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Journal Articles

Irradiation performance of HTGR fuel in WWR-K research reactor

Ueta, Shohei; Shaimerdenov, A.*; Gizatulin, S.*; Chekushina, L.*; Honda, Masaki*; Takahashi, Masashi*; Kitagawa, Kenichi*; Chakrov, P.*; Sakaba, Nariaki

Proceedings of 7th International Topical Meeting on High Temperature Reactor Technology (HTR 2014) (USB Flash Drive), 7 Pages, 2014/10

A capsule irradiation test with the high temperature gas-cooled reactor (HTGR) fuel is being carried out using WWR-K research reactor in the Institute of Nuclear Physics of the Republic of Kazakhstan (INP) to attain 100 GWd/t-U of burnup under normal operating condition of a practical small-sized HTGR. This is the first HTGR fuel irradiation test for INP in Kazakhstan collaborated with Japan Atomic Energy Agency (JAEA) in frame of International Science and Technology Center (ISTC) project. In the test, TRISO coated fuel particle with low-enriched UO$$_{2}$$ (less than 10% of $$^{235}$$U) is used, which was newly designed by JAEA to extend burnup up to 100 GWd/t-U comparing with that of the HTTR (33 GWd/t-U). Both TRISO and fuel compact as the irradiation test specimen were fabricated in basis of the HTTR fuel technology by Nuclear Fuel Industries, Ltd. in Japan. A helium-gas-swept capsule and a swept-gas sampling device installed in WWR-K were designed and constructed by INP. The irradiation test has been started in October 2012 and will be completed up to the end of February 2015. The irradiation test is in the progress up to 69 GWd/t of burnup, and integrity of new TRISO fuel has been confirmed. In addition, as predicted by the fuel design, fission gas release was observed due to additional failure of as-fabricated SiC-defective fuel.

JAEA Reports

Development of capsule design support subprograms for 3-dimensional temperature calculation using FEM code NISA

Tobita, Masahiro*; Matsui, Yoshinori

JAERI-Tech 2003-042, 132 Pages, 2003/03

JAERI-Tech-2003-042.pdf:7.19MB

Prediction of irradiation temperature is one of the important issues in the design of the capsule for irradiation test. Many kinds of capsules with complex structure have been designed for recent irradiation requests, and three-dimensional (3D) temperature calculation becomes inevitable for the evaluation of irradiation temperature. For such 3D calculation, however, many works are usually needed for input data preparation, and a lot of time and resources are necessary for parametric studies in the design. To improve such situation, JAERI introduced 3D-FEM (finite element method) code NISA (Numerically Integrated elements for System Analysis) and developed several subprograms, which enabled to support input preparation works in the capsule design. The 3D temperature calculation of the capsule are able to carried out in much easier way by the help of the subprograms, and specific features in the irradiation tests such as non-uniform gamma heating in the capsule, becomes to be considered.

JAEA Reports

Development of seal technique for optical fiber; Soldering seal and silver alloy brazing seal

Matsui, Yoshinori; Kikuchi, Taiji; Kakuta, Tsunemi

JAERI-Tech 2002-060, 23 Pages, 2002/08

JAERI-Tech-2002-060.pdf:4.42MB

Recently, the number of in-situ tests using optical fibers as signal transmission lines is increasing in the JMTR, because of their noise-tolerant capability and recent development of irradiation proof type fibers. The convensional seal methods, however, have the problem of trust when they applied to the penetration of the irradiation capsule using optical fibers. As the solution of the problem, we selected soldering seal method that was already applied to the deep-sea optical fiber cables and, as its modification, the silver alloy brazing method. From the result of the out-of-pile test, it was confirmed that both soldering seal and silver alloy brazing seal would be applicable to the plug seal of irradiation capsules. Then the soldering seal was applied to a capsule with optical fibers and was irradiated for 5 operation cycles of the JMTR (about 3000 hours). No deterioration was found at the seal after irradiation. This suggested that in-core use of optical fiber was thought to be promising.

Journal Articles

Development of 3-dimensional capsule temperature calculation program using FEM (NISA Code)

Tobita, Masahiro*; Matsui, Yoshinori

KAERI/GP-195/2002, p.87 - 95, 2002/00

In the Japan Materials Testing Reactor (JMTR) of Japan Atomic Energy Research Institute (JAERI), the temperature distribution inside of irradiation specimens and capsules structure material are evaluated in the design of irradiation capsules. For the evaluation of detailed temperature distribution, NISA (Numerically Integrated elements for System Analysis) code has been introduced, and subprograms are developed to simplify the input data of the capsules structure and the analysis conditions using the three-dimensional finite element method. By the development of subprograms, prediction of the temperature distribution inside of irradiation specimens and capsules structure material became detailed and more accurate than calculation by one-dimensional code. Also estimation of detail temperature distribution during irradiation became possible based on the indication of thermocouple.

