S.; Enoeda, M.; Hatano, T.; Hirose, T.; Hayashi, K.; Tanigawa, H.; Ochiai, K.; Nishitani, T.; Tobita, K.; Akiba, M.

    2006-01-01

    This paper presents the significant progress made in the research and development (R and D) of key technologies on the water-cooled solid breeder blanket for the ITER test blanket modules in JAERI. Development of module fabrication technology, bonding technology of armours, measurement of thermo-mechanical properties of pebble beds, neutronics studies on a blanket module mockup and tritium release behaviour from a Li 2 TiO 3 pebble bed under neutron-pulsed operation conditions are summarized. With the improvement of the heat treatment process for blanket module fabrication, a fine-grained microstructure of F82H can be obtained by homogenizing it at 1150 0 C followed by normalizing it at 930 0 C after the hot isostatic pressing process. Moreover, a promising bonding process for a tungsten armour and an F82H structural material was developed using a solid-state bonding method based on uniaxial hot compression without any artificial compliant layer. As a result of high heat flux tests of F82H first wall mockups, it has been confirmed that a fatigue lifetime correlation, which was developed for the ITER divertor, can be made applicable for the F82H first wall mockup. As for R and D on the breeder material, Li 2 TiO 3 , the effect of compression loads on effective thermal conductivity of pebble beds has been clarified for the Li 2 TiO 3 pebble bed. The tritium breeding ratio of a simulated multi-layer blanket structure has successfully been measured using 14 MeV neutrons with an accuracy of 10%. The tritium release rate from the Li 2 TiO 3 pebble has also been successfully measured with pulsed neutron irradiation, which simulates ITER operation

  9. Key achievements in elementary R and Ds on water-cooled solid breeder blanket for ITER Test Blanket Module in JAERI

    Suzuki, S.; Enoeda, M.; Hatano, T.; Hirose, T.; Tanigawa, H.; Tobita, K.; Akiba, M.; Hayashi, K.; Ochiai, K.; Nishitani, T.

    2005-01-01

    This paper presents significant progress in research and development (R and D) of key elementary technologies on the water-cooled solid breeder blanket for the ITER test blanket modules (TBMs) in JAERI. Development of module fabrication technology, bonding technology of armors, measurement of thermo-mechanical properties of pebble beds, neutronics studies on a blanket module mockup, and tritium release behavior from Li 2 TiO 3 pebble bed under neutron pulsed operation condition are summarized. By the improvement of heat treatment process for blanket module fabrication, a fine-grained microstructure of F82H, can be obtained by homogenizing it at 1150 deg C followed by normalizing at 930 deg C after the Hot Isostatic Pressing (HIP) process. Moreover, a promising bonding process for a tungsten armor and an F82H structural material was developed by using a solid state bonding method based on uniaxial hot compression without any artificial compliant layer. As a result of high heat flux tests of F82H first wall mockups, it was found that the thermal fatigue lifetime of F82H can be predicted by using Manson-Coffin's law. As for R and Ds on a breeder material, Li 2 TiO 3 , effective thermal conductivity of Li 2 TiO 3 pebble was measured under compressive force simulating the ITER TBM environment. The increase in the effective thermal conductivity of the pebble bed was about 2.5 % at the compressive strain of 0.9 % at 400 deg C. Neutronic performance of the blanket module mockup has been carried out by the 14 MeV neutron irradiation. It was confirmed that the measured tritium production rate agreed with the calculated values within about 10% difference. Also, tritium release from a Li 2 TiO 3 pebble bed was measured under pulsed neutron irradiation conditions simulating the ITER operation. (author)

  10. Proceedings of the symposium on the joint research program between JAERI and Universities. Current status and future perspectives of the chemistry research in the nuclear fuel cycle back end field

    1999-10-01

    The first Symposium on the Joint Research Project between JAERI and Universities was held in Tokyo, January 27, 1999, to present the main achievements of the project in these 5 years and to discuss future perspectives of the chemistry research relating to the nuclear fuel cycle. The areas covered by the Joint Research Project are (1) Nuclear Chemistry for TRU Recycling, (2) Solid State Chemistry on Nuclear Fuels and Wastes, (3) Solution Chemistry on Fuel Reprocessing and Waste Management, and (4) Fundamental Chemistry on Radioactive Waste Disposal. The 8 papers are indexed individually. (J.P.N.)

  11. Experiments using LHTL in JAERI

    Takamura, Saburo; Maeta, Hiroshi

    1984-01-01

    The liquid helium temperature loop (LHTL) in the Japan Atomic Energy Research Institute finished the irradiation experiment in March, 1983, accompanying the reconstruction of JRR-3 reactor, and at present, the removing work is in progress. This facility was built so as to be able to irradiate fast neutrons at 5 K, and in the state of having freezed the defects formed by irradiation, electric resistance, internal friction, X-ray scattering, length, mechanical strength and so on were able to be measured, and the state of recovery of irradiation defects accompanying temperature rise was able to be investigated. Recently, the irradiation damage of superconducting magnet materials used for nuclear fusion reactors has become a problem, and the importance of the irradiation experiment at extremely low temperature has increased. The LHTL engaged also in this problem. The transfer of irradiated specimens to the cryostat for measurement, the measurement of electric resistance, X-ray and the change of length, and compression test are reported. As for the properties of irradiation defects in metals, the examples of experiment carried out by the authors are briefly described. The effect of the irradiation at very low temperature on superconducting magnet materials is reported. (Kako, I.)

  12. Health physics in JAERI, 26

    1984-10-01

    In the annual report No.26 (fiscal 1983) are described the activities of health physics including radioactive waste management in Tokai Research Establishment, Takasaki Radiation Chemistry Research Establishment and Oarai Research Establishment. In all the three research establishments, radiation monitoring in nuclear facilities, individual monitoring, environmental monitoring and maintenance of measuring instruments were carried out as in the previous years. There were no occupational exposures exceeding the maximum permissible doses and no releases of radioactive gaseous and liquid wastes beyond the release limits specified according to the regulations. In the environment there were observed no abnormal radioactivities due to facilities. (J.P.N.)

  13. Neutron protein crystallography in JAERI

    results have clearly suggested that hydrogen atoms and water molecules around ... resolution (from 1.5 Å to 2.0 Å) structural analyses of several proteins. .... system like PDB is not sufficient to study hydrogen-related studies such as hydrogen.

  14. Health physics in JAERI, 22

    1980-10-01

    In the annual report No. 22 (fiscal 1979) are described the activities of health physics including radioactive waste management in Tokai Research Establishment, Takasaki Radiation Chemistry Research Establishment and Oarai Research Establishment. In all the three research establishments, radiation monitoring in nuclear facilities, individual monitoring, environmental monitoring and maintenance of measuring instruments were carried out as in previous years. There were no occupational exposures exceeding the maximum permissible doses and no release of radioactive gaseous and liquid wastes beyond the release limits specified according to regulations. In the environment there were observed no abnormal radioactivities due to facilities. In Tokai and Oarai Research Establishments radioactive waste management including decontamination works was also carried out and radioactive solid wastes were stored in the same way as in previous years. Construction of the Packaged Waste Storage Facility was completed, and of the Facility of Radiation Standards and the Medium-Level Waste Treatment Facility progressed on schedule in Tokai Research Establishment. In Oarai Research Establishment, construction was completed on the latter project of radioactive waste treatment facilities, starting in 1974. Technical development and research were made as in previous years for improving techniques and methods in monitoring of individuals, facilities and environment and also in waste management and decontamination. (author)

  15. Annual report on major results and progress of Naka Fusion Research Establishment of JAERI from April 1 to September 30, 2005 and Fusion Research and Development Directorate of JAEA from October 1, 2005 to March 31, 2006

    Yoshida, Hidetoshi; Oasa, Kazumi; Hayashi, Takao; Nakamura, Hiroo; Ogawa, Hiroaki

    2006-09-01

    This annual report provides an overview of major results and progress on research and development (R and D) activities at Naka Fusion Research Establishment of Japan Atomic Energy Research Institute (JAERI) during the period from April 1 to September 30, 2005 and at Fusion Research and Development Directorate of Japan Atomic Energy Agency (JAEA) from October 1, 2005 to March 31, 2006, including those performed in collaboration with other research establishments of JAERI, research institutes, and universities. In JT-60, ferritic steel tiles (FSTs) were installed inside the vacuum vessel of JT-60U to reduce the toroidal field ripple. After the installation of FSTs, a high normalized beta plasma at β N ∼2.3 was sustained for 28.6s with ELMy H-mode confinement as required for an ITER hybrid operation scenario. National Centralized Tokamak was placed as the ITER satellite tokamak in collaboration with the EU fusion community, and the facility design was modified strongly in support of ITER. In theoretical and analytical researches, studies on H-mode confinement, ITB in reversed shear plasmas, aspect ratio effects on external MHD modes and magnetic island evolution in a rotating plasma were progressed. Progress was also made in the NEXT project in which the behaviors of collisionless MHD modes and the dynamics of zonal flows were simulated. In fusion reactor technologies, R and Ds for ITER and fusion DEMO plants have been carried out. For ITER, a steady state operation of the 170GHz gyrotron up to 1000 s with 0.2 MW was demonstrated. Also current density of the neutral beam injector has been extended to 134A/m 2 at 0.75MeV. In the ITER Test Blanket Module (TBM), designs of Water and Helium Cooled Solid Breeder TBMs and R and Ds of tritium breeder/multiplier materials were progressed. Tritium processing technology for breeding blankets was also progressed. For the DEMO reactors, high temperature superconductor such as Bi2212 has been examined. In plasma facing

  16. Test of the scroll pump in the JAERI Fuel Cleanup System in the Tritium Systems Test Assembly. JFCU scroll pump test and result, JFCU stand alone tritium test 2

    Hayashi, Takumi; Konishi, Satoshi [Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment; Ohira, Shigeru [and others

    1993-03-01

    In the JAERI Fuel Cleanup System (JFCU), major subsystem of the TSTA simulated fusion fuel loop, a Normetex Scroll pump is used to pump out hydrogen isotope gases from the palladium diffuser. The characteristics of the pump was measured with hydrogen isotopes and helium, in a closed loop. Compression ratio and ultimate pressure were strongly affected by the delivery pressure and the species of the gas. Particularly with H{sub 2} and D{sub 2}, additional metal bellows pump was proved to be needed to satisfy the process requirement. For hydrogen isotopes, pumping characteristics improves with the mass of the gas and similar pumping capability was obtained with pure T{sub 2} and helium. (author).

  17. Quantification of design margins and safety factors based on the prediction uncertainty in tritium production rate from fusion integral experiments of the USDOE/JAERI collaborative program on fusion blanket neutronics

    Youssef, M.Z.; Konno, C.; Maekawa, F.; Ikeda, Y.; Kosako, K.; Nakagawa, M.; Mori, T.; Maekawa, H.

    1995-01-01

    Several fusion integral experiments were performed within a collaboration between the USA and Japan on fusion breeder neutronics aimed at verifying the prediction accuracy of key neutronics parameters in a fusion reactor blanket based on current neutron transport codes and basic nuclear databases. The focus has been on the tritium production rate (TRP) as an important design parameter to resolve the issue of tritium self-sufficiency in a fusion reactor. In this paper, the calculational and experimental uncertainties (errors) in local TPR in each experiment performed i were interpolated and propagated to estimate the prediction uncertainty u i in the line-integrated TPR and its standard deviation σ i . The measured data are based on Li-glass and NE213 detectors. From the quantities u i and σ i , normalized density functions (NDFs) were constructed, considering all the experiments and their associated analyses performed independently by the UCLA and JAERI. Several statistical parameters were derived, including the mean prediction uncertainties u and the possible spread ±σ u around them. Design margins and safety factors were derived from these NDFs. Distinction was made between the results obtained by UCLA and JAERI and between calculational results based on the discrete ordinates and Monte Carlo methods. The prediction uncertainties, their standard deviations and the design margins and safety factors were derived for the line-integrated TPR from Li-6 T 6 , and Li-7 T 7 . These parameters were used to estimate the corresponding uncertainties and safety factor for the line-integrated TPR from natural lithium T n . (orig.)

  18. US/Japan collaborative program on fusion reactor materials: Summary of the tenth DOE/JAERI Annex I technical progress meeting on neutron irradiation effects in first wall and blanket structural materials

    Rowcliffe, A.F.

    1989-01-01

    This meeting was held at Oak Ridge National Laboratory on March 17, 1989, to review the technical progress on the collaborative DOE/JAERI program on fusion reactor materials. The purpose of the program is to determine the effects of neutron irradiation on the mechanical behavior and dimensional stability of US and Japanese austenitic stainless steels. Phase I of the program focused on the effects of high concentrations of helium on the tensile, fatigue, and swelling properties of both US and Japanese alloys. In Phase II of the program, spectral and isotropic tailoring techniques are fully utilized to reproduce the helium:dpa ratio typical of the fusion environment. The Phase II program hinges on a restart of the High Flux Isotope Reactor by mid-1989. Eight target position capsules and two RB* position capsules have been assembled. The target capsule experiments will address issues relating to the performance of austenitic steels at high damage levels including an assessment of the performance of a variety of weld materials. The RB* capsules will provide a unique and important set of data on the behavior of austenitic steels irradiated under conditions which reproduce the damage rate, dose, temperature, and helium generation rate expected in the first wall and blanket structure of the International Thermonuclear Experimental Reactor

  19. JAERI femtosecond pulsed and tens-kilowatts average-powered free-electron lasers and their applications of large-scaled non-thermal manufacturing in nuclear energy industry

    Minehara, Eisuke J.

    2004-01-01

    We first reported the novel method that femto-second (fs) lasers of the low average power Ti: Sapphire one, the JAERI high average power free-electron laser, excimer laser, fiber laser and so on could peel off and remove both stress corrosion cracking (SCC) origins of the cold-worked (CW) and very crack-susceptible material, and residual tensile stress in the hardened surface of low-carbon stainless steel cubic samples for nuclear reactor internals as a proof of principle experiment except for the last and third origin of corrosive environment. Because it has been successfully demonstrated that the fs lasers could clearly remove the two SCC origins, we could resultantly prevent the cold-worked SCC in many field near future. The SCC is a well known phenomenon in modern material sciences, technologies, and industries, and defined as an insidious failure mechanism that is caused by the corrosive environment, and the crack-susceptible material and the surface residual tensile stress simultaneously. There are a large number of famous SCC examples for damaging stainless steels, aluminum alloys, brass and other alloy metals in many different cases. In many boiling light-water reactor (BWR) nuclear power plants and a few pressurized light water reactor (PWR) ones in Japan and the world up to now, a large number of the deep and wide cracks have been recently found in the reactor-grade low-carbon stainless steel components of core shroud, control-blade handle, re-circulating pipes, sheath and other internals in the reactor vessel under very low or no applied stresses. These cracks have been thought to be initiated from the crack-susceptible like very small-sized cracks, pinholes, concentrated dislocation defects and so on in the hardened surface, which were originated from cold-work machining processes in reactor manufacturing factories, and to be insidiously penetrated widely into the deep inside under the residual tensile stress and corrosive environment, and under no

  20. JAERI Nuclear Engineering School and technology transfer

    Nishimura, Kazuaki; Kawaguchi, Chiyoji

    1978-01-01

    A method is introduced to evaluate the degree of nuclear technology transfer; that is, the output powers of Japanese nuclear reactors constructed in these 20 years are chronologically plotted in a semi-log figure. All reactors plotted are classified into imported and domestic ones according to a value of domestication factor. A space between two historical trajectories of reactor construction may be interpreted as one of the measures indicating the degree of nuclear technology transfer. In connection with this method, historical change of educational and training courses in Nuclear Engineering School of Japan Atomic Energy Research Institute is reviewed in this report. (author)

  1. Health physics in JAERI No. 32

    1990-12-01

    In the annual report No. 32 (fiscal 1989) are described the activities of health physics including radioactive waste management in Tokai Research Establishment, Takasaki Radiation Chemistry Research Establishment, Oarai Research Establishment, Mutsu Establishment and Nuclear Ship Mutsu. There were no occupational exposure exceeding the dose equivalent limit and no release of radioactive gaseous and liquid wastes beyond the release limits specified according to the regulations. In the environment there were observed no abnormal radioactivity due to the facilities. The following works were made in the researches of radiation dosimetry, body radioactivity, airborne radioactivity and waste treatment. For radiation dosimetry: preparation of β-ray plain source for dose estimation on skin contamination, 4π directional dependence of external effective dose equivalent (III), analysis of career dose to workers, distribution of annual collective dose of workers among nuclear power reactors. For body radioactivity: theoretical study for correction of plutonium chest counting data (II), radiosensitivity of chromosomes of rabbit lymphocytes (V), and dicentric and indirect action. For airborne radioactivity: tritium oxide permeability of membranes used for protective appliances (V), effect of hydrogen isotope composition on conversion reaction of tritium gas to tritiated water, development of models of tritium dispersion in the environment near nuclear facilities, and effectiveness of sheltering in a wooden building against radioactive airborne contaminations. For waste treatment: effects of residual radioactivity on scientific and industrial instruments (II), and safety verification test of rational disposal of very low-level radioactive solid wastes. (J.P.N.)

  2. Health physics in JAERI, No.27

    1985-10-01

    In the annual report No. 27 (fiscal 1984) are described the activities of health physics including radioactive waste management in Tokai Research Establishment, Takasaki Radiation Chemistry Research Establishment and Oarai Research Establishment. In all the three research establishments, radiation monitoring in nuclear facilities, individual monitoring, environmental monitoring and maintenance of measuring instruments were carried out as in the previous years. There were no occupational exposure exceeding the maximum permissible dose and no release of radioactive gaseous and liquid waste beyond the release limit specified according to the regulations. In the environment there were observed no abnormal radioactivity due to facilities. In Tokai and Oarai Research Establishment, radioactive waste management including decontamination was carried out and radioactive solid waste was stored in the same way as in the previous years. (author)

  3. Health physics in JAERI No. 33

    1991-11-01

    In the annual report No. 33 (fiscal 1990) are described the activities of health physics including radioactive waste management in Tokai Research Establishment, Takasaki Radiation Chemistry Research Establishment, Oarai Research Establishment, Mutsu Establishment and Nuclear Ship Mutsu. In all the establishments, radiation monitoring in nuclear facilities, individual monitoring, environmental monitoring and maintenance of monitoring instruments were carried out as in the previous years. There were no occupational exposure exceeding the dose equivalent limit and no release of radioactive gaseous and liquid wastes beyond the release limits specified according to the regulations. In the environment there were observed no abnormal radioactivity due to the facilities. In Tokai and Oarai Research Establishment and Mutsu Establishment, radioactive waste management including decontamination was carried out and radioactive solid wastes were stored in the same way as in the previous years. Technology developments were made as in the previous years for improving the techniques and methods in monitoring of individuals, facilities and environment, radiation measurement instrumentation and also in waste management and decontamination. The following works were made in the researches of radiation dosimetry, body radioactivity, airborne radioactivity and waste disposal. (J.P.N.)

