Refine your search:     
Report No.
 - 
Search Results: Records 1-12 displayed on this page of 12
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

JAEA Reports

Periodic Safety Review of the Experimental Fast Reactor JOYO; Review of Aging Management

Isozaki, Kazunori; Ogawa, Toru; Nishino, Kazunari; Kaito, Yasuaki; Ichige, Satoshi; Sumino, Kozo; Suto, Masayoshi; Kawahara, Hirotaka; Suzuki, Toshiaki; Takamatsu, Misao; et al.

JNC TN9440 2005-003, 708 Pages, 2005/05

JNC-TN9440-2005-003.pdf:31.46MB

Periodic safety review (Review of the aging management) which consisted of Technical review on aging for the safety related structures, systems and components and Establish a long term maintenance program was carried out up to April 2005.1. Technical review on aging for the safety related structures, systems and components It was technically confirmed to prevent the loss of function of the safety related structures, systems and components due to aging phenomena, which (1) irradiation damage, (2) corrosion, (3) abrasion and erosion, (4) thermal aging, (5) creep and fatigue, (6) Stress Corrosion Cracking, (7) insulation deterioration and (8) general deterioration, under the periodic monitoring or renewal of them 2. Establish a long term maintenance program The long term maintenance program during JPY2005 to 2014 were established based on the technical review on aging for the safety related structures, systems and components. It was evaluated that the inspection or renewal based on the long term maintenance program, in addition to the spontaneous inspection long-term schedule of the long term voluntary inspection plan, could prevent the loss of function of the safety related structures, systems and components in future.

JAEA Reports

MK-III Function Tests in JOYO; Dump Heat Exchanger (DHX)

Kawahara, Hirotaka; Isozaki, Kazunori; Ishii, Takayuki; Ichige, Satoshi; Nose, Shoichi; Sakaba, Hideo; Nakai, Satoru

JNC TN9410 2004-016, 106 Pages, 2004/06

JNC-TN9410-2004-016.pdf:8.47MB

A key part of the upgrade of the experimental fast reactor JOYO to the MK-III design was the replacement of the dump heat exchangers. MK-III function tests (SKS-1) of the new dump heat exchangers were carried out from August 27,2001 through September 13,2001. The major results of the function tests of the dump heat exchangers were as follows: (1) Air flow of the main blower with an inlet vane opening of 50% was confirmed to exceed the design rated flow of 7,700m3/min. It was also demonstrated that an inlet vane opening of 100% provides about 130% of the design rated flow. This is because the new DHX flow route has more low pressure loss than the design value. (2) Tests of the air flow of the main blower demonstrated that with a fully opened inlet damper a full opened outlet damper and an inlet vane opening of O% provides about 5% of the design rated flow. (3) Free flow coast down characteristics of the main blower achieved an inlet vane O% opening in an average of 7.9 seconds. Revolutions per minute of the main blower reached zero in an average of 8.7 seconds. The delay time from the opening of the vacuum contact breaker to the air flow decrease was approximately 1 second. This was a more conservative value than the 5 seconds assumed in design thermal transient analyses. (4) The loudest noise occurred with the main blower operating with a 25% inlet vane opening. At that time, the noise around the main blower was approximately 100dB, and in the surrounding monitoring area boundary, the noise was 50dB. This was confirmed to be within the standard of the Ibaraki prefectural ordinance. (5) Although the MK-III inlet vane and inlet damper drive unit was bigger than the MK-II unit, the accumulator tank was confirmed to provide sufficient volume during a compression air loss event.

JAEA Reports

Evaluation of dissolution rate on high plutonium content MOX fuel

; Endo, Hideo; Ogasawara, Masahiro*; Shinada, Masanori*; *

JNC TN8440 2003-004, 24 Pages, 2003/05

JNC-TN8440-2003-004.pdf:5.0MB

The dissolution rate of high Pu content MOX fuel into the nitric acid was measured as a function of Pu content. MOX fuel sample which was pressed and sintered, were dissolved in boiling 7M nitric acid, and dissolution rate was measured by analysis of the Pu and U concentration in the solution. Dissolution rate of MOX fuel had the following tendencies : it decreased with increase of the Pu content and was reduced after 6 hours dissolution. These results agreed well to previous one, but dissolution rate was 3-6 times larger than that. It is estimated that the cause of this difference was due to the underestimate of surface area of MOX fuel powder and the difference of MOX O/M ratio.

JAEA Reports

MK-III Modification work of heat transport system in JOYO; Dismantling and sodium cleaning of secondary cooling system components

Ishii, Takayuki; Isozaki, Kazunori; Ashida, Takashi; Minakawa, Satoru; Terakado, Tsuguo; Nogami, Hiroshi*; Kakurai, Katsuhiko*; Ueda, Soji*; Kawahara, Hirotaka; Ichige, Satoshi; et al.

