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Journal Articles

Development of a knowledge based system linked to a materials database

Kaji, Yoshiyuki; Tsuji, Hirokazu; Fujita, Mitsutane*; Xu, Y.*; Yoshida, Kenji*; Mashiko, Shinichi*; Shimura, Kazuki*; Miyakawa, Shunichi*; Ashino, Toshihiro*

Data Science Journal (Internet), 3, p.88 - 94, 2004/07

The distributed material database system named "Data-Free-Way" has been developed by four organizations (the National Institute for Materials Science, the Japan Atomic Energy Research Institute, the Japan Nuclear Cycle Development Institute, and the Japan Science and Technology Corporation) under a cooperative agreement. In order to create additional values of the system, knowledge base system, in which knowledge extracted from the material database is expressed, is planned to be developed for more effective utilization of Data-Free-Way. XML (eXtensible Markup Language) has been adopted as the description method of the retrieved results and the meaning of them. One knowledge note described with XML is stored as one knowledge which composes the knowledge base. This paper describes the current status of Data-Free-Way, the description method of knowledge extracted from the material database with XML and the distributed material knowledge base system.

Journal Articles

Development of knowledge base system linked to material database

Kaji, Yoshiyuki; Yoshida, Kenji*; Mashiko, Shinichi*; Fujita, Mitsutane*; Shimura, Kazuki*; Kinugawa, Junichi*; Tsuji, Hirokazu; Miyakawa, Shunichi*; Iwata, Shuichi*

Nihon Genshiryoku Gakkai Wabun Rombunshi, 1(4), p.412 - 418, 2002/12

The distributed material database system named 'Data-Free-Way' has been developed by four organizations (the National Institute for Materials Science, the Japan Atomic Energy Research Institute, the Japan Nuclear Cycle Development Institute, and the Japan Science and Technology Corporation) under a cooperative agreement. In order to create additional values of the system, knowledge base system, in which knowledge extracted from the material database is expressed, is planned to be developed for more effective utilization of Data-Free-Way. XML (eXtensible Markup Language) has been adopted as the description method of the retrieved results and the meaning of them. One knowledge note described with XML is stored as one knowledge which composes the knowledge base. This paper describes the current status of Data-Free-Way, the description method of knowledge extracted from the material database with XML and the distributed material knowledge base system.

JAEA Reports

First selection of the LLFP iodine compound by the literature on this subject

Donomae, Takako; ; Onose, Shoji; Miyakawa, Shunichi; Nakamura, Yasuo

JNC TN9420 2002-003, 19 Pages, 2002/03

JNC-TN9420-2002-003.pdf:0.66MB

The Partitioning and Transmutation (P&T) for radionuclides included in high level has been researched in many countries. This technology for the radionuclides consists of partitioning them to several groups according to their half-lives and purposes of utilization and transmutating minor actinides (MA) and long lived fission products (LLFP) to short lived or stable nuclides. Japan Nuclear Cycle Development Institute (JNC) made a plan to develop this technology in the Feasibility Study for Fast Reactors and Related Fuel Cycle (FS), in cooperation with basic research groups. The main objective of JNC is to transmutate MA and LLFP in fast reactor. And this research was planned to carry out, taking into account not only reduction of environmnental burden and nuclear non-proliferation but also technical realization and economics. As a part of the research, the development of the elements for irradiation tests has just stated. According to the gained results of FS. The LLFPs, which have a possibility to realize the transmutation from the view point of nuclear physics, are $$^{129}$$I and $$^{99}$$Tc. Therefore, it was tried to select iodine chemical compounds fitted for transmutation by means of literature survey, because the half-life of $$^{129}$$I is long and the effect of radiation is comparatively hard. The literature survey was performed from the viewpoint of five properties, that is, nuclear physics, thermal phase change, chemical stability, fabrication, applicability to cycle use. As a result, 8 chemical compounds, namely, MgI$$_{2}$$, KI, NiI$$_{2}$$, CuI, RbI, YI$$_{3}$$, MoI$$_{2}$$, BaI$$_{2}$$ were selected as target materials from 32 candidates.