  4. Repeating pneumatic pellet injector in JAERI

    Kasai, Satoshi; Hasegawa, Kouichi; Suzuki, Sadaaki; Miura, Yukitoshi; Oda, Yasushi; Onozuka, Masanori; Tsujimura, Seiichi.

    1992-09-01

    A repeating pneumatic pellet injector has been developed and constructed at Japan Atomic Energy Research Institute. This injector can provide repetitive pellet injection to fuel tokamak plasmas for an extended period of time, aiming at the improvement of plasma performance. The pellets with nearly identical speed and mass can be repeatedly injected with a repetition rate of 2-3.3 Hz and a speed of up to 1.7 km/s by controlling the temperature of the cryogenic system, the piston speed and the pressure of the propellant gas. (author)

  5. Status of ECR ion sources at JAERI

    Yokota, W; Nara, T; Ishi, Y; Arakawa, K; Ohkoshi, K

    1999-01-01

    At the Takasaki site of Japan Atomic Energy Research Institute, four ECR ion sources were purchased or developed so far. This paper will report their performance, modification and status. The outlines for each source are as follows; 1. OCTOPUS purchased from IBA s.a. has been in use with a cyclotron since 1990. The gas feed system was modified to change gas species within 10 minutes to avoid impurity ions in the cocktail beam acceleration technique of the cyclotron. 2. ECR-18 with 18-GHz microwave has a solenoid coil between a pair of mirror coils to change mirror ratio in a wide range. A bump between mirror peaks in the original axial field distribution was removed by halving the solenoid length. The performance in generating high charge state ions was significantly improved as a result. 3. HYPERNANOGAN was purchased from PANTECHNIK s.a. and installed in the cyclotron system this year. Test operation was successfully made with generation of Ar, Pb and Ta ions. 4. MINI ECR is a full permanent magnet source wi...

  6. Health physics in JAERI. no.30

    1988-11-01

    There were no occupational exposure exceeding the maximum permissible dose and no release of radioactive gaseous and liquid waste beyond the release limit specified according to the regulations. In the environment there were observed no abnormal radioactivity due to the facilities. In Tokai and Oarai Research Establishment, radioactive waste management including decontamination was carried out and radioactive solid waste was stored in the same way as in the previous years. Technology developments were made as in the previous years for improving the technique and methods in monitoring of individuals, facilities and environment, radiation measurement instrumentation and also in waste management and decontamination. The following works were made in the researches of radiation dosimetry, body radioactivity, airborne radioactivity and waste disposal. For radiation dosimetry: 4π directional dependency of external effective dose equivalent, dependence of neutron energy spectrum on composition and form of phantom, U.S. occupational exposure analysis, and a model of dose and age distribution of workers. For body radioactivity: development of tissue equivalent liquid material for chest phantom, radiosensitivity of chromosomes of rabbit lymphocytes, and quick measurement of thyroid exposure to inhaled radioiodine. For airborne radioactivity and waste disposal: field studies of HT, tritium oxide permeability of membrance in protective appliances, tritium gas conversion to tritiated water, and safety demonstration tests of rational disposal of very low-level radioactive solid waste. (author)

  7. Repeating pneumatic pellet injector in JAERI

    Kasai, Satoshi; Hasegawa, Kouichi; Suzuki, Sadaaki; Miura, Yukitoshi (Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment); Oda, Yasushi; Onozuka, Masanori; Tsujimura, Seiichi.

    1992-09-01

    A repeating pneumatic pellet injector has been developed and constructed at Japan Atomic Energy Research Institute. This injector can provide repetitive pellet injection to fuel tokamak plasmas for an extended period of time, aiming at the improvement of plasma performance. The pellets with nearly identical speed and mass can be repeatedly injected with a repetition rate of 2-3.3 Hz and a speed of up to 1.7 km/s by controlling the temperature of the cryogenic system, the piston speed and the pressure of the propellant gas. (author).

  8. Current status of JAERI-Mutsu Tandetron

    Kitamura, Toshikatsu; Aramaki, Takafumi; Mizutani, Yoshihiko; Togawa, Orihiko

    2001-01-01

    Tandetron Accelerator Mass Spectrometer was installed at Mutsu research establishment, Japan Atomic Energy Institute, in 1997 for the purpose of the study of the radionuclide transfer in marine environment. The carbon line started full operation in December 1999, whereas the iodine line was tested for its precision using heavy ion detectors in 1999. The operation experience since 1999 and the state-of-art of the facility, and results from the precision tests of the iodine line are described. The tests were performed in order to ensure the alignment of the iodine line. The C-12/C-14 measurement of IAEA standard sample C-1, seawater samples from the North Pacific and the Sea of Okhotsk was performed as well. (A. Yamamoto)

  9. Health physics in JAERI, No. 23

    1981-10-01

    In the annual report No.23 (fiscal 1980) are described the activities of health physics including radioactive waste management in Tokai Research Establishment, Takasaki Radiation Chemistry Research Establishment and Oarai Research Establishment. In all the three research establishments, radiation monitoring in nuclear facilities, individual monitoring, environmental monitoring and maintenance of measuring instruments were carried out as in previous years. There were no occupational exposures exceeding the maximum permissible doses and no releases of radioactive gaseous and liquid wastes beyond the release limits specified according to the regulations. In the environment there were observed no abnormal radioactivities due to facilities. In Tokai and Oarai Research Establishments radioactive waste management including decontamination works was also carried out and radioactive solid wastes were stored in the same way as in previous years, except that in Tokai Research Establishment, the Packaged Waste Storage Facility started storing packaged wastes and in Oarai Research Establishment, the Radioactive Waste Treatment Facility (the Latter Project) started routine operation. Construction of the Facility of Radiation Standards and the Medium-Level Waste Treatment Facility was completed in Tokai Research Establishment. Technology development and research were made as in previous years for improving the techniques and methods in monitoring of individuals, facilities and environment and also in waste management and decontamination. (J.P.N.)

  10. Health physics in JAERI. No.29

    1987-11-01

    There were no occupational exposure exceeding the maximum permissible dose and no release of radioactive gaseous and liquid waste beyond the release limit specified according to the regulations. In the environment there were observed no abnormal radioactivity except fallout due to the Chernobyl accident. Technology developments were made as in the previous years for improving the techniques and methods in monitoring of individuals, facilities and environment, radiation measurement instrumentation and also in waste management and decontamination. The following works were made in the researches of radiation dosimetry, body radioactivity, airborne radioactivity and estimation of radiation dose due to low level waste disposal. For radiation dosimetry: evaluation of β-ray dose equivalent rates, activity measurement of large area γ-ray plane source, assessment of U.S. occupational exposure, application of HLN distribution to assessing average internal exposure of workers, and property of statistics of HLN distribution. For body radioactivity: realistic chest phantom with artificial rib cage for an assessment of Pu in lung, and radiosensitivity of chromosomes of rabbit lymphocytes. For airborne radioactivity and waste disposal: sheltering effect of houses for radioactive effluent, physicochemical species of airborne iodine-131 in Japan from Chernobyl, deposition velocities of iodine-131 due to the Chernobyl accident, tritium oxide permeability of membranes in protective appliances, calculation of doses from the pathway of groundwater migration for shallow land disposal of radioactive waste, and safety demonstration tests of rational disposal of very low-level radioactive solid waste. (author)

  11. Present status of radioisotope production in JAERI

    Yamabayashi, Hisamichi

    1994-01-01

    Since 1962, the technology for producing a wide variety of processed radioisotopes and sealed radiation sources has been developed by using the reactors, JRR-1, JRR-2, JRR-3, JRR-4 and JMTR, and the products have been offered to domestic users. At present, 31 products of 29 nuclides are on the list of processed radioisotopes. Some of those isotopes such as P-32, S-35, Cr-51 and short lived nuclides are produced for regular distribution, but the rest are produced upon request. The radiation sources of Co-60 needles for industrial use, Ir-192 pellets for the nondestructive inspection of pipelines, Gd-153 pellets for the diagnosis of born mineral and seven kinds of brachy therapy Ir-192 and Au-198 grains are produced and distributed regularly. The organic compounds labeled with H-3 and C-14 are widely used. In fiscal year 1992, 34 batches and total amount 12 TBq of processed radioisotopes and 100 batches, 1.2 PBq of radiation sources were produced as scheduled. The development of the techniques for producing the sources emitting high energy β ray used for the diagnosis and treatment of cancer is in progress. The method of producing new isotopes is developed. (K.I.)

  12. Progress of JAERI neutron science project

    Oyama, Yukio

    1999-01-01

    Neutron Science Project was started at Japan Atomic Energy Research Institute since 1996 for promoting futuristic basic science and nuclear technology utilizing neutrons. For this purpose, research and developments of intense proton accelerator and spallation neutron target were initiated. The present paper describes the current status of such research and developments. (author)

  13. Application of JAERI research reactors to education

    Ogawa, Shigeru; Morozumi, Minoru

    1987-01-01

    At the dawning of the atomic age in Japan, training on reactor operation and reactor engineering experiments has been started in 1958 using JRR-1 (a 50 kW water boiler type reactor with liquid fuel), which was the first research reactor in Japan. The role of the training has been transferred to JRR-4 (a 3500 kW swimming pool type reactor with ETR type fuel) since 1969 due to the decommission of JRR-1. The training courses which have been held are: JRR-1 Short-Term Course for Operation (1958 ∼ 1963) General Course (1961 ∼ ) Reactor Engineering Course (1976 ∼ ) Training Course in Nuclear Technology (International course)(1986 ∼ ). And individual training concerning research reactors for the participants of scientist exchange program sponsored by Science and Technology Agency and of bilateral agreement have been initiated in 1985. The graduates of these courses work as staff members in various fields in nuclear industry. (author)

  14. Experimental study of synthesis of heavy nuclei at JAERI

    Nishio, K.; Ikezoe, H.; Mitsuoka, S.; Satou, K.

    2001-01-01

    Evaporation residue (ER) cross sections for 82 Se+ nat Ce and 76 Ge+ 150 Nd were measured in the vicinity of the Coulomb barrier, and the fusion probability was obtained with the aid of calculated survival probability. The former system represents fusion of two spherical nuclei, the latter fusion involving the pro-lately deformed target 150 Nd. The collision of 76 Ge with the side of 150 Nd is more compact in configuration at touching. The system 82 Se+ nat Ce showed fusion hindrance in form of extra-extra-push energy of 27 ± 5 MeV, whereas the system 76 Ge+ 150 Nd does not show fusion hindrance at and above the Coulomb barrier energy, suggesting that the reaction starting from the compact touching point results in a higher fusion probability. (author)

  15. Health physics and safety in JAERI, No.17

    1975-09-01

    In the annual report No.17 (fiscal 1974), the activities of health physics and safety in the Tokyo Office, Tokai Research Establishment, Takasaki Radiation Chemistry Research Establishment, and Oarai Research Establishment are described. (auth.)

  16. Neutron scattering research at JAERI reactors - past, present and future -

    Funahashi, Satoru; Morii, Yukio; Minakawa, Nobuaki

    1992-01-01

    It was in 1961 that the first neutron scattering experiment was performed in Japan at JRR-2. The start of JRR-3 in 1964 accelerated the neutron scattering activities in Japan. The research in this field in Japan grew up by using these two research reactors. Among them JRR-2 has played an important role because its neutron flux was about seven times higher than that of the old JRR-3. The completion of the new JRR-3M in 1990 made an epoch to the neutron scattering activities in Japan. The long-waited JRR-3M came up to the expectations of the scientists of Japan. It is a realization of the ideal reactor with tangential beam holes, cold source and neutron guides in a large guide hall. The flux at the neutron scattering instruments is about five times higher than that of JRR-2. Utilization of JRR-3M has just started. Twelve neutron scattering machines are running there. The number will increase up to close twenty in a couple of years. (author)

  17. The JAERI code system for evaluation of BWR ECCS performance

    Kohsaka, Atsuo; Akimoto, Masayuki; Asahi, Yoshiro; Abe, Kiyoharu; Muramatsu, Ken; Araya, Fumimasa; Sato, Kazuo

    1982-12-01

    Development of respective computer code system of BWR and PWR for evaluation of ECCS has been conducted since 1973 considering the differences of the reactor cooling system, core structure and ECCS. The first version of the BWR code system, of which developmental work started earlier than that of the PWR, has been completed. The BWR code system is designed to provide computational tools to analyze all phases of LOCAs and to evaluate the performance of the ECCS including an ''Evaluation Model (EM)'' feature in compliance with the requirements of the current Japanese Evaluation Guideline of ECCS. The BWR code system could be used for licensing purpose, i.e. for ECCS performance evaluation or audit calculations to cross-examine the methods and results of applicants or vendors. The BWR code system presented in this report comprises several computer codes, each of which analyzes a particular phase of a LOCA or a system blowdown depending on a range of LOCAs, i.e. large and small breaks in a variety of locations in the reactor system. The system includes ALARM-B1, HYDY-B1 and THYDE-B1 for analysis of the system blowdown for various break sizes, THYDE-B-REFLOOD for analysis of the reflood phase and SCORCH-B2 for the calculation of the fuel assembl hot plane temperature. When the multiple codes are used to analyze a broad range of LOCA as stated above, it is very important to evaluate the adequacy and consistency between the codes used to cover an entire break spectrum. The system consistency together with the system performance are discussed for a large commercial BWR. (author)

  18. Design study of fusion Demo plant at JAERI

    Tobita, K.; Nishio, S.; Enoeda, M.

    2006-01-01

    Three options of fusion Demo plant are proposed characterized by functions of the center solenoid (Cs). The prime option uses a downsized CS, which does not provide sufficient V-s for plasma current ramp-up but supplies enough coil current for plasma shaping. This option produces a fusion output of 3 GW with a major radius of 5.5 m, aspect ratio of 2.6, normalized beta of 4.3 and maximum field of 16.4 T. The estimated reactor weight is lighter than that of other conventional tokamak reactors, suggesting an economic advantage. The plant uses rather conservative technologies such as Nb 3 Al superconductor, water-cooled solid breeder blanket, low activation ferritic steel as the structural material and tungsten monoblock divertor plate. The design philosophy and key issues related to the constituent technologies of the plant are described in the present paper

  19. Study on premixing phase of steam explosion at JAERI

    Yamano, Norihiro; Moriyama, Kiyofumi; Maruyama, Yu; Park, H.; Yang, Y.; Sugimoto, Jun [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1998-01-01

    Melt jet breakup (MJB) and fragmentation has been studied in the frame of ALPHA program. In the first two experiments of MJB series, jet of molten lead-bismuth eutectic alloy was released into a deep pool of saturated water. Steam generation rate was measured and correlated with the jet behavior observed by a high-speed camera. The jet breakup length and debris size distribution were also evaluated. In parallel with the experimental study, JASMINE code has been developed for the simulation of steam explosion. The melt jet breakup model and the particle breakup model in the code were tested by analyzing FARO-L14 and ALPHA MJB experiments. (author)

  20. Research and development of radiation utilization in 1986 at JAERI

    1986-01-01

    In the peaceful utilization of atomic energy, in addition to the method of utilizing the energy obtained by nuclear fission and nuclear fusion as electric power or heat source, there is the field of utilizing radiation, in which the effect that radiation exerts on substances and the properties of radiation are used for measurement, analysis and others. The fields of utilizing radiation are diverse such as medicine, technology and agriculture, and those directly related to the health and daily life of people are many. Japan Atomic Energy Research Institute has positively advanced the research and development on radiation utilization, which are related to the utilization of irradiation and the production and use of radioisotopes. The former is carried out in Takasaki Radiation Chemistry Research Establishment, and the latter in the Isotope Division, Tokai Research Establishment. Also, the research and development on the radiation-withstanding properties of organic materials and the production techniques for tritium are advanced, and it is expected to begin the highly advanced scientific and technological research using ion beam. The research and development of polymer materials, the techniques of using irradiation, the production and utilization of radioisotopes and others are reported. (Kako, I.)

  1. Studies on fast wave current drive in the JAERI tokamaks

    Kimura, H.; Yamamoto, T.; Fujii, T.; Kawashima, H.; Tamai, H.; Saigusa, M.; Imai, T.; Hamamatsu, K.; Fukuyama, A.

    1991-01-01

    Fast wave electron heating experiment (FWEH) on JFT-2M and JT-60 and analysis of fast wave current drive (FWCD) ability on JT-60U are presented. In the JFT-2M, absorption of fast waves have been investigated by using a phased four-loop antenna array. The absorption of the fast waves has been studied for various plasma parameters by using combination of other additional heating methods such as electron cyclotron heating (ECH) and ion cyclotron heating. It is shown that the absorption efficiency estimated from various methods well correlates with one calculated theoretically in single pass damping. Interaction of the fast waves with fast electrons in combination with ECH has been examined through the measurement of non-thermal electron cyclotron emission (ECE). The observed ECE during FWEH is well explained by the theoretical model, which indicates generation of the appreciable energetic fast electrons by the fast waves. New four-loop array antennas have been employed to improve the absorption of unidirectionally-propagating waves. Characteristics of antenna loading resistance can be reproduced by a coupling calculation code. In JT-60, FWEH experiment in combination with lower hybrid current drive was performed. Power absorption efficiency of fast wave is substantially improved in combination with LHCD of relatively low power for both phasing modes. Bulk electron heating is observed with high-k // mode and coupling with fast electron is confirmed in hard X-ray emission with low-k // mode. The results are consistent with theoretical prediction based on 1.D full wave code. Synergetic effects between FWEH and LHCD are found. Coupling calculation indicates that eight-loop antenna is favourable for keeping high directivity in the required N // -range. Current drive efficiency is calculated with 1-D full wave code including trapped particle effects and higher harmonic ion cyclotron damping

  2. The 33 years of research reactors in JAERI

    1990-11-01

    The development and utilization of atomic energy in Japan began with the installation of JRR-1 reactor which attained the criticality in August, 1957, thus the third fire was lighted for the first time in Japan. JRR-2 was constructed as a full scale versatile research reactor, which attained the criticality in October, 1960, and since 1962, it has accomplished the role of the reactor for joint utilization. JRR-3 is the first reactor made in Japan by concentrating Japanese technologies in it, to develop and improve Japanese atomic energy technology. It attained the criticality in September, 1962, and has been used as a versatile research reactor. In 1960, Research Reactor Management Department was founded. JRR-4 was constructed as the research reactor for shielding for developing a nuclear-powered ship, which attained the criticality in January, 1965. The first hot laboratory in Japan for carrying out the post-irradiation test on the fuel and materials irradiated in these research reactors was installed in 1961. The JRR-1 was stopped in September, 1968, and is used as the commemorative exhibition hall. The JRR-3 was reconstructed, and attained the criticality in March, 1990, using 20 % enriched uranium fuel. The course of the research reactors for 33 years is reported. (K.I.)