JNC TN9410 2002-013, 86 Pages, 2002/11

JNC-TN9410-2002-013.pdf:68.29MB

The MK-III project has been proceeding to improve the irradiation capability of the experimental fast reactor JOY0. The MK-III project has three major purposes such as increase high neutron flux, improvement of plant availability factor and upgrading in irradiation techniques. Thermal output by core transformation for high neutron flux was increased from 100MWt to 140MWt. The main components in the cooling system such as IHX(Intermediate Heat Exchanger) and DHX(Dump Heat Exchanger) were replaced in MK-III modification in order to increase heat removal capability. Heat transfer capacity of IHX was increased from 50MWt/Unit to 70MWt/Unit and that of DHX was increased from 25MWt/Unit to 35MWt/Unit. These components replacement has been safety completed from october 30, 2000 through September 21, 2001. This report summarizes the way, results and safety measures about dismantling of no sodium adhered components and such as DHX blower and sodium cleaning of sodium components such as the DHX, the pipes connected with DHX and secondary side of IHX. Dismantling and sodium cleaning of secondary cooling system components were performed safely and efficiently as almost planned. The total amount of removed sodium was about 13.5kg.

Journal Articles

None

; ; ; ;

Saikuru Kiko Giho, (15), p.41 - 46, 2002/06

None

JAEA Reports

Study of uranium particle fuel fabrication with the external gelation process with the vibration dropping Method

Nishimura, Kazuhisa; Shoji, Shuichi*; *; Sato, Seiichi*; ; Endo, Hideo

JNC TN8430 2001-005, 64 Pages, 2001/09

JNC-TN8430-2001-005.pdf:4.1MB

The external gelation process is one of the candidates of MOX particle fuel fabrication for advanced recycle system. It was necessary to perform preliminary fuel fabrication with uranium before starting MOX tests. As the result of the preliminary examination, Basics conditions of the fabrication were obtained: (1)Optimized uranyl nitrate solution and PVA solution, as raw materials were prepared. (2)The frequency of vibration and the amount of flow were obtained with optimized broth (mixture) in the vibration dropping process. (3)The influence of composition of broth and concentration of ammonia solution on gelation process was obtained. (4)Impurities after aging, washing and drying spHerical gel were surveyed, (5)The spherical gel were calcined to oxide particles and the particles were characterized by TG-DTA, therefore it is certain that outlook on the sintered particles as final products is very clear. On the top of that, there were no fatal technicalities of the external gelation process through material balance and a diameter dispersion of spherical gel and oxide particles. It is necessary to perform uranium examination to solve some new problems, for instant, surface crack of spherical gel. Although almost of all the preparations are completed and fabrication examination of MOX particles with vibration dropping equipment are ready for starting.

JAEA Reports

None

; ; Obata, Shinichi; ; Endo, Hideo

JNC TN8410 99-011, 65 Pages, 1999/04

JNC-TN8410-99-011.pdf:3.63MB

None

Journal Articles

Development of high efficiency and crowbar switchless dc power supply for 1MW CW CPD gyrotron

Tsuneoka, Masaki; Kasugai, Atsushi; ; Sakamoto, Keishi; Imai, Tsuyoshi; Fujita, Hideo*; *; *; *; *; et al.

Int. J.Electronics, 86(2), p.233 - 243, 1999/00

 Times Cited Count:10 Percentile:56.53(Engineering, Electrical & Electronic)

no abstracts in English

Journal Articles

Power supply control and protection system for long pulse and high power gyrotron

Tsuneoka, Masaki; Fujita, Hideo*; Nagashima, Takashi; *; *; *

Purazuma, Kaku Yugo Gakkai-Shi, 70(9), p.992 - 1002, 1994/09

no abstracts in English

Journal Articles

Development of a high power gyrotron for ECH of tokamak plasma

Sakamoto, Keishi; Tsuneoka, Masaki; Maebara, Sunao; Kasugai, Atsushi; Fujita, Hideo*; *; Yamamoto, Takumi; Nagashima, Takashi; Kariya, Tsuyoshi*; *; et al.

Proceedings of the 17th International Conference on Infrared and Millimeter Waves, p.188 - 189, 1992/00

no abstracts in English

Journal Articles

Construction and testing of the new multijunction LHRF launcher for JT-60 upgrade

Seki, Masami; Ikeda, Yoshitaka; *; Imai, Tsuyoshi; ; Yokokura, Kenji; Sawahata, Masayuki; Suganuma, Kazuaki; Sato, Minoru; *; et al.

Fusion Technology 1990, p.1060 - 1064, 1991/00

no abstracts in English

Journal Articles

ESR study of Pb$$^{3}$$$$^{+}$$ ions in cubic PbF$$_{2}$$ crystals irradiated with $$gamma$$-rays and neutrons at low temperatures

*; *; *; Kazumata, Y.

Journal of the Physical Society of Japan, 42(6), p.1900 - 1905, 1977/06

 Times Cited Count:11

no abstracts in English

12 (Records 1-12 displayed on this page)
  • 1