Journal Articles

The Fruits and Hope of The Experimental Fast Reactor "JOYO"

Miyakawa, Shunichi; Yanagisawa, Tsutomu; ; ; Mitsugi, Takeshi

P247, 247 Pages, 2002/00

None

Journal Articles

Obtainable knowledge for materials from Data-Free-Way; Description method of knowledge obtained from fact database

Tsuji, Hirokazu; Kaji, Yoshiyuki; Fujita, Mitsutane*; Kinugawa, Junichi*; Yoshida, Kenji*; Mashiko, Shinichi*; Shimura, Kazuki*; Miyakawa, Shunichi*; Iwata, Shuichi*

Proceedings of 10th German-Japanese Workshop on Chemical Information, p.131 - 133, 2002/00

The distributed material database system named "Data-Free-Way" has been developed by four organizations (the National Institute for Materials Science, the Japan Atomic Energy Research Institute, the Japan Nuclear Cycle Development Institute and Japan Science and Technology Corporation) under a cooperative agreement. It is a system which can display the data which the user demands without considering the organization which stores data as a table and a graph. The knowledge of the forte of each organization based on the retrieval result from the fact database is made aiming at more highly developed use of this system. The development of the system by which the user can refer to the knowledge is advanced. Though the retrieval result from the fact database was displayed as a table and a graph, that is, the finding note where they were described and expressed with XML as knowledge.

JAEA Reports

Final Report JNC/ANL Collaborative Program for Evaluation of Irradiated EBR-2 Stainless Steel

Tsai, H.*; Allen, T. R.*; Cole, J. I.*; Strain, R. V.*; Yoshitake, Tsunemitsu; Donomae, Takako; Akasaka, Naoaki; Mizuta, Shunji; Ukai, Shigeharu; Miyakawa, Shunichi

JNC TY9400 2001-025, 117 Pages, 2001/07

JNC-TY9400-2001-025.pdf:6.94MB

None

JAEA Reports

The evaluation of irradiation effect on the mechanical properties of the oxide dispersion strengthened ferritic steel claddings irradiated at JOYO/CMIR-4&5

; ; Miyakawa, Shunichi

JNC TN9400 2001-105, 41 Pages, 2001/07

JNC-TN9400-2001-105.pdf:1.33MB

The effect of fast neutron irradiation on the mechanical properties of the oxide dispersion strengthened (ODS) ferritic steel claddings (1DS & 1DK) which were manufuctured by warm working as the first trial cladding tube manufucturing in JNC, were investigated. The samples were irradiated in JOYO/CMIR-4&5. Uni-axial tensile test, ring-tensile test, burst test and miniaturized Charpy impact test were carried out to study the mechanical properties such as strength and elongation, of irradiated ODS ferritic claddings. The results of this study showed that there was no considerable deterioration on the mechanical properties of these ODS ferritic steel cladding samples under the irradiation conditions examined. The results obtained in this study are as follows; (1)The increase in strength due to irradiation hardening appeared in higher temperatures ($$sim$$600,650$$^{circ}$$C) than that of austenitic steels such as PNC316. (2)There was an anisotropy in the short time range strengths after irradiation due to its particular crystalline structure so called "bamboo structure". (3)The elongation of hoop direction after irradiation was significantly tended to be much lower than that of longitudinal direction because of its particular "bamboo structure". (4)There was no obvious decrease in elongation and miniaturized Charpy impact properties under irradiation conditions examined. (5)TEM observation showed that there was no significant change in microstructure before and after irradiation except the precipitation of Laves phase on grain boundary after irradiation and that Y$$_{2}$$O$$_{3}$$ particles and their fine distribution might be stable during irradiation.