  3. Health physics and safety in JAERI, No. 18

    1976-10-01

    In the annual report No.18 (fiscal 1975), the activities of health physics and safety in the Tokyo Office, Tokai Research Establishment, Takasaki Radiation Chemistry Research Establishment, and Oarai Research Establishment are described. (auth.)

  4. Second preliminary design of JAERI experimental fusion reactor (JXFR)

    Sako, Kiyoshi; Tone, Tatsuzo; Seki, Yasushi; Iida, Hiromasa; Yamato, Harumi

    1979-06-01

    Second preliminary design of a tokamak experimental fusion reactor to be built in the near future has been performed. This design covers overall reactor system including plasma characteristics, reactor structure, blanket neutronics radiation shielding, superconducting magnets, neutral beam injector, electric power supply system, fuel recirculating system, reactor cooling and tritium recovery systems and maintenance scheme. Safety analyses of the reactor system have been also performed. This paper gives a brief description of the design as of January, 1979. The feasibility study of raising the power density has been also studied and is shown as appendix. (author)

  5. Water chemistry management of research reactor in JAERI

    Yoshijima, Tetsuo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1998-10-01

    The JRR-3M cooling system consists of four systems, namely; (1) primary cooling system, (2) heavy water cooling system, (3) helium system and (4) secondary cooling system. The heavy water is used for reflector and pressurized with helium gas. Water chemistry management of the JRR-3M cooling systems is one of the important subject for the safety operation. The main objects are to prevent the corrosion of cooling system and fuel elements, to suppress the plant radiation build-up and to minimize the generation of radioactive waste. All measured values were within the limits of specifications and JRR-3M reactor was operated with safety in 1996. Spent fuels of JRR-3M reactor are stored in the spent fuel pool. This pool water has been analyzed to prevent corrosion of aluminum cladding of spent fuels. Water chemistry of spent fuel pool water is applied to the prevention of corrosion of aluminum alloys including fuel cladding. The JRR-2 reactor was eternally stopped in December 1996 and is now under decommissioning. The JRR-2 reactor is composed of heavy water tank, fuel guide tube and horizontal experimental hole. These are constructed of aluminum alloy and biological shield and upper shield are constructed of concrete. Three types of corrosion of aluminum alloy were observed in the JRR-2. The Alkaline corrosion of aluminum tube occurred in 1972 because of the mechanical damage of the aluminum fuel guide tube which is used for fuel handling. Modification of the reactor top shield was started in 1974 and completed in 1975. (author)

  6. Preriminary operation results of JAERI ECR ion source OCTOPUS

    Yokota, W.; Arakawa, K.; Tachikawa, T.; Satoh, T.; Dupont, C.; Jongen, Y.

    1990-01-01

    An ECR ion source, new OCTOPUS, was built for and AVF cyclotron of the Japan Atomic Energy Research Institute, Takasaki. The design of this source is almost identical to the first built OCTOPUS, except for the RF frequency for the 2nd stage. The first operation of the new OCTOPUS was performed. High intensity of X-ray leakage was measured outside the lead shield wall of the source. (author)

  7. Annual report of the Division of Thermonuclear Fusion Research, JAERI

    1977-02-01

    The JFT-2 operating regime was extended to higher toroidal field of 18 kG. Plasma confinements were studied on impurities, instabilities, plasma-wall interaction. Properties of a plasma with a separatrix magnetic surface and plasma behaviour in the scrape-off layer were studied in JFT-2a. In the diagnostics, a grazing-incidence vacuum ultra-violet spectrometer for studies on impurities was completed and put into operation. Several minor improvement and remodelling on the JFT-2 and JFT-2a tokamaks were carried out for the convenience of operation. In the plasma heating, constructions of the JFT-2 neutral injection system and the injector test stand ITS-2 for development of the higher energy ion source were started. The design of 200 kW RF power source for the plasma heating in JFT-2 was also made. Research in surface effects in fusion devices started at April 1, 1975. Experimental apparatus was designed and constructed in this fiscal year. A group for superconducting magnet development for fusion device was set up in January, 1976. Theoretical works continued in the analyses on transport processes, plasma heating, and mhd stabilities with an increasing effort on computational studies. A preliminary design of the 100 MW sub(t) tokamak experimental fusion reactor has been started in April, 1975. At the same time a conceptual design of the 2000 MW sub(t) power reactor was further improved. In the development of large tokamak device of next generation, programs on JT-60 and JT-4 are being carried out. Research and development works and detailed design studies on JT-60 are started based on the preliminary design studies made in the previous year. Preliminary design studies on JT-4 are completed. (auth.)

  8. Neutronics experiments for DEMO blanket at JAERI/FNS

    Sato, Satoshi; Ochiai, K.; Hori, J.; Verzilov, Y.; Klix, A.; Wada, M.; Terada, Y.; Yamauchi, M.; Morimoto, Y.; Nishitani, T.

    2003-01-01

    In order to verify the accuracy of the tritium production rate (TPR), neutron irradiation experiments have been performed with a mockup relevant to the fusion DEMO blanket consisting of F82H blocks, Li 2 TiO 3 blocks with a 6 Li enrichment of 40 and 95%, and beryllium blocks. Sample pellets of Li 2 TiO 3 were irradiated and the TPR was measured by a liquid scintillation counter. The TPR was also calculated using the Monte Carlo code MCNP-4B with the nuclear data library JENDL-3.2 and ENDF-B/VI. The results agreed with experimental values within the statistical error (10%) of the experiment. Accordingly, it was clarified that the TPR could be evaluated within 10% uncertainty by the calculation code and the nuclear data. In order to estimate the induced activity caused by sequential reactions in cooling water pipes in the DEMO blanket, neutron irradiation experiments have been performed using test speciments simulating the pipes. Sample metals of Fe, W, Ti, Pb, Cu, V and reduced activation ferritic steels F82H were irradiated as typical fusion materials. The effective cross-sections for incident neutron flux to calculate the radioactive nuclei ( 56 Co, 184 Re, 48 V, 206 Bi, 65 Zn and 51 Cr) due to sequential reactions were measured. From the experimental results, it was found that the effective cross-sections remarkably increases with coming closer to polyethylene board that was a substitute of water. As a result of the present study, it has become clear that the sequential reaction rates are important factors to accurately evaluate the induced activity in fusion reactors design. (author)

  9. Present status of nuclear power safety studies in JAERI

    1989-01-01

    Japan Atomic Energy Research Institute carries out the safety research required for ensuring safety accompanying the development and utilization of atomic energy, dividing the roles with industrial circules, universities and other public research institutes. First, it carries out the research based on the yearly program of safety research, in which the subjects of safety research that the state should execute are decided. Next, it carries out a series of the safety verification test on atomic energy facilities entrusted by the state using the special account for power source development promotion countermeasures. Besides, it carries out the safety research on the specific subjects entrusted by outside organizations. The object and range of atomic energy safety at present are roughly divided into four fields, that is, nuclear power stations, nuclear fuel facilities, waste treatment and disposal, and environmental radioactivity. In order to advance the research effectively, in addition to the generalization department and the execution department, various committees are organized. In 1988, about 260 persons engaged in these four research fields, and the budget for fiscal year 1988 was about 17.4 billion yen. (K.I.)

  10. The TOF experiments and plans at JAERI-FNS

    Maekawa, Hiroshi

    1982-01-01

    A fast neutron source system (FNS) has been constructed at the Tokai Laboratory of Japan Atomic Energy Research Institute. The pulse width of d-d neutron from the FNS is 1.72 ns. The length of flight path is about 33 m. Prepared detectors are a NE-213 bank, a (B-10) 4 C-NaI bank, and Li-6, Li-7 glass scintillators. Various electronic circuits are provided. A DEC VAX- 11/780 computer is used for the data processing. The experiment to measure the angle-dependent leak spectra by Li 2 O and Li plate assemblies are designed and will be done in near future. (Kato, T.)

  11. Present status of nuclear power safety studies in JAERI, 1994

    1994-10-01

    Securing safety in the development and utilization of nuclear power is the prerequisite, and in order to maintain the safety of nuclear power facilities at level corresponding to the expansion and diversification of nuclear power development and utilization, it is necessary to promote the safety research. The reliable evaluation of environmental effect and the safe disposal of radioactive waste are the indispensable conditions. Japan Atomic Energy Research Institute has carried out the research on the engineering safety of nuclear reactors and nuclear fuel cycle facilities and the research on the environmental safety related to environmental radiation and the treatment and disposal of radioactive waste. In this book, the researches on the safety of reactor fuel, the reliability of reactor machinery and equipment and structures, the thermo-hydraulic behavior of reactors at the time of accidents, the behavior of reactors at the time of severe accidents, the analytical research on the safety of reactors, the researches on the safety of nuclear fuel cycle, the treatment and disposal of radioactive waste, the assessment and analysis of environmental radiation and radioactivity, and the individual researches related to nuclear power safety are reported. (K.I.)

  12. Neutronics experiments for DEMO blanket at JAERI/FNS

    Sato, S.; Ochiai, K.; Hori, J.; Verzilov, Y.; Klix, A.; Wada, M.; Terada, Y.; Yamauchi, M.; Morimoto, Y.; Nishitani, T.

    2003-01-01

    In order to verify the accuracy of the tritium production rate (TPR), neutron irradiation experiments have been performed with a mockup relevant to the fusion DEMO blanket consisting of F82H blocks, Li 2 TiO 3 blocks with a 6 Li enrichment of 40 and 95%, and beryllium blocks. Sample pellets of Li 2 TiO 3 were irradiated and the TPR was measured by a liquid scintillation counter. The TPR was also calculated using the Monte Carlo code MCNP-4B with the nuclear data library JENDL-3.2 and ENDF-B/VI. The results agreed with experimental values within the statistical error (10%) of the experiment. Accordingly, it was clarified that the TPR could be evaluated within 10% uncertainty by the calculation code and the nuclear data. In order to estimate the induced activity caused by sequential reactions in cooling water pipes in the DEMO blanket, neutron irradiation experiments have been performed using test specimens simulating the pipes. Sample metals of Fe, W, Ti, Pb, Cu, V and reduced activation ferritic steel F82H were irradiated as typical fusion materials. The effective cross- sections for incident neutron flux to calculate the radioactive nuclei ( 56 Co, 184 Re, 48 V, 206 Bi, 65 Zn and 51 Cr) due to sequential reactions were measured. From the experimental results, it was found that the effective cross-sections remarkably increases with coming closer to polyethylene board that was a substitute of water. As a result of the present study, it has become clear that the sequential reaction rates are important factors to accurately evaluate the induced activity in fusion reactors design. (author)

  13. Experiences in radioactive gaseous effluent management in JAERI

    Yoshida, Y.; Matsui, H.; Yamamoto, H.; Ikezawa, Y.; Hirayama, K.; Kokubu, M.

    1983-01-01

    In the Japan Research Reactor-II (JRR-2), the main source of 41 Ar generation is the exhaust air from the horizontal experimental holes and the pneumatic tubes. For the horizontal experimental holes, the flow of exhaust air through the holes was decreased by improving the airtightness, and a decay duct of capacity 2.4 m 3 was installed in the middle of the exhaust line. In consequence, the release rate of 41 Ar was reduced by 6-8%. For the pneumatic tubes, a mechanical shutter was installed in the tube. The shutter stops the exhaust air flow, except when the pneumatic tube is used. Prior to the use, the activated air in the tube is led to a decay tank. As a result, the 41 Ar release rate was reduced by 10-20%. By the above means, the yearly exposure at the site boundary was reduced to 0.36 mR from 2.6 mR. In Hot Laboratory for metallurgical examination of spent fuel, the exhaust filtration system consists of filters in the cave, i.e. frame trap, prefilter, HEPA filter, and the main filter system, i.e. prefilter, two-stage HEPA filter and charcoal filter (the charcoal filter is by-passed to lengthen its life when radioiodine is not released). Values of removal efficiency and the dispersion factor for iodine were 80% and 4.4x10 - 3 and for cesium 97% and 3.5x10 - 3 , respectively. The exhaust filtration system in Radioactive Waste Incineration Plant consists of a two-stage ceramic filter installed immediately after the incinerator, air cooler, two-stage HEPA filter and final scrubber. The decontamination factor of the two-stage ceramic filter is 1x10 6 for particulate matter, when measured with radioactive particles from burning of simulated contaminants with 75 mCi of 137 Cs. The decontamination factor of the HEPA filter after the ceramic filter is about 10 3 . The overall decontamination factor for the plant is estimated to be more than 10 6

  14. Engineering aspects of the JAERI proposal for INTOR, (2)

    1979-11-01

    To assess the data base of INTOR, a design study of the INTOR-J reactor system was carried out. Purpose of the study to evaluate the following five could be attained: (1) validity of the guiding parameters (especially those related to reactor size), (2) feasibility of a reactor with poloidal divertors, (3) design problems and research/development items in respective components, (4) possibility of repair and maintenance, and (5) design of the test sections for tritium breeding and electric power generation. (Author)

  15. Turbomolecular pumping systems for nuclear fusion devices in JAERI

    Ohga, Tokumichi; Arai, Takashi

    1978-01-01

    The turbomolecular pumping systems for the nuclear fusion devices JFT-2, JFT-2a and the injector test stands ITS-1, 2 and 3 in the Japan Atomic Energy Research Institute are mainly reported. For these vacuum systems, many requirements exist, such as oil free, large exhausting speed up to high pressure region (10 -3 Torr), compactness and easy operation and maintenance, etc., for the special usage. The outline of the systems and components, and the functions and the operational characteristics of the turbomolecular pumps are introduced. Concerning to the vacuum systems for JFT-2 and JFT-2a, the main system flow charts, the key specifications, the exhausting characteristic curves in case of starting from the atmospheric pressure for both JFT-2 and JFT-2a, and the conductance for hydrogen gas in the high vacuum side of JFT-2a are explained. As for the vacuum system for ITS-2, the main specification, the system flow chart, the main components, the functions, the conductance for hydrogen gas, the pumping characteristic curve, the starting characteristic of the turbomolecular pump, the exhausting speed for hydrogen gas and an example of mass spectrum are shown. The vacuum pressure obtained is almost 10 -5 -- 10 -6 torr for the three pumping systems. (Nakai, Y.)

  16. Statistics of meteorological data at Tokai Research Establishment in JAERI

    Sekita, Tsutomu; Tachibana, Haruo; Matsuura, Kenichi; Yamaguchi, Takenori

    2003-12-01

    The meteorological observation data at Tokai site were analyzed statistically based on a 'Guideline of meteorological statistics for the safety analysis of nuclear power reactor' (Nuclear Safety Commission on January 28, 1982; revised on March 29, 2001). This report shows the meteorological analysis of wind direction, wind velocity and atmospheric stability etc. to assess the public dose around the Tokai site caused by the released gaseous radioactivity. The statistical period of meteorological data is every 5 years from 1981 to 1995. (author)

  17. Forty years of nuclear manpower development activities in JAERI

    1998-01-01

    The training institute which was founded in 1958 for training researchers and engineers in atomic energy field attained to 40 years in January, 1998. During this period, it has accomplished the main role of training atomic energy engineers in Japan, but meeting the needs of the age, international training has been held, and also internally, the seminars for general public were carried out. So far, more than 45,000 persons who have finished the training have taken active parts in various atomic energy fields in Japan and abroad. The change of the training institute from initial Radioisotope Training Institute and Nuclear Reactor Training Institute to present International Atomic Energy General Technical Center is briefed. As to the training in Japan, the training of radioisotope and radiation technicians is reported about the basic course, the special course and the designated short course. As to the training of atomic energy engineers, the courses related to nuclear reactor engineering, the special courses on health physics, radiation protection, nuclear fuel and radioactive waste management, and the development of training techniques are described. As to the training of general public, the lecture on disaster prevention and atomic energy experiment seminar are performed. International training and the technical interchange in Asia and Pacific regions are reported. (K.I.)

  18. Critical experiments facility and criticality safety programs at JAERI

    Kobayashi, Iwao; Tachimori, Shoichi; Takeshita, Isao; Suzaki, Takenori; Miyoshi, Yoshinori; Nomura, Yasushi

    1985-10-01

    The nuclear criticality safety is becoming a key point in Japan in the safety considerations for nuclear installations outside reactors such as spent fuel reprocessing facilities, plutonium fuel fabrication facilities, large scale hot alboratories, and so on. Especially a large scale spent fuel reprocessing facility is being designed and would be constructed in near future, therefore extensive experimental studies are needed for compilation of our own technical standards and also for verification of safety in a potential criticality accident to obtain public acceptance. Japan Atomic Energy Research Institute is proceeding a construction program of a new criticality safety experimental facility where criticality data can be obtained for such solution fuels as mainly handled in a reprocessing facility and also chemical process experiments can be performed to investigate abnormal phenomena, e.g. plutonium behavior in solvent extraction process by using pulsed colums. In FY 1985 detail design of the facility will be completed and licensing review by the government would start in FY 1986. Experiments would start in FY 1990. Research subjects and main specifications of the facility are described. (author)

  19. Forty years of training program in the JAERI

    1998-03-01

    This report is to compile the past training program of researchers, engineers and regulatory members at the NuTEC (Nuclear Technology and Education Center) of Japan Atomic Energy Research Institute and the past basic seminars for the public, in addition to advice and perspective on the future program from relevant experts, in commemoration of the forty years of the NuTEC. It covers the past five years of educational courses and seminars in utilization of radioisotopes and nuclear energy for domestic and for international training provided at Tokyo and Tokai Education Centers and covers the activity of the Asia-Pacific nuclear technology transfer, including the activity of various committees and meetings. Especially, fifty six experts and authorities have contributed to the report with positive advice and perspective on the training program in the 21st century based on their reminiscences. (author)

  20. Conceptual design of the JAERI demonstration fusion reactor

    Sako, K.; Tone, T.; Seki, Y.

