Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Ito, Chikara; Ito, Hideaki; Ishida, Koichi; Aoyama, Takafumi
JAEA-Technology 2011-007, 56 Pages, 2011/06
JAEA-Technology-2011-007.pdf:9.2MB
In the experimental fast reactor Joyo, measurement for characterizing and predicting the deposition condition and the condition change of the corrosion product (CP) that is the major radiation source in equipments and piping of primary cooling system has been carried out regularly from early period of reactor operation. Cooling system modification work with the shift to the MK-III core was carried out after the last measurement that was carried out, and the main equipments such as intermediate heat exchangers were replaced. This measurement in this report was carried out at after the 2nd cycle operation of the MK-III core which started formal operation.
Okawachi, Yasushi; Maeda, Shigetaka; Ito, Chikara; Kawahara, Hirotaka; Aoyama, Takafumi; Ishida, Koichi
JAEA-Technology 2009-047, 130 Pages, 2009/09
JAEA-Technology-2009-047-1.pdf:44.46MBJAEA-Technology-2009-047-2.pdf:38.7MBJAEA-Technology-2009-047-3.pdf:33.16MB
This report summarizes the contents about "Reactor physics and plant dynamics experiments using the Joyo simulator" which is one of the training themes. Training is performed using the full scope nuclear reactor simulator for Joyo operation training. While pushing from starting of a nuclear reactor in each experiment of criticality, a control rod proofreading examination, measurement of the temperature of a nuclear reactor, or the reactivity coefficient accompanying output change, feedback reactivity measurement of a fast reactor, etc. and understanding self-regulating characteristics peculiar to a nuclear reactor, the operation of a nuclear reactor can be experienced.
Ito, Chikara; Kagota, Eiichi; Ishida, Koichi; Kitamura, Ryoichi; Aoyama, Takafumi
Proceedings of 15th International Conference on Nuclear Engineering (ICONE-15) (CD-ROM), 9 Pages, 2007/04
no abstracts in English
Ishida, Koichi; Ito, Chikara; Aoyama, Takafumi
Proceedings of International Conference on Nuclear Energy System for Future Generation and Global Sustainability (GLOBAL 2005) (CD-ROM), 6 Pages, 2005/10
When a fuel failure occurs in a nuclear reactor, it is important to detect and identify the failed fuel subassembly to improve reactor safety and reduce radiation exposure and impact on the environment. A Fuel Failure Simulation Test in the experimental fast reactor JOYO was performed to confirm the JOYO plant operation procedures for potential future fuel failure events and help prepare for future planned run-to-cladding-breach tests in JOYO. The test fuel elements with an artificial slit in the fuel cladding was loaded in the core center position of the MK-III core. The test fuel elements were irradiated, the release of fission products was detected, and the location of the leaking test subassembly was identified. The performance of the fuel failure detection system and the failed fuel detection and location systems, and the plant operation procedure of fuel failure were confirmed. To decrease the radioactive concentration in the cover gas, the Cover Gas Clean-up System which collects fission product nuclides by the cryogenic distillation method and furnace-cover-gas-purge were operated, and their operation procedure and performance ware confirmed. This test results will improve the JOYO operation procedures and potential upgrades to the facilities, and be contributed to the safety enhancement of fast breeder reactors.
Oyama, Kazuhiro; Kawahara, Hirotaka; Ishida, Koichi; Ariyoshi, Masahiko; Isozaki, Kazunori; Sugaya, Kazushi*; Fukami, Akihiro*
JNC TN9410 2005-006, 121 Pages, 2005/03
JNC-TN9410-2005-006.pdf:10.81MB
In the MK-III performance test, the experimental fast reactor JOYO raised the reactor thermal power gradually with about 20%, 50%, 75%, 90%, and 100% (140MWt), and reached 140MWt which are the full power of a MK-III reactor core on October 28, 2003. Then, continuation operation beyond full power 100 hour was attained. This report summarized the result of power-up test , full power continuation operation test, blower start-up test.The outline is as follows.(1)From the standby state (system temperature of 250degree), the usual power-up operation (an power-up rate ;about 5MWt/20min, a power is held for about 10 minutes every 5MWt) attained the reactor thermal full power (140MWt) gradually on October 28,2004. Moreover, it checked that each part temperature and flow were less than alarm setting values on each power level.(2)The reactor thermal power was made into the parameter, a series of operations about the blower start-up, and the influence which it has on coolant temperature was checked. As a result, the optimal reactor thermal power which starts up the blower from a natural ventilation cooling state was set to about 18 MWt, and the starting procedure was made into the method(order of 1A-2A-1B-2B) which starts four sets of the one blower at a time one by one.(3)It checked that reactor shutdown operation by two control-rod simultaneous insertion at 35MWt, and it could carry out with time margin with a series of sufficient operations of resulting from control rod insertion in the blower shutdown. By adopting this reactor shutdown operation method, operation of an operation stuff was mitigated and it checked that plant characteristics also improved.(4)The reactor full power was reached on November 14. Continuation operation beyond full power 100 hour was attained after that till on November 20, 10:30. The data of each part of a plant was acquired at intervals of 24 hours, and it checked that it was less than an alarm setting value.