Journal Articles

None

Yoshitake, Tsunemitsu; Akasaka, Naoaki; Donomae, Takako; Miyakawa, Shunichi

Saikuru Kiko Giho, (10), p.67 - 76, 2001/03

None

Journal Articles

Burst properties of imadiated oxide dispersion strengthened ferritic steel claddings

Yoshitake, Tsunemitsu; ; Miyakawa, Shunichi

10th International Conference on Fusion Reactor Materials, 154 Pages, 2001/00

None

Journal Articles

Obtainable knowledge for materials from data-free-way; Method for description of knowledge obtained from fact database

Kaji, Yoshiyuki; Yoshida, Kenji*; Mashiko, Shinichi*; Fujita, Mitsutane*; Shimura, Kazuki*; Kinugawa, Junichi*; Tsuji, Hirokazu; Miyakawa, Shunichi*; Iwata, Shuichi*

Dai-38-Kai Joho Kagaku Gijutsu Kenkyu Shukai Happyo Yokoushu, p.43 - 47, 2001/00

A distributed database system named Data-Free-Way for advanced nuclear materials has been developed by the National Institute for Materials Science (NIMS), the Japan Atomic Energy Research Institute (JAERI), the Japan Nuclear Cycle Development Institute (JNC), and the Japan Science and Technology Corporation (JST) under a cooperative agreement. In this system, end-users are able to obtain necessary data such as tables or graphs, even if they do not know the sites in which the data are stored. A distributed knowledge database in which each organization makes the knowledge based on the retrieval results from fact database and end-users can get the knowledge, has been developed to make more useful utilization of this system. Though the retrieval results from the fact database were shown in the tables or graphs, the new system constitutes the information notes described the retrieval ones for the knowledge by XML. This paper describes the present status of the Data-Free-Way and the description method of XML for the retrieval results.

Journal Articles

The Development of a Sodium Bonded Type Control Rod in Joyo

Soga, Tomonori; Tobita, Koichi; Mitsugi, Takeshi; Miyakawa, Shunichi

Saikuru Kiko Giho, (8), p.13 - 22, 2000/09

None

JAEA Reports

Irradiation report of the Ex-vessel irradiation rig (EXIR) in JOYO

Yasu, Tetsunori; *; Soroi, Masatoshi; ; ; Miyakawa, Shunichi

JNC TN9430 2000-001, 55 Pages, 1999/12

JNC-TN9430-2000-001.pdf:2.38MB

The EX-vessel irradiation Rig (EXIR) is the on-line measurement and control irradiation equipment. It was developed to test uniaxial creep rupture strength of the reactor structural material under neutron irradiation condition, and installed between reactor guard vessel and safety vessel of the Experimental Fast Reactor "JOYO". The irradiation test using EXIR started at the 29th operation cycle in August 1994, and finished at the 30th operation cycle in March 1997 since the burst signals of two test pieces were detected. Through this irradiation test, performance of EXIR are confirmed and in reactor creep data on SUS316FR were obtained. The results are summarized as follows. (1)Temperature Conditions. The Temperature of the test pieces was controlled so as to be constant during the reactor operation. Its deviation from target temperature was recorded within $$pm$$2$$^{circ}$$C, which sufficiently outperformed the designed accuracy of $$pm$$3$$^{circ}$$C. (2)Tensile load Conditions. The control of the tensile load was retained in $$pm$$8.8N range for the set load value, and it was the performance which sufficiently satisfied control precision $$pm$$29.4N. (3)Displacement Result. On SUS316FR which was the structural material for fast reactor, uniaxial creep rupture strength test under the neutron irradiation was carried out, and the displacement data were acquired. The analysis of the displacement data will be reported after post irrdiation experiment.