    1976-01-01

    Conceptual design of a tokamak demonstration fusion reactor is carried out. This design is an extended and improved version of the previous design which was presented at the 5th IAEA Conference. The main design parameters are as follows: the reactor thermal power 2000 MW, torus radius 10.5 m, plasma radius 2.7 m, first wall radius 3.0 m, toroidal magnetic field on axis 6T, blanket fertile material Li 2 O, coolant He, structural material Mo-alloy and tritium breeding ratio 1.2

  1. Development of beam instruments at JAERI cyclotron facility

    Okumura, Susumu; Fukuda, Mitsuhiro; Ishibori, Ikuo; Agematsu, Takashi; Yokota, Watalu; Nara, Takayuki; Nakamura, Yoshiteru; Arakawa, Kazuo [Japan Atomic Energy Research Inst., Takasaki, Gunma (Japan). Takasaki Radiation Chemistry Research Establishment

    1997-03-01

    A beam phase monitor and two kinds of fluence distribution monitors have been developed for measuring characteristics of cyclotron beams. The beam phase monitor provides a beam phase signal for tuning a beam chopping system and a beam phase selection system. A two-dimensional fluence distribution on a large area is measured with fluence distribution monitors. (author)

  2. Developing plan and pre-conceptual design of target system for JAERI`s high intensity neutron source

    Hino, Ryutaro; Kaminaga, Masanori; Haga, Katsuhiro; Ishikura, Syuichi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Nakamura, Fumito; Uchida, Shoji

    1997-11-01

    This paper presents an outline of developing plan of a target system and topics obtained by a pre-conceptual design, which aims to establish a technology base of the target system and to make clear a system concept. In the plan, two types of target - solid and mercury targets - are to be developed for a neutron scattering facility. Information obtained through the development shall be applied to designs of an irradiation and a transmutation facilities. Through the pre-conceptual design, system arrangement, scale etc. were made clear: total weight will be 12000 ton, and 26 beam lines with beam shutters will be equipped for 4 moderators. Engineering problems were also made clear through the design; high flux heat removal, dynamic stress caused by thermal shock and pressure wave, loop technology for the mercury target and a slurry moderator consisting of methane pellets and liquefied hydrogen. We are now constructing new test apparatuses and arranging computer codes for solving these problems. (author)

  3. Safety concept for spallation target system. JAERI/KEK joint project

    Kobayashi, K.; Kaminaga, M.; Haga, K.; Kinoshita, H.; Hino, R.

    2001-01-01

    A MW-class mercury target of the spallation target generates much larger amounts of radioactive nuclides than existing spallation neutron sources. To estimate the maximum level of public exposure under the guillotine break of mercury pipelines that is one of the major accidents of the target system, the hazard analyses were carried out by using a transportation model which considers heat transmission of mercury decay heat, diffusion of evaporated radioactive nuclides, etc. In the analyses, mercury, iodine, bromine and noble gas were selected as the effective source term because of their high vapor pressures and activation levels. From the preliminary analytical results obtained under the conservative conditions of 2 m/s of the air velocity around the mercury leakage area, the maximum level of the public exposure was approximately 5.8 x 10 -3 mSv. This level is negligible in comparison with 1 mSV one-year natural radiation exposure. (author)

  4. Voltage conditioning and beam performance of the 2OUR Pelletron at JAERI

    Norton, G.A.; Sundquist, M.L.; Daniel, R.E.; Rathmell, R.D.

    1982-01-01

    The Pelletron Model 2OUR was formally accepted by the Japan Atomic Energy Research Institute in Tokai, Japan, on August 10, 1982. The 2OUR is a 20 MV, folded tandem with a 300 kV injector with four ion sources on the injector deck. The 2OUR is equipped with an internal ion source and nanosecond bunching and pulsing system in the high voltage terminal. This ion source and pulsing system is designed to produce intense peak currents of proton and deuteron beams. The accelerator is also equipped with an external nanosecond bunching and pulsing system for nanosecond pulsed beams in the tandem mode for ions up to mass 240. The formal acceptance of the accelerator was based on operation at 18 MV. However, the 2OUR has operated in a very stable fashion, accelerating an oxygen beam with a terminal potential of 18.5 MV. Mechanical deficiencies outside of the accelerating tube presently limit operation below 20 MV

  5. Health physics in JAERI, No.39. (April 1, 1996 - March 31, 1997)

    NONE

    1997-12-01

    In the annual report No.39 (fiscal 1996) are described the activities of health physics in Tokai Research Establishment, Naka Fusion Research Establishment, Takasaki Radiation Chemistry Research Establishment, Oarai Research Establishment, Kansai Research Establishment and Mutsu Establishment. In all the establishments, radiation monitoring in nuclear facilities, individual monitoring, environmental monitoring and maintenance of monitoring instruments were carried out as in the previous years. There were no occupational exposure exceeding the effective dose equivalent limit and no release of radioactive gaseous and liquid wastes beyond the release limits specified in the regulations. In the environment, no abnormal radioactivity was detected except for a slight amount of radioactive cesium in a dust sample at Oarai Research Establishment attributable to the fire and explosion (March 11, 1997) at the Asphalt Bituminization Treatment Facility at the Tokai Works of Power Reactor and Nuclear Fuel Development Corporation. Technology developments were made as in the previous years for improving the techniques and methods of monitoring of individuals, facilities and environment, and also radiation measurement instrumentation. The research works were carried out in various fields such as radiation dosimetry, environmental monitoring, and so forth. (author)

  6. Atomic and molecular data activities at JAERI, September 1999 - August 2001

    Shirai, T.

    2001-01-01

    Compilation and evaluation work has been carried out to make the 5th edition of Evaluated Atomic and Molecular (A+M) Data Library (JEAMDL-5) for fusion. The main objective of JEAMDL-5 is to evaluate A+M data relevant to divertor plasmas. Recent data activities and work in progress are briefly summarized. (author)

  7. A target-moderator-reflector concept of the JAERI 5 MW pulsed spallation neutron source

    Watanabe, Noboru; Teshigawara, Makoto; Aizawa, Kazuya; Suzuki, Jyunichi; Oyama, Yukio

    1998-03-01

    In Japan Atomic Energy Research Institute the construction of a 5 MW (short) pulsed spallation neutron source is under planning using a projected high power superconducting proton (or H - ) linac of 8 MW in total beam power. In the present paper we report our consideration on target-moderator-reflector concept, based on the layout of the tentative neutron instruments for the assumed neutron scattering experiments in future. The choice of cold neutron moderators for high resolution and high intensity experiments, thermal and epithermal neutron moderators for high resolution uses was discussed and a reference layout of target-moderator-reflector system was proposed for detailed neutronic calculation and optimization. The proposed system was designed like that it can provide, at least, 30 beam lines for more than 40 instruments. (author)

  8. Health physics and safety in JAERI, No.20 (April 1, 1977 - March 31, 1978)

    1979-01-01

    In the annual report No. 20 (fiscal 1977) are described the activities of health physics and safety in the Tokyo Office, Tokai Research Establishment, Takasaki Radiation Chemistry Research Establishment, and Oarai Research Establishment. (Author)

  9. Health physics in JAERI, No. 40. April 1, 1997 - March 31, 1998

    1998-12-01

    In the annual report No. 40(fiscal 1997) are described the activities of health physics in Tokai Research Establishment, Naka Fusion Research Establishment, Takasaki Radiation Chemistry Research Establishment, Oarai Research Establishment, Kansai Research Establishment and Mutsu Establishment. In all the establishments, radiation monitoring in nuclear facilities, individual monitoring, environmental monitoring and maintenance of monitoring instruments were carried out as in the previous years. There were no occupational exposure exceeding the effective dose equivalent limit and no release of radioactive gaseous and liquid wastes beyond the release limits specified in the regulations, Kansai Research Establishment completely discontinued use of radioisotopes at Neyagawa Office and commissioned Japan Synchrotron Radiation Research Institute to manage radiation control works on the Synchrotron Radiation Facilities. The investigation of the radiation monitoring plans for Advanced Photon Research Center which is founded at Kizu site was started. Technology developments were made as in the previous years for improving the techniques and methods of monitoring of individuals, facilities and environment, and also radiation measurement instrumentation. The research works were carried out in various fields such as radiation dosimetry, environmental monitoring, and so forth. (author)

  10. Present status of nucleon-meson transport code NMTC/JAERI

    Takada, H.; Meigo, S.

    2001-01-01

    The nucleon-meson transport code NMTC/JAM has been developed for the neutronics design study of the joint project for high-intensity proton accelerators with a power of mega-watts. The applicable energy range is extended by the inclusion of the jet AA microscopic transport model (JAM). The nucleon-nucleus cross sections are also updated for accurate transport calculation. The applicability of NMTC/JAM is studied through the analyses of thick target experiments such as neutron transmission through shield and activation reaction rate measurements. (orig.)

  11. Activities of JAERI's health physics department for the criticality accident of JCO

    Yamamoto, Katsumune; Kitano, Kyoshiro; Murakami, Hiroyuki; Yamaguchi, Takenori; Tsunoda, Masahiko

    2000-01-01

    This report describes early health physics activities from September 30 to October 1 taken by the authors' department after the JCO accident. They firstly knew the accident at around 12:20 (about 2 hr after the criticality). The activities involved the planning of schedule for ending the criticality; calculation of scheduled dose for the work to end it; dose measurement around JCO site; loaning out of devices for measuring neutron and of personal dose-meter; collection and radioactivity measurement of dust and soil, and of drinking water; and examination for contamination of people around the site, of their houses inside and of school gardens and equipments. The dose was scheduled to be firstly 20 mSv and then changed to 50 mSv due to the actual measurement at the accident site. The working time was to be 3 min at the site. The work was on either the dose or time. Radiation monitoring outside the JCO site revealed the presence of Na-24 and Cs-138: neutron dose was 10 times as high as γ-ray dose. The time course of dose rate change was found to be in parallel with the progress of works to end the criticality. (K.H.)

  12. Overview of gap streaming experiments for ITER at JAERI/FNS

    Konno, Ch.; Maekawa, F.; Oyama, Y.; Uno, Y.; Kasugai, Y.; Wada, M.; Maekawa, H.; Ikeda, Y.

    1998-01-01

    Gap streaming experiments were performed by using a D-T neutron source, FNS, at Japan Atomic Energy Research Institute as a part of an ITER/EDA R and D Task (T-218), in order to investigate the influence of neutron streaming due to gap between shielding blanket modules in ITER. The direct gap increased 14-MeV neutron flux by 20 times at the cavity center and rear surface of the experimental assembly, while the offset gap increased by 3 times. On the other hand the increase of neutrons below 1 MeV and gamma-rays was less than a few tens % even for the direct gap assemblies. This result suggests that gap streaming has a large influence on helium production and radiation damage sensitive to high energy neutrons rather than on gamma heating. Calculated values agreed within ±30 % with most of the experimental data. This result demonstrates that the MCNP code with the FENDL/E-1.1 and JENDL Fusion File cross section libraries can be used with reliance for shield designs of ITER for configuration with gap if the geometry is modeled precisely. (authors)

  13. IFPE/IFA-508 and 515, PCMI Behaviour of Thin Cladding Rods, JAERI and HRP

    2007-01-01

    Description: To measure the integrated response of UO 2 and its cladding to conditions associated with PCI, the Japan Atomic Energy Research Institute carried out a series of experiments in the Halden BWR. The experiment involved two major objectives. The first was to study the influence of rod design parameters on PCI. Diametral gap, wall cladding thickness, SiO 2 additive, and pellet grain size were used as design parameters. The second objective was to study the influence of pre-irradiation (i.e. burnup) on PCI. The maximum burnup attained in the experiment was 23 MWd/kgU. These research results can be applied to current BWR-type fuel rods. The tests were performed between April 1977 and March 1981

  14. Present status of nuclear fusion research and development in JAERI. 1984 ed.

    1984-01-01

    This year is the 10th year in the ''Second stage nuclear fusion research and development project'', and the main plan to construct a critical plasma testing apparatus, JT-60, is about to be completed. The test of the power source and control system, and the assembling of the main body were finished, and the final general test is about to be started. In foreign countries, already experiment was begun with the TFTR and the JET, and the formation of the plasma at 20 million deg with the containment time of about 0.3 sec was accomplished. The results of heating experiment by incorporating heating devices are anxiously waited for. As the next generation projects, the conceptual design of the burning core experiment aiming at the attainment of self ignition condition was started in USA, and the next European torus is to be developed in EC before reaching the prototype DEMO. In Japan, it is intended to advanced to the attainment of self ignition condition and an experimental reactor for verifying nuclear fusion technology. In USSR, the construction of a superconducting tokamak T-15 is likely to be completed in 1986. The international cooperation is expected because of the financial condition of respective countries. (Kako, I.)

  15. Estimation of a beam centering error in the JAERI AVF cyclotron

    Fukuda, M.; Okumura, S.; Arakawa, K.; Ishibori, I.; Matsumura, A.; Nakamura, N.; Nara, T.; Agematsu, T.; Tamura, H.; Karasawa, T.

    1999-01-01

    A method for estimating a beam centering error from a beam density distribution obtained by a single radial probe has been developed. Estimation of the centering error is based on an analysis of radial beam positions in the direction of the radial probe. Radial motion of a particle is described as betatron oscillation around an accelerated equilibrium orbit. By fitting the radial beam positions of several consecutive turns to an equation of the radial motion, not only amplitude of the centering error but also frequency of the radial betatron oscillation and energy gain per turn can be evaluated simultaneously. The estimated centering error amplitude was consistent with a result of an orbit simulation. This method was exceedingly helpful for minimizing the centering error of a 10 MeV proton beam during the early stages of acceleration. A well-centered beam was obtained by correcting the magnetic field with a first harmonic produced by two pairs of harmonic coils. In order to push back an orbit center to a magnet center, currents of the harmonic coils were optimized on the basis of the estimated centering error amplitude. (authors)

  16. Report on progress of researches by common utilization of JAERI nuclear facilities, for fiscal 1982

    1983-01-01

    The utilization of the facilities in the Japan Atomic Energy Research Institute in common in 1982 has finished in active state, and the results of the researches have reached the stage of publication. The subjects of the researches spread over wide fields, and in 1982 also, extremely diversified researches were carried out. In this report, theses results were collected in one book, and it is desirable to utilize it actively. The number of the research themes is 131. In the field of general researches, the researches on radiochemistry, the utilization of radiation and the effects of irradiation were mostly carried out, while in cooperative researches, the researches were mainly concerned with nuclear reactor engineering and nuclear reactor materials. The total number of visitors was 3025. The facilities offered to the common utilization were JRR-2, JRR-3, JRR-4, Co-60 irradiation facility and others. The abstracts of the papers are reported. (J.P.N.)

  17. In-terminal ECR Ion Source of the Tandem Accelerator at JAERI

    Matsuda, M; Takeuchi, S

    1999-01-01

    Electron Cyclotron Resonance Ion Source(ECRIS)s are able to produce intense beams of highly charged positive ions and used injection system for cyclotron, linac as well as experiments of atomic physics. The tandem accelerator system has been benefiting from use of an electron stripper at the high voltage terminal. The most probable charged state after a foil stripper is, however, much lower than the highest charge state of ions with an intensity of more than several emA from a high performance ECRIS. With respect to beam current, the life time of stripper foils decrease with increasing beam current. Especially for very heavy ions, it is difficult to obtain a stable and intense beam for a long time without foil exchange. Use of an ECRIS in a tandem accelerator is expected to increase beam intensity, beam energy and beam species. A small permanent magnet ECRIS has been installed in the high voltage terminal of the vertical and folded type 20UR Pelletron tandem accelerator at Japan Atomic Energy Research Institu...

  18. Radiation safety of Takasaki ion accelerators for advanced radiation in JAERI

    Watanabe, Hiromasa; Tanaka, Susumu; Anazawa, Yutaka

    1991-01-01

    Building layout of Takasaki ion accelerator facility has been started since 1987, with the propulsion of research development of (1) cosmetic environment materials, (2) nuclear fusion reactors, (3) biotechnology, and (4) new functional materials. This paper deals with an AVF cyclotron and a tandem type accelerator, focusing on safety design, radiation safety management, and radioactive waste management. Safety design is discussed in view of radiation shielding and activation countermeasures. Radiation safety management covers radiation monitoring in the workplace, exhaust radioactivity, environment outside the facility, and the other equipments; personal monitoring; and protective management of exposure. For radiation waste management, basic concept and management methods are commented on. (N.K.)

  19. Improvement of spallation reaction simulation codes NMTC/JAERI and NUCLEUS

    Nishida, T.; Takada, H.; Kanno, I.; Nakahara, Y.

    1990-01-01

    To make evaluations of theoretical models for nuclear spallation reaction, simulation codes are modified and a new mass formula is used to improve the accuracy of Monte Carlo calculations. The following conclusions are made from analyses of calculated distributions of nuclear spallation products. A difference is found between the Cameron's old and the Uno and Yamada's new mass formula, which is due to the difference in the method used to fit their shell energy terms to measured data for selected nuclei and in data themselves. For nuclides with an atomic number larger than 70, mass excesses calculated by the Camerons's mass formula are greater than those by the Uno and Yamada's one, whereas the reverse tendency is seen for ones with atomic numbers smaller than 70. Analysis shows that the distributions of produced nuclei have patterns that appear natural from a physical point of view when artificial restrictions are removed in counting the nuclide production events. The new mass formula can reproduce fairly well the experimental product yield distributions, especially in the neutron excess side. It is also found that the old mass formula gives lower estimations for the number of produced nuclei than the new one, especially in the nuclide region far from the beta stable line. (N.K.)