Ito, Chikara; Ito, Hideaki; Ishida, Koichi; Hatoori, Kazuhiro; Oyama, Kazuhiro; Sukegawa, Kazuya*; Murakami, Takanori; Kaito, Yasuaki; Nishino, Kazunari; Aoyama, Takafumi; et al.
JNC TN9410 2005-003, 165 Pages, 2005/03
JNC-TN9410-2005-003.pdf:12.66MB
At experimental fast reactor JOYO, appraisal of detection efficiency of behavior and FFD and FFDL of the fission product which is discharged inside the furnace as one of safety research of the country, is carried out. In MK-II core, the slit in the gas plenum part of the test sub-assembly, the test which irradiates this(1985 April, FFDL in-pile test(I)), providing the slit in the fuel column part of the test sub-assembly, the test which it irradiates(1992 November, FFDL in-pile test(II)) were carried out.MK-III reactor core replacement was completed and started in 2004. That the behavior in the system of FP with the reactor core replacement and so on changes in the MK-III reactor core and to have an influence on the sensitivity and the replying of FFD and FFDL are thought of. Therefore, behavior of FP in the fuel failure in the MK-III reactor core, the performance of FFD and FFDL must be confirmed beforehand. Moreover, to prepare for the fuel failure and the RTCB test which is doing a future plan, and to confirm a plant operation procedure in the fuel failure in MK-III reactor core operation and to attempt for the correspondency to improve are important.Therefore, in the period from 2004 November 11th to November 29th, it carried out the FFDL in-pile(III). It did a series of plant operation to stop a nuclear reactor after loading a reactor core center with the fuel element for the test which provided an artificial slit for the fuel cladding in the MK-III reactor core and irradiating it and detecting fuel damaging and to take out fuel. And it confirmed the operation procedure of the fast reactor in the fuel failure.Also, the improvement items such as the improvement of the operation and the procedure and the remodeling and the service of the facilities could be picked up. In the future, it attempts these compatible, and it prepares for the MK-III reactor core operation and it incorporates a final examination result by the improvement of the safety of FBR.
Kawahara, Hirotaka; Rekimoto, Masafumi; Jo, Takahisa; Ishida, Koichi; Ariyoshi, Masahiko; Isozaki, Kazunori
JNC TN9410 2005-002, 135 Pages, 2005/02
JNC-TN9410-2005-002.pdf:17.48MB
The manual shutdown tests and loss of electric power supply tests were carried out as the transient response test on anomaly condition at 70MWt and 140MWt operation. The decay heat removal tests by main cooling system were carried out after each transient response tests. It was confirmed that the plant protection system operates properly and the reactor can be shut down safely. These results confirmed that the thermal transients are less severe than the design conditions.
Ishida, Koichi; Ariyoshi, Masahiko; Fukami, Akihiro*; Sugaya, Kazushi*; Kuroha, Takaya*
JNC TN9410 2004-018, 91 Pages, 2004/05
JNC-TN9410-2004-018.pdf:4.31MB
This paper describes the results of following 2 tests, which were examined as a part of JOYO MK-III function test.1) In-Vessel Coolant Flow Distribution Measurement Test2) Primary System Pressure Drop Measurement Test
Terakado, Tsuguo; Morimoto, Makoto; Izawa, Osamu; Ishida, Koichi; Hoshino, Katsuaki; Suzuki, Shinya; Ito, Hideaki; Aoki, Hiroshi; Odo, Toshihiro
JNC TN9430 2004-003, 87 Pages, 2004/03
JNC-TN9430-2004-003.pdf:2.86MB
This paper describes the results of Secondary Cooling System main pumps test ,which were done as a part of JOYO MK-3 function test. The function tests were cexcuted to get the operating characteristics of secondary cooling system, after the Intermediate Heat Exchangers, Dump Heat Exchangers, secondary main pump motors, pump speed control board and rheostat were replaced in the MK-3 conversion. These tests are composed of six items. These tests purpose are confirmed in the function of the Main pumps, sodium purification system and argon cover gas pressure control system in Secondary Cooling System. (1) SKS-205-1: flow control test, (2) SKS-205-2: flow coast down characteristics test, (3) SKS-205-3: running operation test, (4) SKS-205-4: pump vibration measurement test, (5) SKS-212: secondary sodium purification system electromagnetic-pump flow control test, (6) SKS-213: argon cover gas pressure in secondary cooling system pressure control test function tests are satisfied the design criteria. We have confirmed the system performance of the main pump, secondary sodium purification system and argon cover gas pressure control system in the Secondary Cooling System after the MK-3 conversion.