JAEA Reports

Design of uninstrumented irradiation subassembly type-D (UNIS-D)

; Miyakawa, Shunichi; Mitsugi, Takeshi; Kitamura, Ryoichi

JNC TN9410 99-010, 350 Pages, 1999/06

JNC-TN9410-99-010.pdf:11.62MB

In the needs of the fuel irradiation test in "Joyo" MK-III core, there have been required that the irradiation of high performance fuel at high liner heat rate to high burn-up range, or the irradiation of advanced fuel such as MA fuel and Vipac fuel. In order to carry out these irradiation tests, newly designed irradiation subassembly is required with special features of; (1)Capability of the re-assembling after post-irradiation examination, even if the number of fuel in the identical irradiation condition decreases because of intermediate inspection. (2)Enhanced flexibility of the irradiation temperature setting ( in the present, UNIS-B's has 6 cases on the maximum). (3)Sufficient flexibility for the coolant flow distribution in the subassembly by extending variety of the flow rate setting. UNIS-D is a fuel irradiation subassembly which has been developed from above viewpoints. It is a compartment loading type irradiation subassembly that is able to load maximum of 18 compartments. Two types of compartments $$gamma$$ -type and $$delta$$ -typc arc prepared for UNIS-D. Thc sufficient consideration has also been made on the rc-assembling. A $$gamma$$ -type is the same compartment as the existing UNIS-B's and a $$delta$$ -type is the newly designed one for UNIS-D. Three to five fuel pins are loaded into a $$gamma$$ -type compartment and only one pin is loadcd into a $$delta$$ -type compartment. It is possible to carry out the irradiation test in a maximum of 18 test temperature conditions within a subassembly, since it has the sufficient flexibility for the coolant flow distribution. As for the development of UNIS-D, we have finished the detailed structure design and the design verification by the water flow examination, which confirmed that the UNIS-D exceeded its required performances in use and that its structure design was satisfactory.

JAEA Reports

The Improvement of control rod in experimental fast reactor JOYO; The development of a sodium bonded type control rod

Soga, Tomonori; Miyakawa, Shunichi; Mitsugi, Takeshi

JNC TN9400 99-052, 355 Pages, 1999/06

JNC-TN9400-99-052.pdf:13.11MB

Currently, the lifetime of control rods in JOYO is limited by Absorber-Cladding Mechanical Interaction (ACMI) due to swelling of B$$_{4}$$C(boron carbide) pellets accelerated by relocation of pellet fragments. A sodium bonded type control rod was developed which improves the thermal conductivity by means of charging sodium into the gap between B$$_{4}$$C and cladding and by utilizing a shroud which wraps the pellet fragments in a thin tube. This new design will be able to enlarge the gap between B$$_{4}$$C and cladding, without heating B$$_{4}$$C or fragment relocation, thus extending the life of the control rod. The sodium bonded type will be fabricated as the ninth reload control rods in JOYO. (1)The specification of a sodium bonded type control rod was determined with the wide gap between B$$_{4}$$C and cladding. In the design simulation, main component temperature were below the maximum limit. And the local heating by helium bubble generated from B$$_{4}$$C in the sodium gap, was not a serious problem in the analysis which was considered. (2)A structural design for the sodium entrance into the pin was determined. A formula was developed which the limit for sodium charging given physical dimension of the structure and sodium property. Result from sodium out-pile experiments validated the theoretical formula. (3)The analysis of ACMI indicated a lifetime extension of the sodium bonded type by 4.6% in comparison with lifetime of the helium bonded type of 1.6%. This is due to the boron10 burn-up rate being three times higher in the sodium bonded type than in the helium bonded type. To achieve a target burn-up 10% in the future, it will be necessary to modify design based on irradiation data which will be obtained by practical use of the sodium bonded control rods in JOYO. (4)The effects due to Absorber-Cladding Chemical Interaction (ACCI) were reduced by controlling the cladding temperature and chromium coating to the cladding's inner surface. It was confirmed that ...