  20. Health physics in JAERI, No. 41 (April 1, 1998 - March 31, 1999)

    NONE

    2000-03-01

    In the annual report No. 41(fiscal 1998) are described the activities of health physics in Tokai Research Establishment, Naka Fusion Research Establishment, Takasaki Radiation Chemistry Research Establishment, Oarai Research Establishment, Kansai Research Establishment and Mutsu Establishment. In all the establishments, radiation monitoring in nuclear facilities, individual monitoring, environmental monitoring and maintenance of monitoring instruments were carried out as in the previous years. There were no occupational exposure exceeding the effective dose equivalent limit and no release of radioactive gaseous and liquid wastes beyond the release limits specified in the regulations. Kansai Research Establishment was made the investigation of the radiation monitoring plans for Advanced Photon Research Center which was under construction at Kizu site. Technology developments were made as in the previous years for improving the techniques and methods of monitoring of individuals, facilities and environment, and also radiation measurement instrumentation. The research works were carried out in various fields such as radiation dosimetry, environmental monitoring, and so forth. In Department of Health Physics, matters for restructure of the department were discussed continuously, especially about a subject for the research of health physics was discussed with reference to the opinion of knowledgeable people. (author)

  1. A computer code 'BEAM' for the ion optics calculation of the JAERI tandem accelerator system

    Kikuchi, Shiroh; Takeuchi, Suehiro

    1987-11-01

    The computer code BEAM is described, together with an outline of the formalism used for the ion optics calculation. The purpose of the code is to obtain the optimum parameters of devices, with which the ion beam is transported through the system without losses. The procedures of the calculation, especially those of searching for the parameters of quadrupole lenses, are discussed in detail. The flow of the code is illustrated as a whole and its constituent subroutines are explained individually. A few resultant beam trajectories and the parameters used to obtain them are shown as examples. (author)

  2. Recent status of research activities for development of CTBT-related technologies in JAERI

    Hirota, Naoki; Houkida, Takanori; Inoue, Yoji

    2003-08-01

    This report describes research activities of the R and D Group for Non-Proliferation Technology related to the Comprehensive Nuclear-Test-Ban Treaty (CTBT) verification regime. The main subjects of this report are (1) an overview of the CTBT verification regime, (2) preparation of the National Data Center for radionuclide data, (3) construction and operation of the radionuclide monitoring stations at Takasaki and Okinawa and the certified radionuclide laboratory at Tokai in Japan. We have participated in an intercomparison test internationally organized for the certified laboratories and the test results are given here. Scientific application of the CTBT-related technologies to environmental researches is also depicted. (author)

  3. SRAC: JAERI thermal reactor standard code system for reactor design and analysis

    Tsuchihashi, Keichiro; Takano, Hideki; Horikami, Kunihiko; Ishiguro, Yukio; Kaneko, Kunio; Hara, Toshiharu.

    1983-01-01

    The SRAC (Standard Reactor Analysis Code) is a code system for nuclear reactor analysis and design. It is composed of neutron cross section libraries and auxiliary processing codes, neutron spectrum routines, a variety of transport, 1-, 2- and 3-D diffusion routines, dynamic parameters and cell burn-up routines. By making the best use of the individual code function in the SRAC system, the user can select either the exact method for an accurate estimate of reactor characteristics or the economical method aiming at a shorter computer time, depending on the purpose of study. The user can select cell or core calculation; fixed source or eigenvalue problem; transport (collision probability or Sn) theory or diffusion theory. Moreover, smearing and collapsing of macroscopic cross sections are separately done by the user's selection. And a special attention is paid for double heterogeneity. Various techniques are employed to access the data storage and to optimize the internal data transfer. Benchmark calculations using the SRAC system have been made extensively for the Keff values of various types of critical assemblies (light water, heavy water and graphite moderated systems, and fast reactor systems). The calculated results show good prediction for the experimental Keff values. (author)

  4. Joint operation of TSTA under the collaboration between JAERI and DOE

    Konishi, Satoshi; O-hira, Shigeru; Inoue, Masahiko

    1993-03-01

    Under the Annex IV of the US-Japan Collaboration Program, loop test of the TSTA was performed in October, 1990. This test is focused on the Isotope Separation System with 3 distillation columns operated. The system was stably operated and DT products were continuously obtained. Composition profile along the columns were successfully measured with the Gas Chromatograph. In the Fuel Cleanup System, amount of adsorbed tritium on the cold molecular sieve beds were measured and a large impact of this phenomena on inventory was revealed. (author)

  5. RIKEN-JAERI 8-GeV synchrotron radiation project - SPring-8

    Awaya, Yohko

    1990-01-01

    The plan of an 8-GeV synchrotron radiation facility, which is called SPring-8 (Super Photon Ring-8GeV), had been proposed by Science and Technology Agency (STA) in Japan and it was decided that its construction would be started from April 1990. An atomic physics group in Japan had the first meeting in December 1988 to discuss the future studies of atomic physics and related problems at SPring-8 and plans of research and development (R and D) for them. Their report was published in May 1990. In this report, an outline of SPring-8 is described. Results of the discussions of Japanese working group of atomic physics and the present status of R and D of this group will be presented by M. Kimura in this workshop

  6. Recent progress of partitioning process in JAERI: development of amide-based artist process

    Shoichi, Tachimori; Yuji, Sasaki; Yasuji, Morita; Shin-ichi, Suzuki

    2003-01-01

    A branched-alkyl monoamide which extracts An(VI) exclusively by the steric effect and tridentate diglycol-amide; TODGA, which recovers all actinides and Sr(II) from highly acidic waste solutions, were developed. Then, a new chemical process, ARTIST process, is proposed for the treatment of nuclear spent fuel consolidating plutonium management and the partitioning concept. (author)

  7. Research and development of the JAERI large tokamak (JT-60), (4)

    Takashima, Tetsuo; Shimizu, Masatsugu; Ohta, Mitsuru; Minaguchi, Tadayoshi; Maeda, Hideto.

    1978-01-01

    A pair of fast-acting movable rail limiters are to be installed in the vacuum chamber of JT-60 to suppress skin current in the plasma column. They should travel across the vacuum chamber over a stroke of about 1 m in 0.1 sec in the build-up phase of the plasma current. Each movable limiter system consists of a drive mechanism, a vacuum seal, a bearing usable at high temperatures in a vacuum, a molybdenum rail limiter head and its auxiliary members. Various engineering problems are involved in constructing such a system because the design specifications outlined above exceed the present technology. A full-scale movable limiter, therefore, was designed, constructed and then put to mechanical, electrical and vacuum-technological tests. The model features a hydraulic drive mechanism with servovalves to control the oil flow. A special vacuum seal allowing a movement at high speeds was developed. It consists of welded bellows jointed together and connected to a pantograph at the joints. It allows uniform expansion of each bellows at high speeds. Molybdenum disulphide with 20% Ta is chosen as the most suitable bearing material after conducting tests on various bearing materials. The overall test of the model showed that its specifications were met with satisfactory reliability and reproducibility. Furthermore, the endurance test demonstrated that it functioned reliably over 50,000 times of operation. (author)

  8. Report on JAERI's Reimei Research Program. April 1, 2005 - March 31, 2006

    Ikezoe, Hiroshi

    2007-02-01

    The Reimei (Dawn) Research Program is a research project based on public application to be conducted within the framework of the Reimei Research Promotion project of the Japan Atomic Energy Research Institute. The objective of the program is to encourage original and/or unique ideas in the field of fundamental nuclear science and nuclear energy. The number of the research subjects accepted in the fiscal year 2005 was 38 and the summaries of these research subjects were compiled in this report. We hope that new researches will be grown and developed by the help of Reimei Research Promotion project. (author)

  9. Health physics in JAERI No. 35 (April 1, 1992 ∼ March 31, 1993)

    1993-09-01

    In the annual report No. 35 (fiscal 1992) are described the activities of health physics in Tokai Research Establishment, Takasaki Radiation Chemistry Research Establishment, Oarai Research Establishment, Mutsu Establishment and Nuclear Ship Mutsu. In all the establishments, radiation monitoring in nuclear facilities, individual monitoring, environmental monitoring and maintenance of monitoring instruments were carried out as in the previous years. There were no occupational exposure exceeding the dose equivalent limit and no release of radioactive gaseous and liquid wastes beyond the release limits specified according to the regulations. In the environment there were detected no abnormal radioactivity due to the facilities. (author)

  10. Experimental study on accelerator driven subcritical reactor. JAERI's nuclear research promotion program, H12-031 (Contract research)

    Shiroya, Seiji; Misawa, Tsuyoshi; Unesaki, Hironobu

    2004-03-01

    In view of the future plan of Research Reactor Institute, Kyoto University (KURRI), the present study consisted of 1) the transmission experiments of high energy neutrons through materials, 2) experimental simulation of ADSR using the Kyoto University Critical Assembly (KUCA), and 3) conceptual neutronics design study on Kyoto University Reactor (KUR) type ADSR using the MCNPX code. The purpose of the present study was not only to obtain the knowledge usable for the realization of ADSR as a new neutron source for research but also to select technical issues in the field of reactor physics for the development of ADSR in general. Through the present study, valuable knowledge on the basic nuclear characteristics of ADSR was obtained both theoretically and experimentally. This kind of knowledge is indispensable to promote the study on ADSR further. If one dare say the main part of knowledge in short words, the basic nuclear characteristics of ADSR is overwhelmed by the characteristics of the subcritical reactor as expected. For the realization of ADSR in the future, it is considered to be necessary to accumulate results of research steadily. For this purpose, it is inevitable 1) to compile the more precise nuclear data for the wide energy range, 2) to establish experimental techniques for reactor physics study on ADSR including subcriticality measurement and absolute neutron flux measurement from the low energy region to the high energy region, and 3) to develop neutronics calculation tools which facilitate to take into account the neutron generation process by the spallation reaction and the delayed neutron behavior. (author)

  11. World's largest DC flywheel generator for the toroidal field power supply of JAERI's JFT-2M Tokamak nuclear fusion reactor

    Tani, Takashi; Nakanishi, Yuji; Horita, Tsuyoshi; Kawase, Chiharu; Oyabu, Isao; Kishimoto, Takeshi.

    1996-01-01

    Mitsubishi Electric has delivered the world's largest DC generator for the toroidal field coil power supply of the JFT-2M Tokamak at the Japan Atomic Energy Research Institute. The unit rotates at 225 or 460 rpm, providing a maximum rated output of 2,700 V, 19,000 A and 51.3 MW. The toroidal field is a DC field, so use of a DC generator permits a simpler design consuming less floor space than an AC drive system. The generator was manufactured following extensive studies on commutation, mechanical strength and insulation. (author)

  12. Status of the research and development at JAERI on the C/C composite control rod for HTGR

    Eto, M.; Ishiyama, S.; Ugachi, H.

    1996-01-01

    Control rod elements made of carbon-carbon composites were prepared and fracture-tested, aiming at the development of the more heat-resistant control rod which may impose the less restriction on the operation and shutdown of the HTGR. The control rod elements included pellet holder, lace truck and pin of PAN- or pitch-based composite material. On the basis of the results of fracture tests on the unirradiated elements, those made of PAN-based material were selected for an irradiation experiment. The irradiation was carried out in JRR-3 at 900 ± 50 deg. C to a maximum neutron fluence of 1 x 10 25 n/m 2 (E>29fJ). Fracture tests of the elements indicated that both fracture load and fracture displacement enough to assure the integrity of a control rod were maintained even after the irradiation. It was also found that both fracture strength and strain increased when applied load was parallel to the fiber felt plane, whereas the strength increase and strain decrease were observed for the load applied against the plane. (author). 11 refs, 16 figs

  13. The 1/3-scale aerodynamics performance test of helium compressor for GTHTR300 turbo machine of JAERI (step 1)

    Takada, Shoji; Takizuka, Takakazu; Kunitomi, Kazuhiko; Xing, Yan

    2003-01-01

    A program for research and development on aerodynamics in a helium gas compressor was planned for the power conversion system of the Gas Turbine High Temperature Reactor (GTHTR300). The three-dimensional aerodynamic design of the compressor achieved a high polytropic efficiency of 90%, keeping a sufficient surge margin over 30%. To validate the design of the helium gas compressor of GTHTR300, aerodynamic performance tests were planned, and a 1/3-scale, 4-stage compressor model was designed. In the tests, the performance data of the helium gas compressor model will be acquired by using helium gas as a working fluid. The maximum design pressure at the model inlet is 0.88 MPa, which allows the Reynolds number to be sufficiently high. The present study is entrusted from the Ministry of Education, Culture, Sports, Science and Technology of Japan. (author)

  14. Development of reconstitution technique of irradiated specimen. 2. Annual report for FY1994 on JAERI-IHI cooperated research program

    Nishiyama, Yutaka; Fukaya, Kiyoshi; Onizawa, Kunio; Suzuki, Masahide; Shibata, Katsuyuki [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Kaihara, Shoichiro; Nakamura, Terumi; Sato, Akira; Yoshida, Kazuo

    1996-02-01

    A surface-activated joining method to construct Charpy impact specimens from a limited volume of broken specimens is being developed. The method is likely to decrease the thermal input led to annealing and metallurgical changes. This paper describes the technical qualification process of the joining parameters and surface configuration of joined specimens. All tests have been done with A533B cl.1. The joining machine with higher vacuum than that previously used was prepared for the tests. Precise control of joining parameters led to heat-affected zone as small as 1mm in each side. In the case of joining the square shaped (10x10mm) and circular shaped ({phi} 16mm) specimens, overall joining was achieved by an attached envelope to the square shaped specimen. In addition, the grooved surface of the circular shaped specimen brought out uniformly distributed heat-affected zone. The specification of hot-use joining machine which involves the joining sequence and restrictions of the dimension was also examined. (author).

  15. Utilization of actinide as cell active materials. JAERI's nuclear research promotion program, H10-034-1. Contract research

    Shiokawa, Yoshinobu; Yamamura, Tomoo; Watanabe, Nobutaka; Umekita, Satoshi

    2002-03-01

    The electrochemical properties of U, Np, Pu and Am were discussed from the viewpoint of cell active materials From the thermodynamic properties and the kinetics of electrode reactions, it is found that neptunium in the aqueous system and some uranium complexes in the polar aprotic solvents can be utilized as an active material of the redox flow battery for the electric power storage. Moreover, A new actinide redox battery is proposed in the present article: the galvanic cell is expressed by Electrode(-) |An 3+ , An 4+ | |AnO 2 + , AnO 2 2+ | Electrode(+). The actinide batteries are expected to have more excellent charge and discharge performance than the current vanadium battery because of the great similarity of chemical species in the each redox couple. The standard rate constants and formal potential of Np(VI)/Np(V) and Np(IV)/Np(III) couples were determined by the cyclic voltammetry and the neptunium battery was demonstrated. For the development of uranium redox flow battery, the redox reaction mechanisms and redox potentials of uranium -diketones including new -tetraketones were elucidated and it was found the open circuit voltage is increased with the acid dissociation constant of the ligand. (author)

  16. Present status of research on radiation utilization in 1994 at JAERI. Utilization of irradiation and RI production and utilization

    1994-10-01

    In Japan Atomic Energy Research Institute, Takasaki Radiation Chemistry Research Establishment is in charge of the utilization of irradiation, and Tokai Research Establishment is in charge of the production and utilization of radioisotopes. As for the utilization of irradiation the development of new polymers, the development of environment preservation technology such as flue gas treatment, and by using various ion beams from four accelerators, the development of the materials used for space environment, nuclear fusion and new functional materials, the research on the radiation application to biotechnology, the development of the production and utilization of new radioisotopes have been carried out. As for the production and utilization of radioisotopes, the development of new products and new utilization techniques, the technology of producing and using a large amount of tritium, and the research on the chemical behavior of tritium have been carried out. The international cooperations have been promoted positively. In this report, the research activities in 1994 are described. (K.I.)

  17. Fuel temperature prediction during high burnup HTGR fuel irradiation test. US-JAERI irradiation test for HTGR fuel

    Sawa, Kazuhiro; Fukuda, Kousaku; Acharya, R.

    1995-01-01

    This report describes the preirradiation thermal analysis of the HRB-22 capsule designed for an irradiation test in a removable beryllium position of the High Flux Isotope Reactor(HFIR) at Oak Ridge National Laboratory. This test is being carried out under Annex 2 of the Arrangement between the U.S. Department of Energy and the Japan Atomic Energy Research Institute on Cooperation in Research and Development regarding High-Temperature Gas-cooled Reactors. The fuel used in the test is an advanced type. The advanced fuel was designed aiming at burnup of about 10%FIMA(% fissions per initial metallic atom) which was higher than that of the first charge fuel for the High Temperature Engineering Test Reactor(HTTR) and was produced in Japan. CACA-2, a heavy isotope and fission product concentration calculational code for experimental irradiation capsules, was used to determine time-dependent fission power for the fuel compacts. The Heat Engineering and Transfer in Nine Geometries(HEATING) code was used to solve the steady-state heat conduction problem. The diameters of the graphite fuel body, which contains the fuel compacts, and of the primary pressure vessel were determined such that the requirements of running the fuel compacts at an average temperature less than 1250degC and of not exceeding a maximum fuel temperature of 1350degC were met throughout the four cycles of irradiation. The detail design of the capsule was carried out based on this analysis. (author)

  18. Expected performance and benefits of an advanced containment and surveillance system at the fast critical facility fca of jaeri

    Mukaiyama, T.; Kuroi, H.