Journal Articles

Natural convection heat transfer from a heated horizontal cylinder with microencapsulated phase-change-material slurries

Kubo, Shinji; Akino, Norio; Tanaka, Amane*; Nagashima, Akira*

Nihon Kikai Gakkai Rombunshu, B, 64(625), p.3013 - 3020, 1998/09

no abstracts in English

Journal Articles

Thermal characteristics of microencapsulated phase-change materials

E.Choi*; Akino, Norio

Proc. of 11th Int. Heat Transfer Conf. (Heat Transfer 1998), 7, p.121 - 126, 1998/00

no abstracts in English

Journal Articles

Natural convection heat transfer enhancement using microencapsulted phase-change-material slurries

Kubo, Shinji; Akino, Norio; Tanaka, Amane*; Nakano, Fumihiko*; Nagashima, Akira*

Thermal Science and Engineering, 5(1), p.9 - 13, 1997/01

no abstracts in English

JAEA Reports

Fuel temperature prediction during high burnup HTGR fuel irradiation test; US-JAERI irradiation test for HTGR fuel

Sawa, Kazuhiro; Fukuda, Kosaku; R.Acharya*

JAERI-Tech 94-038, 46 Pages, 1995/01

JAERI-Tech-94-038.pdf:1.26MB

no abstracts in English

JAEA Reports

Development of irradiation capsule for nuclear research reactor using aromatic polyether (BEK)

Arigane, Kenji; ; Sasajima, Fumio; Takahashi, Hidetake; Seguchi, Tadao;

JAERI-Tech 94-004, 33 Pages, 1994/07

JAERI-Tech-94-004.pdf:1.37MB

no abstracts in English

Journal Articles

Estimation for temperature distribution in a heat-generating cylinder with multiple holes

Harayama, Yasuo; Hoshiya, Taiji; ; Niimi, Motoji; Kobayashi, Toshiki*

Journal of Nuclear Science and Technology, 30(4), p.291 - 301, 1993/04

 Times Cited Count:4 Percentile:44.66(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Development of transient data processing system in the NSRR experiments

Tanzawa, Sadamitsu

JAERI-M 93-011, 32 Pages, 1993/02

JAERI-M-93-011.pdf:0.93MB

no abstracts in English

JAEA Reports

SATCAP-C: A Program for thermal hydraulic design of pressurized water injection type capsule

Harayama, Yasuo; ; Aso, Tomokazu; Niimi, Motoji

JAERI-M 92-149, 78 Pages, 1992/10

JAERI-M-92-149.pdf:2.53MB

no abstracts in English

JAEA Reports

Annual progress report on the NSRR experiments, 19; Jan.1987 $$sim$$ Dec.1987

;

JAERI-M 91-130, 156 Pages, 1991/08

JAERI-M-91-130.pdf:6.5MB

no abstracts in English

Journal Articles

Highmolecule material as irradiation capsule for research reactor

Arigane, Kenji

Oyo Hoshasen Kagaku Shimpojiumu; Hoshasen Kankyo To Kobunshi Zairyo Koen Yoshishu, p.25 - 28, 1991/01

no abstracts in English

JAEA Reports

Design procedure of capsule with multistage heater control, named MUSTAC

; Endo, Yasuichi; Hoshiya, Taiji; Niimi, Motoji; Harayama, Yasuo

JAERI-M 90-214, 57 Pages, 1990/11

JAERI-M-90-214.pdf:1.59MB

no abstracts in English

JAEA Reports

Irradiation Experiments of Coted Particle Fuels by Gas-Swept Capsules,(II); Irradiation by 75F4A and 75F5A Capsules

; ; ; Tobita, Tsutomu; Minato, Kazuo; Yamamoto, Katsumune; ;

JAERI-M 87-020, 79 Pages, 1987/02

JAERI-M-87-020.pdf:4.96MB

no abstracts in English

JAEA Reports

Irradiation Experiment of Coated Particle Fuels by Sweep Gas Capsule(Irradiation by 74F-9J Capsule)

; ; ; Ikawa, Katsuichi; Iwamoto, K.; Yamamoto, Katsumune; ;

JAERI-M 84-054, 65 Pages, 1984/03

JAERI-M-84-054.pdf:2.84MB

no abstracts in English

Journal Articles

In-pile high temperature irradiation testing techniques for the materials and fuels of HTGR in JMTR

; ; ; ;

Int.Topic Meeting on Irradiation Technology, p.529 - 537, 1983/00

no abstracts in English

30 (Records 1-20 displayed on this page)