JAEA Reports

Development of an electrical connector for liquid sodium environment; Final report

; ; ; Miyakawa, Shunichi

PNC TN9410 98-076, 89 Pages, 1998/07

PNC-TN9410-98-076.pdf:8.52MB

The INstrumented irradiation Test Asembly (INTA) has been used to conduct precision on-line instrumented irradiation tests in the experimental fast reactor JOYO. In INTA, direct instrumentation wiring between the irradiation test section in the core and the upper structure section in the rotating plug makes INTA structurally complex and expensive. Instead of direct wiring, if an electrical connector capable of withstanding a heated liquid sodium environment could be used between the irradiation test section and the upper structure section, the upper mechanism of INTA could be reused and testing costs would be drastically reduced. Moreover, the reactor load factor would be improved because of reduced handling time for INTA. In an attempt to gain this advantage, research and development of an electric connector in a sodium environment was carried out from 1988 to 1996 at PNC. As no previous R&D had been conducted in this area, this development activity was conducted in a boot strap manner. The first test was carried out for a small model fabrication, the second was for a water partial model, and the third was for a sodium partial model. Based on those tests, a prototype design specification of the connector was determined. In the sodium partial model test, the resiliance of the electrical connector insulation to the sodium environment was investigated. However, severe cracking in the ceramic insulator caused by the high temperature sodium environment was discovered at the junction of ceramic insulator and metallic electrode. This was recognized to be a critical problem because the boundary on the structure could not be secured. To address the problem, additional sodium partial tests were performed for various material combinations of ceramic insulators, metallic electrodes, brazing materials and metallization materials. However for insulator cracking, the results of the tests were unsatisfactory. After all although the newest technology of main ceramics ...

JAEA Reports

Development of the flow control irradiation facility for JOYO

Soroi, Masatoshi; Miyakawa, Shunichi

PNC TN9410 98-050, 57 Pages, 1998/05

PNC-TN9410-98-050.pdf:1.58MB

This report describes the present situation and problems with the development of the flow control irradiation facility (FLORA). The purpose of FLORA is to run the cladding breach (RTCB) irradiation test under loss of flow conditions in the experimental fast reactor "JOYO". FLORA is a facility like FPTF (Fuel Performance Test Facility) plus BFTF (Breached Fuel Test Facility) in EBR-II, USA. The technical feature of FLORA is its annular linear induction pump (A-LIP), which was developed in response to a need identified through the experiences in the mechanical flow control of FPTF. We have already designed the basic system facility of FLORA for the JOYO MK-II core. However, to put FLORA to practical use in the future, we have to confirm the stability of the JOYO MK-III core condition, solve problems and improve the design. The main results and problems of the development of FLORA are as follows; (1)The results of the development: (a)The neutron detector in FLORA can detect the delayed neutron which is emitted from failed fuel. (b)Out-of-pile A-LIP tests in sodium conditions has been completed. (The length of the tested A-LIP is half the actual size.) Out-of-pile test results showed that the A-LIP achieved a 300$$ell$$/min flow rate and 265kPa pressure in 550$$^{circ}$$C sodium. This pump performance satisfied the FLORA requirements. (c)By controlling the sodium flow rate from 40 to 100% using the A-LIP, we can control the fuel cladding temperature satisfactorily. (2)The problems: (a)In the development of the process detector, it is necessary to miniaturize the neutron detector and test the effect of neutron irradiation and high temperatures on the permanent magnet in the flow meter. (b)The problem which is left about A-LIP is its influence on neutron irradiation. For this purpose, we have to irradiate a small size A-LIP and test its characteristics and electric isolation. (c)To get more accurate results concerning the efficiency of the A-LIP, we have to ...