    1981-01-01

    This paper reports on the development and test of a personnel portal monitor for IAEA safeguards at the fast critical facility FCA. The main components of the portal are 1) the walk-through metal detector, 2) the visual surveillance system with CCTV, 3) the tamper indication system using multi sensors and 4) the remote monitoring capability through RECOVER system. The metal detector developed can detect a single coupon of metallic nuclear fuel plate (2 in. *2 in. *1/16 in.) regardless of the orientation of a fuel plate relative to the electromagnetic field generated in the metal detector. 3 refs

  19. Development of novel functional dyes for the effective detection of γ-ray. JAERI's nuclear research promotion program, H12-007. Contract research

    Tokita, Sumio; Yoshida, Masaru

    2004-03-01

    The academic field of ''Functional Dyes'' was proposed in Japan and has been widely applied to novel functional materials for electronic industry, however, its application to radiation chemistry is still scarce. We have found a certain photochromic dye, benzo[1,2,3-kl:4,5,6-k'l'] dixanthene endoperoxide, to give dramatic change of color in acid conditions. In this research project, we have developed this finding to realize novel dosimetry systems. The findings of this research are as follows: 1. Computer programs for the molecular design of functional materials using quantum chemical method such as PPP or INDO/S molecular orbital calculations were developed. 2. Novel functional materials for the detection of γ-ray were surveyed. Among these, the following series of compound were found to have practical importance. a. Color formers having phenoxazine moieties. b. Color formers having sulfur containing protective groups. 3. Novel sensor systems for γ radiation using functional materials were developed. (author)

  20. Super safe small reactor RAPID-L conceptual design and R and D. JAERI's nuclear research promotion program, H11-002 (Contract research)

    Kambe, Mitsuru [Central Research Inst. of Electric Power Industry, Tokyo (Japan); Tsunoda, Hirokazu [Mitsubishi Research Inst., Inc., Tokyo (Japan); Mishima, Kaichiro [Kyoto Univ., Kyoto (Japan); Kawasaki, Akira [Tohoku Univ., School of Engineering, Sendai, Miyagi (Japan); Iwamura, Takamichi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2003-03-01

    The 200 kWe uranium nitride fueled lithium cooled fast reactor 'RAPID-L' combined with thermoelectric power conversion system that can be operated unmanned without refueling for up to ten years has been demonstrated. The RAPID refueling concept enables quick and simplified refueling, and achieves plant design lifetime over 20 years. A significant advantage of the RAPID-L design, which does not require the use of control rods - is the introduction of the innovative reactivity control systems: lithium expansion module (LEM), lithium injection module (LIM) and lithium release module (LRM). LEM is the most promising candidate for improving inherent reactivity feedback. LEMs could realize burnup compensation. LIMs assure sufficient negative reactivity feedback in unprotected transients. LRMs enable an automated reactor startup by detecting the hot standby temperature of the primary coolant. All these systems use {sup 6}Li as liquid poison and are actuated by highly reliable physical properties (volume expansion of {sup 6}Li for LEM, and freeze seal melting for LIM and LRM). (author)

  1. Development of reconstitution technique of irradiated specimens. 3. Report for FY 1995 and FY 1996 on JAERI-IHI cooperated research program (joint research)

    Nishiyama, Yutaka; Fukaya, Kiyoshi; Onizawa, Kunio; Suzuki, Masahide [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Nakamura, Terumi; Kaihara, Shoichiro; Yoshida, Kazuo; Sato, Akira

    1998-10-01

    The cooperated research between Japan Atomic Energy Research Institute and Ishikawajima-Harima Heavy Industries Co., Ltd. on the development of reconstitution technique of irradiated reactor pressure vessel surveillance specimens has been performed from FY 1993. In FY 1993-1994, the method of surface activated joining (SAJ) was applied to reconstitution of Charpy impact specimens. Some verification tests using unirradiated reactor pressure vessel plate materials have shown that SAJ is feasible for a reconstitution technique, in particular, owing to low joining temperature. The present paper reports the results of the cooperated research performed in FY 1995-1996. To improve the quality of the SAJ, the configuration of the end tab surface to be joined with the insert material was modified. The torque measured during joining was also introduced in joining parameters. A nondestructive inspection, temperature measurements in the specimens during joining were performed. The effect of joining on Charpy impact properties was discussed. For practical application of the technique to irradiated specimens, we confirmed that the impact specimens with joining interface gave rise to no failure at the joining position during impact test after neutron irradiation. (author)

  2. Research on the mechanism of inhibition of stress corrosion cracking by water chemistry of nuclear reactor. JAERI's nuclear research promotion program, H10-004 (contact research)

    Shibata, Toshio; Haruna, Takumi; Fujimoto, Shinji; Zhang, Shenghan

    2000-09-01

    We have developed a slow strain rate testing apparatus combined with a CCD camera system for researching stress corrosion cracking of the materials in high temperature and high pressure water, like nuclear reactor environment. The features of the tensile testing apparatus are the following; pressure up to 100 kg/cm 2 , temperature up to 300degC, and cross head speed down to 10 -5 mm/min. In addition, initiation and propagation of the multiple crack appearing on the material surface in the water at high pressure and high temperature can be clearly observed through a sapphire window penetrating an autoclave. Using the apparatus, we investigated the effects of temperature and species of anion, SO 4 2- and B 4 O 7 2- on the crack initiation and propagation of sensitized 304 stainless steel. The following were revealed: in the sulfate solutions, crack initiation time decreased with increase in temperature from 100 to 250degC, while crack initiation frequency showed maximum at 150degC. In the borate solutions, however, no crack was found on the gauge section of the specimen at any temperatures. This indicates the borate can suppress the initiation of cracks. The effect of anion on the crack initiation may be explained by hardness of anion based on the hard and soft acids and bases concept and the passive film model. (author)

  3. Study on the application of CANDLE burnup strategy to several nuclear reactors. JAERI's nuclear research promotion program, H13-002 (Contract research)

    Kunitomi, Kazuhiko

    2005-03-01

    The CANDLE burnup strategy is a new reactor burnup concept, where the distributions of fuel nuclide densities, neutron flux, and power density move with the same constant speed from bottom to top (or from top to bottom) of the core and without any change in their shapes. Therefore, any burnup control mechanisms are not required, and reactor characteristics do not change along burnup. The reactor is simple and safe. When this burnup scheme is applied to some neutron rich fast reactors, either natural or depleted uranium can be utilized as fresh fuel after second core and the burnup of discharged fuel is about 40%. It means that the nuclear energy can be utilized for many hundreds years without new mining, enrichment and reprocessing, and the amount of spent fuel can be reduced considerably. However, in order to perform such a high fuel burnup some innovative technologies should be developed. Though development of innovative fuel will take a lot of time, intermediate re-cladding may be easy to be employed. Compared to fast reactors, application of CANDLE burnup to prismatic fuel high-temperature gas cooled reactors is very easy. In this report the application of CANDLE burnup to both these types of reactors are studied. (author)

  4. Research on spherically converging ion-beam fusion neutron source for the fundamental research of atomic energy. JAERI's nuclear research promotion program, H10-050. Contract research

    Yoshikawa, Kiyoshi; Inoue, Nobuyuki; Yamazaki, Tetsuo

    2002-03-01

    Potential well formation due to space charge associated with spherically converging ion beams plays a key and essential role in the beam-beam colliding fusion, which is the major mechanism of the Inertial Electrostatic Confinement Fusion (IECF) devices. Many theoretical results so far predicted strongly localized potential well formation, and actually for the past 30 years, many experiments were dedicated to clarify this mechanism, but neither could provide definitive evidence. In this study, we succeeded for the first time in the world in observing the double-well potential profile by use of the laser-induced fluorescence method that makes use of Stark effects, which put a period to the controverse for 30 years on the existence of the double-well potential profile. Furthermore, aiming at demonstrating a numerical prediction of a strongly nonlinear dependence of the fusion reaction rate on the discharge current on negligence of the charge exchange processes, triple-grid auxiliary system was introduced in order to reduce the operating gas pressure, with a successful result of reducing the pressure down to 1/5 of the conventional one required for glow discharge with single-grid system. Also, we measured accelerated atoms' kinetic energies through Doppler shift spectroscopy, and found the maximum energy increases proportionally to the applied voltage, which implies an enhancement of the fusion reaction cross-section with an increasing applied voltage in the near future. (author)

  5. Basic study on the development of low exposure CT with Frisch grid avalanche diode. JAERI's nuclear research promotion program, H13-011 (Contract research)

    Katagiri, Masaki; Onabe, Hideaki

    2005-03-01

    For the development of low exposure CT, we have conducted a basic study on Frisch grid avalanche diode detector to realize a high efficiency, high counting rate X-ray detector. First, we fabricated Frisch grid Si detector made of one crystal and studied their features. For the development of X-ray detector with higher performance, bonding semiconductor wafers, including different semiconductors, such as Si and CdTe, is necessary. We have bonded Si wafers by surface activation method and studied on the electric performance of bonded Si wafers. The current-voltage curve of bonded pn Si wafers showed rectifying characteristics, although Si pn junctions are made by diffusion method, generally. Second, we proposed a low dose exposure X-ray transmission method using filtered X-ray and energy subtraction method. The dose exposure with this method is estimated as low as 30% of that of using white X-rays. If we compare the dose exposure of conventional current measurement method, we would conclude further advantage of this method. With the combination of low dose exposure X-ray transmission method and the Frisch grid detector, high performance X-ray transmission method and low exposure CT system will be developed in future. (author)

  6. Super safe small reactor RAPID-L conceptual design and R and D. JAERI's nuclear research promotion program, H11-002 (Contract research)

    Kambe, Mitsuru; Tsunoda, Hirokazu; Mishima, Kaichiro; Kawasaki, Akira; Iwamura, Takamichi

    2003-03-01

    The 200 kWe uranium nitride fueled lithium cooled fast reactor 'RAPID-L' combined with thermoelectric power conversion system that can be operated unmanned without refueling for up to ten years has been demonstrated. The RAPID refueling concept enables quick and simplified refueling, and achieves plant design lifetime over 20 years. A significant advantage of the RAPID-L design, which does not require the use of control rods - is the introduction of the innovative reactivity control systems: lithium expansion module (LEM), lithium injection module (LIM) and lithium release module (LRM). LEM is the most promising candidate for improving inherent reactivity feedback. LEMs could realize burnup compensation. LIMs assure sufficient negative reactivity feedback in unprotected transients. LRMs enable an automated reactor startup by detecting the hot standby temperature of the primary coolant. All these systems use 6 Li as liquid poison and are actuated by highly reliable physical properties (volume expansion of 6 Li for LEM, and freeze seal melting for LIM and LRM). (author)

  7. Research on nuclear reactor instrumentation system using optical technology. JAERI's nuclear research promotion program, H10-041. Contract research

    Nakazawa, Masaharu; Takahashi, Hiroyuki; Fukuda, Daiji [University of Tokyo, Graduate School of Engineering, Tokyo (Japan)

    2002-03-01

    To apply optical fiber sensing technique to nuclear measurements, we have irradiated the F-doped optical fiber and experimented with two optical fiber sensors: Raman Distributed Temperature Sensor (RDTS) and Fiber Bragg Grating (FBG). We have irradiated F-doped optical fiber, which has high radiation resistivity, with a 60Co gamma source and fast neutron source reactor YAYOI. Although the radiation induced loss with gamma source showed saturation tendency, the loss with YAYOI showed linear loss increase. RDTS has been installed at YAYOI with the correction techniques. During the continuous measurements more than 1 year, the feasibility of RDTS for remote inspection and surveillance was demonstrated. From the result of irradiation experiments on FBG, FBG has high radiation resistivity for a temperature or strain monitor in nuclear plants. For these results, optical fiber sensing can be expected as nuclear measurements. (author)

  8. Verification of in-core thermal and hydraulic analysis code FLOWNET/TRUMP for the high temperature engineering test reactor (HTTR) at JAERI

    Maruyama, Soh; Sudo, Yukio; Saito, Shinzo; Kiso, Yoshihiro; Hayakawa, Hitoshi

    1989-01-01

    The FLOWNET/TRUMP code consists of a flow network analysis code 'FLOWNET' for calculations of coolant flow distribution and coolant temperature distribution in the core with a thermal conduction analysis code 'TRUMP' for calculation of temperature distribution in solid structures. The verification of FLOWNET/TRUMP was made by the comparison of the analytical results with the results of steady state experiments by the HENDEL multichannel test rig, T1-M, which consisted of twelve simulated fuel rods heated electrically and eleven hexagonal graphite fuel blocks. The T1-M simulated the one fuel column in the core. The analytical results agreed well with the results of the experiment in which the HTTR operating conditions were simulated. (orig.)

  9. Activities of working party on 'Subcritical core of accelerator-driven system' under the research committee on reactor physics of AESJ and JAERI

    Iwasaki, T.; Tsujimoto, K.; Nishihara, K.; Kitamura, Y.

    2004-01-01

    The Research Committee on Reactor Physics under the Atomic Energy Society of Japan and the Japan Atomic Energy Research Inst. organized the working party (ADS-WP) on S ubcritical Core of Accelerator-Driven System . The ADS-WP investigated reactor physics of subcriticality from the viewpoint of the accelerator driven system (ADS) since subcriticality has been almost studied from the viewpoint of critical safety. The working party was set in July 2001 and it worked for two years. The activities of the ADS-WP are (Work-I) theory of subcriticality, (Work-II) benchmark of subcritical core, (Work-III) setting of subcriticality level of ADS and (Work-JAO monitoring of subcriticality. These activities clarified about the important issues related to the subcriticality or the subcritical core from the wide ranges of theory, analysis, calculation, design and monitoring for ADS. The activities were already summarized and the report will be published in March 2004. (authors)

  10. Research on the behavior of polonium produced in lead-bismuth eutectic irradiated with neutrons. JAERI's nuclear research promotion program, H10-026. Contract research

    Sekimoto, Hiroshi; Igashira, Masayuki; Yano, Toyohiko; Obara, Toru; Ohsaki, Toshiro

    2002-03-01

    Lead-Bismuth Eutectic (LBE) is proposed by several research institutes as a coolant of liquid metal cooled fast reactors, instead of sodium, and a target of accelerator driven subcritical nuclear reactor systems (ADS). LBE has some advantages that it is chemically inert compared to sodium and that its melting point is low like sodium. A problem might be that bismuth produces polonium, which is an alpha emitter, by irradiation of neutrons. The purpose of the study is to get information for quantitative estimations of the release of polonium on LBE cooled fast reactors and on ADSs by making it clear about production rate of polonium (information about cross section) by neutron irradiation of LBE, release rate of the produced polonium from LBE, and adsorption rate of the polonium on various materials. To get the information about production rate of polonium, neutron cross sections of bismuth were measured in keV energy region, which was important in fast reactors, by using the Pelletron accelerator in Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology. The obtained neutron capture cross sections were from 1/2 to 1/3 of the evaluated values in JENDL and the obtained polonium production cross sections were almost 1/3 of it. At the same time, an experimental device was designed for heating and adsorption experiments and the performance was tested. The performance of alpha spectrometer was tested also. By those the method was established for the measurement of polonium released from melted LBE after neutron irradiation. (author)

  11. Proceedings of the third NUCEF seminar

    NONE

    1998-06-01

    The Third NUCEF Seminar was held at JAERI Tokai Establishment on 24 February 1998. This seminar was planned by researchers in JAERI for effective research promotion and cooperation, and researchers from both the inside and outside of JAERI presented one plenary session and 12 papers in the following three technical sessions: Criticality Safety, Reprocessing and Partitioning, and Radioactive Waste Management. (J.P.N.)

  12. Research on the fundamental process of thermal-hydraulic behaviors in severe accident. Breakup and cooling of molten material jets. JAERI's nuclear research promotion program, H10-027-2. Contract research

    Sugiyama, Ken-ichiro; Iguchi, Kentarou

    2002-03-01

    Core melt accidents could lead to the pouring of molten core materials into a body of water accumulating in the reactor lower head in the form of jets with a few centimeters up to a few tens of centimeters. If molten core jets penetrate the body of water without breakup. A poor coolability of the molten core bed would occur, which means the difficulty of maintaining the molten core bed in the reactor vessel. Hence, the breakup mechanism of molten core jets had to be well understood for the evaluation of the coolability of molten core bed. The objective of the present experimental study is to confirm that, even in molten material jets, the breakup of jet originating in the coolant entrained within a molten material jet due to 'the organized motion' between the coolant and the jet, which has been recognized in the field of fluid mechanics, is caused. The first series of experiment was conducted to observe this type of breakup by using molten tin jets up to 25 mm in diameter. Molten tin jet was expected to easily cause this kind of breakup of jet because of a low kinematic viscosity, which means a easy transformation of jet due to the organized motion for the coolant to entrain. The second series of experiment was conducted by using molten copper jet of 25 mm in diameter, of which kinematic viscosity is about same as that of molten UO 2 . The breakup of jet due to the entrainment of the coolant was observed up to high ambient Weber numbers, which cover the atomization regime. The mechanism of the breakup observed in the present study is able to reasonably explain the apparent difference between the breakup lengths of 150 kg-scale corium jets and the breakup lengths of about 8 kg-scale lead-bismuth alloy jets. The breakup by the mechanism reported here also assures a high coolability of molten jets because of an efficient entrainment of coolant within the jet. (author)

  13. Cooperative research at JAERI on the consequences of the Chernobyl accident. 3. Distribution and migration characteristics of long-lived radionuclides in the environment around the damaged Chernobyl reactor

    Amano, Hikaru

    2001-01-01

    The purpose of this study was to elucidate the actual long-term migration characteristics of radionuclides released and accumulated on the earth surface environment after the reactor accident. The objective areas were mainly in 30 km distant areas from the reactor. The study concerned the distribution of radionuclides on the ground surface, their physical and chemical forms, their migration characteristics, their migration from the ground to aqueous system like river, their physical and chemical forms in that system, their migration into vegetables, and their re-floating and concentration in air. The study involved those methods such as a newly developed liquid scintillation counting of 241 Pu for assessing 241 Am accumulation and the alpha-track method for detection of hot particles. Findings were: Hot particles of small diameters around several microns were still present; Depth distribution of radionuclides was dependent on the soil sort; Chemical forms of 90 Sr, 137 Cs and transuranium elements were different; Depth distribution in the soil depended on chemical forms; Annual change of radionuclides was evident in air; Migration coefficients to vegetables were determined; High molecular weight organic colloid was important in the migration to water system; Amounts of 137 Cs and transuranium elements depended on those of suspended matters in the river water and >90% 90 Sr were in soluble forms; Apparent partition ratios (soluble/suspended) of radionuclides in the river and lake were determined; Soluble transuranium elements were bound to humus materials in the river. (K.H.)

