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Journal Articles

Maintenance management corresponding to plant life in JOYO

Suto, Masayoshi; Ichige, Satoshi; Isozaki, Kazunori

UTNL-R-0459, p.5_1 - 5_9, 2007/03

no abstracts in English

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.

Journal Articles

Design and renovation of heat transport system in the experimental fast reactor JOYO

Sumino, Kozo; Ashida, Takashi; Kawahara, Hirotaka; Ichige, Satoshi; Isozaki, Kazunori; Nakai, Satoru

Proceedings of Operating Nuclear Facility Safety(2004ONFS),p204-216, p.204 - 216, 2004/11

None

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.

Journal Articles

Replacement of Secondary Heat Transport System Components In the Experimental Fast Reactor JOYO

Kawahara, Hirotaka; Kawahara, Hirotaka; Ichige, Satoshi; Isozaki, Kazunori; Nakai, Satoru

Proceedings of 12th International Conference on Nuclear Engineering (ICONE-12) (CD-ROM), 0 Pages, 2004/00

A recently completed major upgrade of the JOYO experimental sodium-cooled fast reactor, to the MK-III design, increased its irradiation capability approximately four times. 0ne major change was a 40% increase in thermal power to 140 MWt, which necessitated the replacement of the heat exchangers. Each of the two coolant loops includes an intermediate heat exchanger (IHX) and sodium pump in the primary system, and two dump heat exchangers (DHXs) and a pump in the secondary system. The heat transfer area of the finned tubes in each (air-cooled) DHX was doubled, compared to the old design, to achieve a 35 MWt rating, Major challenges in the replacement of secondary components, such as piping and DHX, were control of impurity ingress into the sodium system, and integrity assurance of the welding. Damage to existing components and systems was avoided during cutting and welding operations by taking measures to Prevent ingress of air into the sodium systems. The measures included use of seal b

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.

JAEA Reports

JOYO MK-III Modification work on heat transport system; Work plan and plant control

Isozaki, Kazunori; ; Oshima, Jun; ; Ashida, Takashi; Saito, Takakazu; Sumino, Kozo

JNC TN9410 2002-007, 142 Pages, 2002/07

JNC-TN9410-2002-007.pdf:10.92MB

The MK-III Project to improve the irradiation capability of the experimental fast reactor JOYO have been in underway since 1987. The increase of fast neutron flux and the enlargement of that field increase the reactor thermal rate from 100MWt To 140MWt. To increase cooling capacity of heat transport system, intermediate heat exchangers (IHXs), dump heat exchangers (DHXs), piping connecting to IHXs and DHXs, main motors on Primary and secondary main circulation pumps were replaced. The replacement of these large components was carried out under following hard conditions. (1)Limitation of work space, (2)Fuel subassembly and melten sodium in the reactor vessel, (3)high radiation circumstances for primary cooling system, (4)treatment of radioactive sodium (radioactive sodium and corrosion product such as $$^{60}$$CO, $$^{54}$$Mn). There are little experiences of this kind of work in the world. Therefore the organization, workmg plan and safety management points were carefully examined and established, based on the previous experience of JOYO operation and maintenance, research and development results of safety treatment of sodium, experience of previous work on sodium facilities. Following sresults were obtained and effectiveness was confirmed in the work. (1)Development of most suitable working plan derived from elements and full size mock up experiments, reduction of exposure time by workers training, reduction of radiation dose by installation of temporal radiation shielding were useful to reduce radiation dose. The usage of seal bag was useful to prevent the contamination spreading over. (2)The usage of seal bag, oxygen concentration monitoring in the seal bag, nitrogen concentration monitoring in the cooling system cover gas, low pressure control of cover gas were useful to reduce the inflow of oxygen to cooling system. (3)The bite cutting method for piping in air and press down cuttmg by roller cutter in the seal bag to prevent inflow of cutting piece, ...