JAEA Reports

Development of fabrication method for thermal expansion difference irradiation temperature monitor

; *; Miyakawa, Shunichi; *;

PNC TN9410 98-035, 60 Pages, 1998/03

PNC-TN9410-98-035.pdf:2.46MB

This report describes the development activities for the fabrication of the Thermal Expansion Difference irradiation temperature monitor (TED) at the Oarai Engineering Center (OEC)/PNC. TED is used for various irradiation tests in the experimental fast reactor JOYO. TED is the most accurate off-line temperature monitor used for irradiation examination. The TED is composed of a metallic sphere lid and either a stainless steel or nickel alloy container. Once the container is filled with sodium, the metallic sphere lid is sealed by using a resistance weld. This capsule is then loaded into a reactor. Once a TED is loaded into the JOYO reactor, the sodium inside the metallic container increases as a result of thermal expansion. The TED identifies the peak irradiation temperature of the reactor based on a formula correlating temperature to increment values. This formula is established specifically for the particular TED being used during a calibration process performed when the TED is fabricated. Initially the TED was developed by Argonne National Laboratory (ANL) in the United States, and was imported by PNC for use in the JOYO reactor. In 1992 PNC decided to fabricate TED domestically in order to ensure the stability of future supplies. Based on technical information provided by ANL, PNC began fabrication of a TED on an experimental basis. In addition, PNC endeavored to make the domestically produced TED more efficient. This involved improving the techniques used in the sodium filling and the metallic sphere welding processes. These quality control efforts led to PNC's development of processes enabling the capsules to be filled with sodium to nearly 100%. As a result, the accuracy of the temperature dispersion in the out-pile calibration test was improved from $$pm$$10$$^{circ}$$C to $$pm$$5$$^{circ}$$. In 1996 the new domestically fabricated TED was attached to a JOYO irradiation rig. In March of 1997, irradiation of the rig was started on the 30th duty cycle operation, .

Journal Articles

On-line Irradiation Technologies at JOYO

Soroi, Masatoshi; Kataoka, H.; Miyakawa, Shunichi

Nihon Genshiryoku Gakkai-Shi, 40(2), p.124 - 134, 1998/00

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

None

Journal Articles

Development of Material International Rig with Precise Temperature Control in Experimental Fast Reactor JOYO

Miyakawa, Shunichi; Kataoka, H.; Yasu, Tetsunori;

Proceedings of 8th International Conference on Fusion Reactor Materials (ICFRM-8), P. 319, 1997/10

None

JAEA Reports

Development and the results for the control rods in MK-II core of experimental fast reactor JOYO

Miyakawa, Shunichi; ; Soga, Tomonori

PNC TN9410 97-068, 113 Pages, 1997/07

PNC-TN9410-97-068.pdf:3.97MB

Since the first control rod design for the Joyo Mk-II core (about twenty years ago), there have been several challenging improvements; for example, a helium venting mechanism and a flow induced vibration prevention mechanism. Forty-four control rods with these various modifications have been fabricated. To date, thirty-four have been irradiated and the sixteen have been examined, This experience and effort has produced fruitful results: (1)Efficiency and reliability of the diving-bell type Helium venting mechanism (2)Efficiency of the flow induced vibration prevention mechanism (3)Efficiency of the improvement for scram damping mechanism (4)Clarification of absorvber-pellet-cladding-mechanical-interaction (ACMI)phenomena and preventive methods The fourth result listed above has been a subject of investigation for fifteen years in several countries, that is a main phenomena to dominate control rod life time. The results of this investigation of ACMI in absorber elements are summarized below: (a)In five of Joyo Mk-II control rods, cladding cracks were found in fifteen of the elements. These cracks were caused by a acceleration ACMI, due to B$$_{4}$$C fragments relocation. They occurred over a wide burnup range from 5E+26 Cap./m$$^{3}$$ to 45E+26Cap./m$$^{3}$$ in a nearly typical provability distribution. The cladding cracked because of its low ductility (approximately 1/4 lower than the uniform elongation of usual tensile testing for irradiated 316SS cladding) due to neutron irradiation and the ultra slow ACMI induced strain rate. (b)In this case the crack growth rate is extremely slow and the ACMI induced cracking in absorber elements do not influence either the reactor or plant operations. It is on this basis that a strict limitation to avoid the cladding crack is not necessary. According1y, it is suggested that a realistic design standard should consider the ACMI phenomena and the burnup limit be based on the nominal base calculation for average plastic strain use ...

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