  14. Chaotic behavior in a system simulating the pressure balanced injection system. Analysis of passive safety reactor behavior. JAERI's nuclear research promotion program, H12-012 (Contract research)

    Madarame, Haruki; Okamoto, Koji; Tanaka, Gentaro; Morimoto, Yuichiro [Tokyo Univ., School of Engineering, Tokyo (Japan); Sato, Akira [Yamagata Univ., Faculty of Engineering, Yonezawa, Yamagata (Japan); Kondou, Masaya [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2003-03-01

    The pressure Balanced Injection System (PBIS) was proposed in a passive safety reactor. Pressurizing Line (PL) connects the Reactor Vessel (RV) and the gas area in the Contain Vessel (CV), and Injected Line (IL) connects two vessels at relatively lower position. In an accident, the two lines are passively opened. The vapor generated by the residual heat pressed downward the water level in the RV. When the level is lower than the inlet of the PL, vapor is ejected into the CV through the PL attaining the pressure balance between the vessels. Then boron water in the CV is injected into the RV through the IL by the static head. This process is repeated by the succeeding vapor generation. In an experiment, the oscillating system was replaced by water column in a U-shaped duct. The vapor generation was simulated by cover gas supply to one end of the duct, while the other end was open to the atmosphere. When the water level reached a certain level, electromagnetic valves opened and the cover gas was ejected. The gas pressure decreased rapidly, resulting in a surface rise. When the water level reached another level, the valves closed. The cover gas pressure increased again, thus, gas ejection occurred intermittently. The interval of the gas ejection was not constant but fluctuated widely. Mere stochastic noise could hardly explain the large amplitude. Then was expressed the system using a set of linear equations. Various types of piecewise linear model were developed to examine the cause of the fluctuation. There appeared tangential bifurcation, period-doubling bifurcation, period-adding bifurcation and so on. The calculated interval exhibited chaotic features. Thus the cause of the fluctuation can be attributed to chaotic features of the system having switching. Since the piecewise linear model was highly simplified the behavior, a quantitative comparison between the calculation and the experiment was difficult. Therefore, numerical simulation code considering nonlinear effect was developed to describe the system behavior in the case there was no stochastic noise. The comparison between the simulation and the experiment revealed that there are some bifurcation-like phenomena being not real bifurcations. Real bifurcations are discovered in the simulation as well as in the experiment. Confirmation of chaotic behavior of the system in the experiment is a subject for a future study. (author)

  15. Research on the fundamental process of thermal-hydraulic behaviors in severe accident. Breakup and cooling of molten material jets. JAERI's nuclear research promotion program, H10-027-2. Contract research

    Sugiyama, Ken-ichiro; Iguchi, Kentarou [Hokkaido Univ., Graduate School of Engineering, Sapporo, Hokkaido (Japan)

    2002-03-01

    Core melt accidents could lead to the pouring of molten core materials into a body of water accumulating in the reactor lower head in the form of jets with a few centimeters up to a few tens of centimeters. If molten core jets penetrate the body of water without breakup. A poor coolability of the molten core bed would occur, which means the difficulty of maintaining the molten core bed in the reactor vessel. Hence, the breakup mechanism of molten core jets had to be well understood for the evaluation of the coolability of molten core bed. The objective of the present experimental study is to confirm that, even in molten material jets, the breakup of jet originating in the coolant entrained within a molten material jet due to 'the organized motion' between the coolant and the jet, which has been recognized in the field of fluid mechanics, is caused. The first series of experiment was conducted to observe this type of breakup by using molten tin jets up to 25 mm in diameter. Molten tin jet was expected to easily cause this kind of breakup of jet because of a low kinematic viscosity, which means a easy transformation of jet due to the organized motion for the coolant to entrain. The second series of experiment was conducted by using molten copper jet of 25 mm in diameter, of which kinematic viscosity is about same as that of molten UO{sub 2}. The breakup of jet due to the entrainment of the coolant was observed up to high ambient Weber numbers, which cover the atomization regime. The mechanism of the breakup observed in the present study is able to reasonably explain the apparent difference between the breakup lengths of 150 kg-scale corium jets and the breakup lengths of about 8 kg-scale lead-bismuth alloy jets. The breakup by the mechanism reported here also assures a high coolability of molten jets because of an efficient entrainment of coolant within the jet. (author)

  16. Liquid-solid interface project in nuclear engineering. Systematization of sorption theory in heterogeneous surface and it's application to radioactive waste disposal. JAERI's nuclear research promotion program, H10-032. Contract research

    Tanaka, Satoru [Tokyo Univ., Graduate School of Engineering, Tokyo (Japan)

    2002-03-01

    Combining of the In-Situ and Ex-situ experiments with quantum chemical calculation, we can draw the following conclusions on the sorption at heterogeneous interfaces, based on the structure of solid surfaces and the profile of charge/electron at surface: (1) Redox sensitive species Np(V) is reduced to Np(IV) by Fe(II) contained in iron oxides. (2) Interactions of ions with C-S-H gels, which is a main component of cementitious materials, consist of replacement of Ca, association with Si and ion exchange. (3) Iodate ions adsorb on the two kinds of sorption sites located on the outer surface of hydrotalcite. (4) Interaction potential between particles and solid surfaces decrease due to the microscopic roughness of solid surface and localized distribution of charge on the surface, leading to the increase in the deposition of particles. (5) Some information on the association situation of water molecules on the metal oxides are obtained. These results suggests that the microscopic heterogeneity of solid surfaces facilities the interaction of ions and particles with solid surfaces. These phenomena can not be explained by the conventional sorption theory. We have to develop the sorption theory by considering the interactions from the microscopic point of view. (author)

  17. Research on the fundamental process of thermal-hydraulic behaviors in severe accident. Behavior of fine droplet flow. JAERI's nuclear research promotion program, H10-027-7. Contract research

    Kataoka, Isao; Yoshida, Kenji; Matsuura, Keizo

    2002-03-01

    Analytical and experimental researches were carried out on the behavior of fine droplet flow in relation to the fundamental phenomena of thermohydraulics in severe accident. Simulation program of fine droplet behavior in turbulent gas flow was developed based on the eddy interaction model with improvement of Graham's stochastic model on eddy lifetime and eddy size. Furthermore, the developed program are capable of simulating the droplet behavior in annular dispersed flow based on the models of droplet entrainment from liquid film and turbulence modification of gas phase by liquid film. This program was confirmed by the various experimental data on droplet diffusion, deposition. Furthermore, this program was applied to the three dimensional droplet flow with the satisfactory agreement of experimental data. This means the developed program can be used as a simulation program for analysis of severe accident. Experimental research was carried out on the effect of liquid film on the turbulence field of gas flow in annular and annular dispersed flow. Averaged and turbulent velocity of gas phase were measured under various gas and liquid film flow rates. Turbulent velocity of gas phase in annular flow increased compared with single phase gas flow. This is due to turbulence generation by waves in liquid film. Corresponding to the turbulence modification by liquid film, distribution of averaged velocity of gas phase became flattened compared with single phase gas flow. (author)

  18. Research on the fundamental process of thermal-hydraulic behaviors in severe accident. Estimation of trigger condition for vapor explosion. JAERI's nuclear research promotion program, H10-027-1. Contract research

    Nariai, Hideki

    2002-03-01

    The experimental and analytical researches were conducted to study melted core material and coolant interaction including solidification and vapor explosion which is one of the most unidentified thermal hydraulic phenomena during sever accident of nuclear reactor. At first, the effect of the material properties on vapor explosion and solidification was examined to clarify the dominant factors for the spontaneous vapor explosion. Next, the interfacial phenomena of the high temperature melt material and violent boiling behavior of water at the interface was visually observed in the experiment. The interfacial phenomena were physically modeled. Finally, trigger phenomena from liquid-liquid contact to atomization were clarified through the forced collapse experiment of vapor film around a molten droplet by using pressure wave generation device. It is indicated by applying the results obtained in the present study to the actual reactor conditions that the possibility of the vapor explosion is extremely unlikely in the actual reactor accident sequence, since the surface of the molten uranium oxide is solidified in the water and the liquid-liquid contact can not be achieved. It should be noted that the decrease of the solidified temperature by metal compounds and the increase of the molten core temperature. (author)

  19. Fundamental research on positive systems of waste disposal and environmental protection using redox reaction and enriching ability of iron for pollutant. JAERI's nuclear research promotion program, H11-003. Contract research

    Ohashi, Hiroshi; Sato, Seichi; Kozaki, Tamotsu

    2002-03-01

    Iron corrosion products have a potential ability to retard the transport of pollutant in soil by sorption, co-precipitation and redox reaction. In this research program, an electrokinetic soil treatment method using iron anode, which can remove the pollutant and form an iron corrosion product layer in soil, was proposed as a new promising environmental remediation technique for contaminated soil with toxic heavy metal, organic materials and/or radioactive nuclides. As a fundamental study of the electrokinetic soil treatment, the formation mechanism of the corrosion product layer was discussed with the experimental data of the ion migration and the time dependence of the electric current during the treatment. In addition, diffusion behavior of Na + ions and He gas in the clay, which are closely related to the treatment, were studied. Furthermore, the potential ability of the iron corrosion layer to retard the transport of pollutant in soil was evaluated in terms of sorption coefficient of Se and Np onto the iron corrosion products and Fe-montmorillonite, which are the major component of the iron corrosion product layer. As results of these studies, it was confirmed that the electrokinetic soil treatment method using iron anode is one of promising environmental remediation techniques for contaminated soil. (author)

  20. Research on the fundamental process of thermal-hydraulic behaviors in severe accident. Vapor film collapse behavior on high temperature particle surface. JAERI's nuclear research promotion program, H10-027-3. Contract research

    Abe, Yutaka

    2002-03-01

    The experimental researches were conducted to study vapor film collapse behavior on high temperature melted core material coarsely mixed in the coolant under the film boiling condition. The film collapse is very important incipient incident of the trigger process for the vapor explosion in sever accident of nuclear reactor. In the experiment, pressure pulse was applied to the vapor film on a high temperature particle surface simulating melted core material to observed microscopic vapor film collapse behavior with a high-speed video camera of 40,500 fps. The particle surface temperature and pressure around the particle were simultaneously measured. The transition of the vapor film thickness and two-dimensional vapor-liquid interface movement and the velocity were estimated with visual data analysis technique, PIV and digital data analysis technique. Furthermore, heat conduction analysis was performed to estimate the vapor-liquid interfacial temperature with the measured temperature and estimated vapor film thickness. As the results, it was clarified that the vapor-liquid interface changed white from transparent view for all the experimental conditions. It is also clarified that the vapor-liquid interfacial temperature decreased under the saturation temperature when the pressure pulse arrive at the particle. The experimental facts indicates the possibility that the vapor film collapse occurs due to the liquid phase homogeneous moving toward the particle drove by the pressure reduction caused by the phase change inside the vapor film. (author)

  1. Liquid-solid interface project in nuclear engineering. Systematization of sorption theory in heterogeneous surface and it's application to radioactive waste disposal. JAERI's nuclear research promotion program, H10-032. Contract research

    Tanaka, Satoru

    2002-03-01

    Combining of the In-Situ and Ex-situ experiments with quantum chemical calculation, we can draw the following conclusions on the sorption at heterogeneous interfaces, based on the structure of solid surfaces and the profile of charge/electron at surface: (1) Redox sensitive species Np(V) is reduced to Np(IV) by Fe(II) contained in iron oxides. (2) Interactions of ions with C-S-H gels, which is a main component of cementitious materials, consist of replacement of Ca, association with Si and ion exchange. (3) Iodate ions adsorb on the two kinds of sorption sites located on the outer surface of hydrotalcite. (4) Interaction potential between particles and solid surfaces decrease due to the microscopic roughness of solid surface and localized distribution of charge on the surface, leading to the increase in the deposition of particles. (5) Some information on the association situation of water molecules on the metal oxides are obtained. These results suggests that the microscopic heterogeneity of solid surfaces facilities the interaction of ions and particles with solid surfaces. These phenomena can not be explained by the conventional sorption theory. We have to develop the sorption theory by considering the interactions from the microscopic point of view. (author)

  2. Research on the fundamental process of thermal-hydraulic behaviors in severe accident. Heat transfer on the liquid-liquid interface between molten core pool and coolant. JAERI's nuclear research promotion program, H10-027-6. Contract research

    Mishima, Kaichiro; Saito, Yasushi

    2002-03-01

    Heat transfer experiments under steady and transient conditions were performed using molten Wood's metal and distilled water to study heat transfer on the liquid-liquid interface between molten fuel pool and coolant under severe accident conditions. In the steady state experiment, boiling curve was measured over the range from natural convection region to film boiling region. The boiling behavior was observed using a high-speed video camera. In the transient experiment, distilled water was poured onto the hot molten metal surface, and the boiling curve was obtained in the cooling process. Comparing the measured boiling curve with existing correlations and experimental data for solid-liquid and liquid-liquid systems, the following conclusions were drawn: (a) When the interface surge is negligible and oxide layer is formed on the interface, the boiling curve at the liquid-liquid surface could be approximately reproduced by the heat transfer correlations for nucleate boiling and film boiling regions and the critical heat flux correlation for a liquid-solid system. (b) When no oxide layer is formed on the interface, the boiling curve at the liquid-liquid surface moved towards higher wall superheat than that at the liquid-solid surface, as Novakovic et al. observed in their experiment using mercury. (c) Transient heat transfer coefficient for film boiling at the liquid-liquid surface was about 100% higher than that predicted by the heat transfer correlation for a solid-liquid system. (author)

  3. Research on the fundamental process of thermal-hydraulic behaviors in severe accident. Behavior of fine droplet flow. JAERI's nuclear research promotion program, H10-027-7. Contract research

    Kataoka, Isao; Yoshida, Kenji [Osaka Univ., Graduate School of Engineering, Osaka (Japan); Matsuura, Keizo [Nuclear Fuel Industry, Co., Ltd., Tokyo (Japan)

    2002-03-01

    Analytical and experimental researches were carried out on the behavior of fine droplet flow in relation to the fundamental phenomena of thermohydraulics in severe accident. Simulation program of fine droplet behavior in turbulent gas flow was developed based on the eddy interaction model with improvement of Graham's stochastic model on eddy lifetime and eddy size. Furthermore, the developed program are capable of simulating the droplet behavior in annular dispersed flow based on the models of droplet entrainment from liquid film and turbulence modification of gas phase by liquid film. This program was confirmed by the various experimental data on droplet diffusion, deposition. Furthermore, this program was applied to the three dimensional droplet flow with the satisfactory agreement of experimental data. This means the developed program can be used as a simulation program for analysis of severe accident. Experimental research was carried out on the effect of liquid film on the turbulence field of gas flow in annular and annular dispersed flow. Averaged and turbulent velocity of gas phase were measured under various gas and liquid film flow rates. Turbulent velocity of gas phase in annular flow increased compared with single phase gas flow. This is due to turbulence generation by waves in liquid film. Corresponding to the turbulence modification by liquid film, distribution of averaged velocity of gas phase became flattened compared with single phase gas flow. (author)

  4. Research on the fundamental process of thermal-hydraulic behaviors in severe accident. Estimation of trigger condition for vapor explosion. JAERI's nuclear research promotion program, H10-027-1. Contract research

    Nariai, Hideki [Tsukuba Univ., Institute of Engineering Mechanics and Systems, Tsukuba, Ibaraki (Japan)

    2002-03-01

    The experimental and analytical researches were conducted to study melted core material and coolant interaction including solidification and vapor explosion which is one of the most unidentified thermal hydraulic phenomena during sever accident of nuclear reactor. At first, the effect of the material properties on vapor explosion and solidification was examined to clarify the dominant factors for the spontaneous vapor explosion. Next, the interfacial phenomena of the high temperature melt material and violent boiling behavior of water at the interface was visually observed in the experiment. The interfacial phenomena were physically modeled. Finally, trigger phenomena from liquid-liquid contact to atomization were clarified through the forced collapse experiment of vapor film around a molten droplet by using pressure wave generation device. It is indicated by applying the results obtained in the present study to the actual reactor conditions that the possibility of the vapor explosion is extremely unlikely in the actual reactor accident sequence, since the surface of the molten uranium oxide is solidified in the water and the liquid-liquid contact can not be achieved. It should be noted that the decrease of the solidified temperature by metal compounds and the increase of the molten core temperature. (author)

  5. Research on the fundamental process of thermal-hydraulic behaviors in severe accident. Vapor film collapse behavior on high temperature particle surface. JAERI's nuclear research promotion program, H10-027-3. Contract research

    Abe, Yutaka [Tsukuba Univ., Institute of Engineering Mechanics and Systems, Tsukuba, Ibaraki (Japan)

    2002-03-01

    The experimental researches were conducted to study vapor film collapse behavior on high temperature melted core material coarsely mixed in the coolant under the film boiling condition. The film collapse is very important incipient incident of the trigger process for the vapor explosion in sever accident of nuclear reactor. In the experiment, pressure pulse was applied to the vapor film on a high temperature particle surface simulating melted core material to observed microscopic vapor film collapse behavior with a high-speed video camera of 40,500 fps. The particle surface temperature and pressure around the particle were simultaneously measured. The transition of the vapor film thickness and two-dimensional vapor-liquid interface movement and the velocity were estimated with visual data analysis technique, PIV and digital data analysis technique. Furthermore, heat conduction analysis was performed to estimate the vapor-liquid interfacial temperature with the measured temperature and estimated vapor film thickness. As the results, it was clarified that the vapor-liquid interface changed white from transparent view for all the experimental conditions. It is also clarified that the vapor-liquid interfacial temperature decreased under the saturation temperature when the pressure pulse arrive at the particle. The experimental facts indicates the possibility that the vapor film collapse occurs due to the liquid phase homogeneous moving toward the particle drove by the pressure reduction caused by the phase change inside the vapor film. (author)

  6. The joint project for high-intensity proton accelerators

    NONE

    1999-08-01

    Japan Atomic Energy Research Institute (JAERI) and the High Energy Accelerator Research Organization (KEK) agreed to promote the joint project integrating both the Neutron Science Project (NSP) of JAERI and the Japan Hadron Facility Project (JHF) of KEK for comprehensive studies on basic science and technology using high-intensity proton accelerator. This document describes the joint proposal prepared by the Joint Project Team of JAERI and KEK to construct accelerators and research facilities necessary both for the NSP and the JHF at the site of JAERI Tokai Establishment. (author)

  7. Progress of nuclear safety research. 2001

    Anoda, Yoshinari; Sasajima, Hideo; Nishiyama, Yutaka (eds.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] [and others

    2001-10-01

    JAERI is conducting nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy or the Safety Research Annual Plan issued by the Japanese government. The safety research at JAERI concerns the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI has conducted international collaboration to share the information on common global issues of nuclear safety. This report summarizes the nuclear safety research activities of JAERI from April 1999 through March 2001. (author)

  8. Progress report on neutron science. April 1, 2003 - March 31, 2004

    Matsuda, Masaaki; Kurihara, Kazuo; Moriai, Atsushi

    2005-03-01

    This issue summarizes research progress in neutron science at Japan Atomic Energy Research Institute (JAERI) by utilizing the research reactor JRR-3 during the period between April 1, 2003 and March 31, 2004. This report contains highlights in research from 10 neutron research groups at JAERI and summary reports of 82 papers. (author)

  9. Actinides compounds for the transmutation: scientific contributions of american and japanese collaborations; Composes d'actinides pour la transmutation: apports scientifiques de collaborations americaines et japonaises

    Raison, Ph.; Albiot, T

    2000-07-01

    This paper deals with the minor actinides transmutation and the scientific contribution of the ORNL and the JAERI. It presents researches on the Am-Zr-Y-O system in the framework of the heterogeneous reprocessing, the curium and pyrochlore structures, with the ORNL contribution and phase diagrams, data of Thermodynamics, actinides nitrides, with the JAERI. (A.L.B.)