JAEA Reports

None

; *; *

JNC TY9400 2000-001, 64 Pages, 1999/12

JNC-TY9400-2000-001.pdf:3.92MB

no abstracts in English

JAEA Reports

Applicability test of the raman distributed temperature sensor for FBR plant instrumentation

Sumino, Kozo; Ichige, Satoshi; Fukami, Akihiro*; Maeda, Yukimoto; Suzuki, Soju

PNC TN9430 98-008, 40 Pages, 1998/09

PNC-TN9430-98-008.pdf:1.75MB

The Raman Distributed Temperature Sensor (RDTS) based on the Raman Scattering Phenomena in the optical fiber is a system, which can easily measure the accurate temperature distribution. In order to evaluate the applicability of RDTS for FBR plant instrumentation, a temperature distribution measurement using RDTS was performed in the primary cooling system of JOYO. By using two optical fiber sensors, which were installed spirally around the primary piping, the temperature distribution on the primary piping was measured from the 30th through the 32nd duty cycle. In addition, the same test was carried out in the secondary cooling system of JOYO in order to test the measurement data from the primary cooling system. The main results were as follows; (1) The temperature data in the primary cooling system was acquired over 180EFPDs of operation at JOYO (accumulated dose : 3 $$times$$ 10$$^{7}$$ R). (2) The chracteristics of FTR in the high dose rate nuclear plant environment was confirmed. (3) The radiation induced temperature errors were calibrated succesfully by using thermocouple readings. The accuracy of the temperature after calibration was approximately $$pm$$3$$^{circ}$$C. (4) It was confirmed that diffent fiber and insulator settings on the piping cause temperature changes.

JAEA Reports

Improvement and verification of blow down code for LEAP code; Comparison with blow down test data of 50MWtSG

*; *; *; *

PNC TJ9124 97-006, 295 Pages, 1997/03

PNC-TJ9124-97-006.pdf:6.03MB

In selecting the reasonable DBL(Design Basis Leak) on steam generator of next large LMFBR, it is indicated that the possibility of failure propagation due to overheating should be evaluated. Therefore, it is important to appropriately evaluate blow down behavior of water and steam in SG. For this purpose, cooling effect by water or steam in the tube should be considered appropriately or an evaluation of overheating tube rupture, and it is important adequately to select a heat transfer mode on the steam side. There, heat transfer models used in LOCA(Loss of Coolant Accident) analysis of a LWR(Light Water Reactor) have been investigated and applicable models have been employed in the LEAP-BLOW code. In addition, verification of analysis code and selection of a combination of the most suitable model has been performed using the test data of 50MWt SG. Then input and output functions have been improved.

JAEA Reports

The deformation analysis of JOYO core support-plate for the fast reactor safety characteristic research

; ; ; *

PNC TN9410 96-269, 24 Pages, 1996/09

PNC-TN9410-96-269.pdf:0.94MB

As the factor which affects the reactivity coefficient, there is a thing by the change of the flow characteristic of the core internal structure by the mechanical deformation. This displacement of core support-plate in the JOYO reactor vessel was analyzed by using "FINAS" (Finite Element Nonlinear Structural Analysis System). This displacement is a result of the coolant loading difference between the shutdown and full operational primary flow rates. The displacement of core support-plate in the JOYO reactor vessel was analyzed by using "FINAS" (Finite Element Nonlinear Structural Analysis System). This displacement is a result of the coolant loading difference between the shutdown and full operational primary flow rates. At first, the deformation of the core support was required according to the two-dimensional axisymmetric model. These displacements were used as input in the three-dimensional models of excluding the support rib. As a result, the displacement of the upper core support-plate would be about +0.39mm in the center and the maximum would be about +0.43mm in the fifth row. Because of the displacement of the support-plate was suppressed by the support rib. The whole core support structure was displaced in the upward direction. And, core support-plate of the upper and lower was spread largest about 0.03mm in the tenth row by the high-pressure plenum coolant loading.

JAEA Reports

None

; *;

PNC TN9520 96-003, 183 Pages, 1996/04

PNC-TN9520-96-003.pdf:25.6MB

None

Journal Articles

None

; Ogawa, Toru;

Donen Giho, -(77), 48 Pages, 1991/03

None

Journal Articles

None

; ; ; Ogawa, Toru;

American Nuclear Society International Topical Meeting on Safety of Operating Reactor, , 

None

Journal Articles

None

; ; ;

An American Nuclear Society International Topical Meeting "Safety of Operting Reactor", , 

None

15 (Records 1-15 displayed on this page)
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