  10. Progress report on neutron science. April 1, 2004 - March 31, 2005

    Kurihara, Kazuo; Moriai, Atsushi; Matsuda, Masaaki

    2005-09-01

    This issue summarizes research progress in neutron science at Japan Atomic Energy Research Institute (JAERI) by utilizing the research reactor JRR-3 during the period between April 1, 2004 and March 31, 2005. This report contains highlights in research by 13 neutron research groups at JAERI and 91 summary articles. (author)

  11. Completion of the ITER central solenoid model coils installation

    Tsuji, H.

    1999-01-01

    The short article details how dozens of problems, regarding the central solenoid model coils installation, were faced and successfully overcome one by one at JAERI-Naga. A black and white photograph shows K. Kwano, a staff member of the JAERI superconducting magnet laboratory, to be still inside the vacuum tank while the lid is already being brought down..

  12. Design and safety data of commercial nuclear power plants in Japan, 1977 edition

    Izumi, Fumio; Harayama, Yasuo

    1977-09-01

    Following on previous JAERI-M 5959(1975) and JAERI-M 6732(1976), which contained the data for design parameters, performance, components and equipments of Japanese nuclear power plants, the 1977 updated edition is compiled as of June 1977. The data are arranged and tabulated by computer processing. (auth.)

  13. Actinides compounds for the transmutation: scientific contributions of american and japanese collaborations

    Raison, Ph.; Albiot, T.

    2000-01-01

    This paper deals with the minor actinides transmutation and the scientific contribution of the ORNL and the JAERI. It presents researches on the Am-Zr-Y-O system in the framework of the heterogeneous reprocessing, the curium and pyrochlore structures, with the ORNL contribution and phase diagrams, data of Thermodynamics, actinides nitrides, with the JAERI. (A.L.B.)

  14. Design and safety data of commercial nuclear power plants in Japan

    Izumi, Fumio; Harayama, Yasuo; Nakazima, Tetuo

    1979-02-01

    Following the previous JAERI-M 6732(1976) and JAERI-M 7261(1977), the 1978 edition as of the December is presented, which contains the data of design parameters, performance, components and equipments in nuclear power plants of Japan. Data are given in tables by computer processing. (author)

  15. Progress of nuclear safety research-2004

    Anoda, Yoshinari; Ebine, Noriya; Chuto, Toshinori; Sato, Satoshi; Ishikawa, Jun; Yamamoto, Toshihiro; Munakata, Masahiro; Asakura, Toshihide; Yamaguchi, Tetsuji; Kida, Takashi; Matsui, Hiroki; Haneishi, Akihiro; Araya, Fumimasa

    2005-03-01

    JAERI is conducting nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy and Annual Plan for Safety Research issued by the Japanese government. The fields of conducting safety research at JAERI are the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI has conducted international collaboration to share the information on common global issues of nuclear safety and to supplement own research. Moreover, when accidents occurred at nuclear facilities, JAERI has taken a responsible role by providing technical experts and investigation for assistance to the government or local public body. This report summarizes the nuclear safety research activities of JAERI from April 2002 through March 2004 and utilized facilities. (author)

  16. Studies on formation and structures of ultrafine Cu precipitates in Fe-Cu model alloys for reactor pressure vessel steels using positron quantum dot confinement in the precipitates by their positron affinity. JAERI's nuclear research promotion program, H11-034 (Contract research)

    Hasegawa, Masayuki; Nagai, Yasuyoshi; Tang, Zheng; Yubuta, Kunio [Tohoku Univ., Sendai (Japan). Inst. for Materials Research; Suzuki, Masahide [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2003-03-01

    Positron annihilation experiments on Fe-Cu model dilute alloys of nuclear reactor pressure vessel (RPV) steels have been performed after neutron irradiation in JMTR. Nanovoids whose inner surfaces were covered by Cu atoms were clearly observed. The nanovoids transformed to ultrafine Cu precipitates by dissociating their vacancies after annealing at around 400degC. The nanovoids and the ultrafine Cu precipitates are strongly suggested to be responsible for irradiation-induced embrittlement of RPV steels. Effects of Ni, Mn and P addition on the nanovoid and Cu precipitate formations were also studied. The nanovoid formation was enhanced by Ni and P, but suppressed by Mn. The Cu precipitates after annealing around 400degC were almost free from these doping elements and hence were pure Cu in the chemical composition. Furthermore the Fermi surface of the 'embedded' Cu precipitates with a body centered cubic crystal structure was obtained from two dimensional angular correlation of annihilation radiation (2D-ACAR) in a Fe-Cu single crystal and was agreed well with that from a band structure calculation. Theoretical calculation of positron confinement in Fe-Cu model alloys showed that a positron quantum dot state induced by positron affinity is attained for the embedded precipitates larger than 1 nm. A new position sensitive detector with a function of one dimensional angular correlation of annihilation radiation (1D-ACAR) has been developed that enables high resolution experiments over wide ranges of momentum distribution. (author)

  17. Research on cooling of ultra high critical heat flux with external flow boiling of water. Challenge to achieve ultra high critical heat flux and improvement in estimation of critical heat flux. JAERI's nuclear research promotion program, H11-004 (Contract research)

    Monde, Masanori; Mitsutake, Yuichi; Ishida, Kenji; Hino, Ryutaro

    2003-03-01

    An ultra high critical heat flux (CHF) has been challenged with a highly subcooled water jet impinging on a small rectangular heated surface. Major objective of the study is to achieve an ultra high heat flux cooling as large as 100 MW/m 2 and to establish an accurate estimation method of the CHF. The experiments were carried out over the experimental range; a fixed jet diameter of 2 mm, jet velocity of 5 - 35 m/s, degree of subcooling of 80 - 170 K and system pressure of 0.1 - 1.0 MPa. The rectangular heated surface with a thin nickel foil of 0.03 - 0.3 mm in thickness, 5 and 10 mm in length, and 4 mm in width and heated by a direct current. Effects of thickness of heater wall, jet velocity and subcooling on the CHF were experimentally elucidated. The experimental results show that the CHF decreases about 50% as the heater thickness, namely heat capacity of heater decreases. Characteristics of the CHF with heater length of 10 mm are correlated within ±20% by the generalized correlation of subcooled CHF proposed by the authors. However, the CHF with the shorter heater length of 5 mm shows large deviation of -40% especially at lower subcooling and higher velocity. The maximum CHF of 212 MW/m 2 was achieved at the subcooling of 151 K, the jet velocity of 35 m/s and system pressure of 0.5 MPa. The maximum CHF under atmospheric pressure approaches to 48% of the ultimate maximum heat flux given by the assumptions that vapor molecules leave a liquid-vapor interface at the average speed of a Boltzman-Maxwellian gas and any molecules returning to the interface are not permitted. The ratio of the CHF and ultimate maximum heat flux was considerably enhanced from the existing record of 30%. This study can give the feasibility of ultra high heat flux removal facing in a development of components such as a diverter of a fusion reactor. (author)

  18. The achivements of Japanese fuel irradiation experiments in HBWR

    Ichikawa, Michio; Yanagisawa, Kazuaki; Domoto, Kazunari

    1984-02-01

    OECD Halden Reactor Project celebrated the 25th anniversary in 1983. The JAERI has been participating in the Project since 1967 on behalf of Japanese Government. Since the participation, thirty-six Japanese instrumented fuel assemblies have been irradiated in HBWR. The irradiation experiments were either sponsored by JAERI or by domestic organizations under the joint research agreements with JAERI, beeing steered by the Committee for the Joint Research Programme. The cooperative efforts have attained significant contributions to the development of water reactor fuel technology in Japan. This report review the irradiation experiments of Japanese fuel assemblies. (author)

  19. Proceedings of the 1st symposium on advanced science research

    1995-09-01

    The 1st symposium on advanced science research was held in Tokai-mura, Ibaraki-ken, on 23-24 March, 1995, under the auspices of JAERI. Two hundred and sixty scientists attended the symposium; over 40% of the attendants were from universities and laboratories outside JAERI. This proceedings consists of 6 oral presentations of the research activities in the Advanced Science Research Center, 70 poster presentations on the field of basic science from both the inside and outside of JAERI and 2 panel discussions on the actinide physics and biocrystallography. (author)

  20. Report of the joint seminar on heavy-ion nuclear physics and nuclear chemistry in the energy region of tandem accelerators (II)

    1986-04-01

    A meeting of the second joint seminar on Heavy-Ion Nuclear Physics and Nuclear Chemistry in the Energy Region of Tandem Accelerators was held after an interval of two years at the Tokai Research Establishment of the JAERI, for three days from January 9 to 11, 1986. In the seminar, about 70 nuclear physicists and nuclear chemists of JAERI and other Institutes participated, and 38 papers were presented. These include general reviews and topical subjects which have been developed intensively in recent years, as well as the new results obtained by using the JAERI tandem accelerator. This report is a collection of the papers presented to the seminar. (author)

  1. Study on decay of rare earth nuclei produced by fission

    Kawade, Kiyoshi; Yamamoto, Hiroshi; Shibata, Michihiro; Asai, Masato [Nagoya Univ. (Japan); Tsukada, Kazuaki; Osa, Akihiko; Shinohara, Nobuo; Iimura, Hideki

    1996-01-01

    JAERI-ISOL utilizes charge particle induced fission by proton and heavy proton produced by the tandem type accelerator (JAERI). To study the decay mechanism and nuclei structure of neutron and excess nuclei produced by actinoid fission, JAERI-ISOL was improved by developing the multilayer target tank. So that, the intensity of mass separated ion beam increased enough to use. New 76.6 KeV {gamma}-ray with about 10s of half life was found in the preliminary experiment. (S.Y.)

  2. Progress report on neutron scattering research. April 1, 1999 - March 31, 2000

    Fujiwara, Satoru; Aizawa, Kazuya; Katano, Susumu (eds.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2001-03-01

    This issue summarizes research progress in neutron scattering at Japan Atomic Energy Research Institute (JAERI) by utilizing the research reactor (JRR-3M) during the period between April 1, 1999 and March 31, 2000. (author)

  3. Experimental SGU background and in sodium water leak noise data provided by the Electricite de France R and D organization for IAEA benchmark tapes

    Jouneau, C.

    1997-01-01

    The paper describes the data which have been provided to Mr. Shinohara (JAERI) and which have served to generate the Fourth Stage Analysis Benchmark Test Tapes distributed in August 1993. (author). 2 refs, 3 figs

  4. Summary of IAEA technical committee meeting on impurity control

    Itoh, Kimitaka.

    1989-03-01

    Presentations given in the IAEA technical committee meeting on impurity control (held in JAERI from 13 to 15 February, 1989) are summarized, putting the emphasis on the physics modelling of the plasma related to the impurity production and confinement. (author)

  5. Progress report on neutron scattering research. April 1, 2002 - March 31, 2003

    Koizumi, Satoshi; Matsuda, Masaaki; Kurihara, Kazuo

    2004-03-01

    This issue summarizes research progress in neutron scattering at Japan Atomic Energy Research Institute (JAERI) by utilizing the research reactor JRR-3 during the period between April 1, 2002 and March 31, 2003. (author)

  6. Progress report on neutron scattering research (April 1, 1998 - March 31, 1999)

    Suzuki, Jun-ichi; Fujiwara, Satoru; Aizawa, Kazuya [eds.] [Advanced Science Research Center (Tokai Site), Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)

    2000-03-01

    The present issue summarizes research progress in neutron scattering at Japan Atomic Energy Research Institute (JAERI) by utilizing the research reactor (JRR-3M) during the period between April 1, 1998 and March 31, 1999. (author)

  7. Progress report on neutron scattering research. April 1, 2001 - March 31, 2002

    Katano, Susumu; Koizumi, Satoshi; Matsuda, Masaaki (eds.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2002-11-01

    This issue summarizes research progress in neutron scattering at Japan Atomic Energy Research Institute (JAERI) by utilizing the research reactor JRR-3M during the period between April 1, 2001 and March 31, 2002. (author)

  8. Progress report on neutron scattering research. April 1, 2000 - March 31, 2001

    Aizawa, Kazuya; Katano, Susumu; Koizumi, Satoshi

    2002-03-01

    This issue summarizes research progress in neutron scattering at Japan Atomic Energy Research Institute (JAERI) by utilizing the research reactor (JRR-3M) during the period between April 1, 2000 and March 31, 2001. (author)

  9. International cooperation in the field of radiation application

    Sato, Shoichi

    1993-01-01

    Bilateral and multilateral research cooperations have been implemented at TRCRE, JAERI, producing favourable results in the field of radiation application. Frameworks and some achievements are described and the significance of the international cooperation is discussed. (Author)

  10. Pramana – Journal of Physics | Indian Academy of Sciences

    Author Affiliations. I Tanaka1 2. Neutron Science Research Center, Japan Atomic Energy Research Institute (JAERI), Tokai, Ibaraki 319-1195, Japan; Faculty of Engineering, Ibaraki University, Hitachi, Ibaraki 316-8511, Japan ...

  11. ITER EDA newsletter. V. 6, no. 12

    1997-12-01

    This issue of the ITER Newsletter contains summary reports (i) on the Sixth ITER Technical Meeting on Safety and Environment and (ii) on JAERI's Annual Public Seminar on Fusion Research and Development

  12. Conceptual design of SC magnet system for ITER, (5)

    Nakajima, Hideo; Nishi, Masataka; Yoshida, Kiyoshi; Tsuji, Hiroshi; Egusa, Shigenori; Seguchi, Tadao; Hagiwara, Miyuki; Kirk, M.A.; Birtcher, R.C.

    1991-08-01

    Japan Atomic Energy Research Institute (JAERI) has been developing a superconducting magnet system for a fusion reactor. One of the key items in developing the superconducting magnets is material development and evaluation. The data of superconducting materials, structural alloys, and non-metallic materials are generated to establish a material data base at JAERI. This report is prepared to provide available data generated by JAERI to designers of superconducting magnets throughout the world. The following review papers written for the International Thermonuclear Experimental Reactor (ITER) report on conceptual design of magnet system are combined here. I. Superconducting Material Data II. Mechanical Properties of the Japanese Cryogenic Steels (JCS) at Cryogenic Temperature III. Review of Radiation Degradation Studies at JAERI on Composite Organic Insulators Used in Fusion Magnets (author)

  13. Annual report of the Osaka Laboratory for Radiation Chemistry, Japan Atomic Energy Research Institute (no.19)

    1987-03-01

    This report describes research activities of Osaka Laboratory for Radiation Chemistry, JAERI during one year period from April 1, 1985 through March 31, 1986. The latest report, for 1984, is JAERI-M 86-051. Detailed descriptions of the activities are presented in the following subjects: studies on surface phenomena under electron and ion irradiations; polymerization under the irradiation of electron beams; modification of polymers, degradation, cross-linking, and grafting. (author)

  14. Annual report of Naka Fusion Research Establishment from April 1, 2001 to March 31, 2002

    Ando, Toshiro; Matsumoto, Hiroshi; Moriyama, Shinichi; Tanaka, Fumiya; Tuda, Takashi; Tsuji, Hiroshi (eds.) [Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment

    2002-11-01

    This report provides an overview of research and development activities at Naka Fusion Research Establishment, JAERI, including those performed in collaboration with other research establishments of JAERI, during the period from April 1, 2001 to March 31, 2002. The activities in the Naka Fusion Research Establishment are highlighted by high performance plasma researches in JT-60 and JFT-2M, and completion of ITER Engineering Design Activities (EDA) in July 2001, including technology R and D. (J.P.N.)

  15. Proceedings of the 8th topical meeting on nuclear code development

    1993-03-01

    The 8th Topical Meeting on Nuclear Code Development, organized by Committee on Reactor Physics and Nuclear Codes Committee of Japan Atomic Energy Research Institute (JAERI), was held at Tokai Research Establishment of JAERI, on 11th and 12th of November, 1992. In the meeting, 14 papers were presented on the topics of (1) the next generation nuclear reactor design system and (2) advances of the nuclear fuel reprocessing safety analysis codes. These papers are compiled in this proceedings. (author)

  16. Annual reports of the Osaka Laboratory for Radiation Chemistry Japan Atomic Energy Research Institute, (No. 23, 24, 25)

    1992-09-01

    Research activities of Osaka Laboratory for Radiation Chemistry, JAERI during three year period from April 1, 1989 through March 31, 1992 are described. The latest report. for 1988, is JAERI-M 91-054. Detailed descriptions of the activities are presented in the following subjects: laser-induced organic synthesis, modification of polymer surface by laser irradiation, polymerization and modification of polymers by electron beam, and electron beam dosimetry. (author) 77 refs

  17. Annual report of the Osaka Laboratory for Radiation Chemistry, Japan Atomic Energy Research Institute, (no. 20)

    1989-01-01

    This report describes research activities of Osaka Laboratory for Radiation Chemistry, JAERI during one year period from April 1, 1986 through March 31, 1987. The latest report, for 1985, is JAERI-M 87-046. Detailed descriptions of the activities are presented in the following subjects: studies on surface phenomena under electron and ion irradiations; polymerization under the irradiation of electron beams; modification of polymers, degradation, cross-linking, and grafting. (author)

  18. Status of nuclear transmutation study

    Takizuka, Takakazu

    1999-01-01

    JAERI is carrying out R and Ds on partitioning and transmutation under the OMEGA Program. The R and Ds include the design study of accelerator-driven transmutation systems and the development of transmutation experimental facilities. Accelerator-driven systems have received much interests due to their potential role as dedicated transmuters in the nuclear fuel cycle for minimizing long-lived waste. Principles of accelerator-driven system, its history, JAERI proposed system concepts, and the experimental program are overviewed. (author)

  19. Annual report of the Osaka Laboratory for Radiation Chemistry, Japan Atomic Energy Research Institute, 14

    1981-12-01

    This report describes research activities of Osaka Laboratory for Radiation Chemistry, JAERI during one year period from April 1, 1980 through March 31, 1981. The latest report, for 1980, is JAERI-M 9214. Detailed descriptions of the activities are presented in the following subjects: studies on reactions of carbon monoxide, hydrogen and methane; polymerization under the irradiation of high dose rate electron beams; modification of polymers, degradation, cross-linking, and grafting. (author)

  20. Annual report of the Osaka Laboratory for Radiation Chemistry, Japan Atomic Energy Research Institute

    1982-12-01

    This report describes research activities of Osaka Laboratory for Radiation Chemistry, JAERI during one year period from April 1, 1981 through March 31, 1982. The latest report, for 1981, is JAERI-M 9856. Detailed descriptions of the activities are presented in the following subjects: studies on reactions of carbon monoxide, hydrogen and methane; polymerization under the irradiation of high dose rate electron beams; modification of polymers, degradation, cross-linking, and grafting. (author)