Ariyoshi, Masahiko; Ishida, Koichi
JNC TN9400 2002-010, 25 Pages, 2002/03
JNC-TN9400-2002-010.pdf:0.67MB
This report is concerning the in-vessel in-service inspection (ISI) technology for the experimental fast reactor JOYO. The present ISI method in JOYO is not able to confirm the integrity of the core structure directly, expecting the visual inspection for the top of core assemblies from above the rotating plug. The purpose of this examination is to progress of the ISI method, and to confirm the integrity of the core structure directly. The core support plate is an important structure and it is selected for the object of in-vessel ISI. From the viewpoint of the influence on the plant, it is regarded impotant the method without all sodium draining, and the remote operation from above of the shielding plug. As a result, following technology is thought promising. (1)Under sodium inspection technique by means of ultrasonic method (it is able to apply in-vessel ISI without all sodium draining). (2)Nondestructive inspection technique by laser based ultrasonic method (it is superior in remote operating) (3)The local sodium discharge mechanism (it makes possible to apply laser based ultra sonic method for under sodium inspection) These technologies were investigated, examined, and the concept applied to ISI in JOYO core support plate was examined. Moreover, the problem when these were applied to in-vessel ISI in JOYO was picked up.
Ishida, Koichi; Maeda, Shigetaka; Saikawa, Takuya*; Masui, Tomohiko*
JNC TN9400 2002-005, 68 Pages, 2002/03
JNC-TN9400-2002-005.pdf:2.14MB
It is essential to evaluate the radiation damage of core structure materials used for core support plate and reactor vessel to maintain the safe operation of nuclear reactor plant. Therefore, surveillance tests for the irradiated specimen have been conducted in the experimental fast reactor JOYO to assure the integrity and to evaluate the life time. Neutron fluence and related spectral information are key palameters in evaluation of irradiation effects on the mechanical properties. They are usually predicted based on the calculation using the DORT two-dimensional transport code. In order to evaluate the calculation accuracy, the surveillance irradiation rigs (SVIRs) with dosimeter sets and gradient-monitor to monitor neutron fluences and temperatures were loaded several positions of the JOYO MK-II core. They were irradiated between 34
and 35 cycle. Based on the verification, the JOYO neutron field was precisely characterized and the calculated neutron flux at the positions of irradiated specimen and those of the core structure components need to be evaluated were corrected based on the experiments. As a result of this study, the following items are concluded: (1)The maximum fast neutron fluence (E
0.1Mev) on surveillance test specimen is determined as 2.07
10
n/cm
at 9th row of the core. (2)The neutron fluences at the positions of surveillance test specimen were higher than those of the core structure components. (3)For the core support plate which seems to be most critical for JOYO life time, the fast neutron fluence at present is 9.3810
n/cm and will reach 2.3110
n/cm at the end of life. The fast neutron fluence of reactor vessel is 3.1210
n/cm at present and will reach 4.8310n/cm at the end of life.
Yamamoto, Kazuhiro; ; ; Kamide, Hideki; *; Maeda, Yukimoto*
JNC TN9410 2001-010, 56 Pages, 2001/03
JNC-TN9410-2001-010.pdf:1.44MB
Flow distribution in the core is planned to measure in the Experimental LMFBR, Joyo. Flow rate in a subassembly will be measured by permanent magnet type electromagnetic flow meter (EMF) which is set at the top of the subassembly by fuel handling machine. In-sodium calibration tests of the EMF were carried out in the Core Component Thermal Hydraulics Test Loop (CCTL). Tests were performed under such various conditions that sodium and permanent magnet temperature were 200, 225, 250, 275
C, and sodium flow rates ranged o to 640 l/min. Tests results are as follows: (1)Calibration curves were obtained at under each temperature condition. The eorrelations were linear and the maximum deviation between the calibration curve and the experimental data was within 
0.4%. (2)The sensitivity of the EMF output (
) at 250C was 29.48 (
V/[l/min]). The uncertainty was l.5% under the nominal flow rate condition (570 l/min). (3) depended on the sodium temperature (T) as follows: = 21.39+1.1610
T-5.0210
T+6.7110
T
(4)Initial change of the after the sodium charge was examined, during few days. The was constant and stable. (5)There was no dependency of impurity concentration (plugging temperature) for the . The calibration curves and temperature dependency are applied to the flow distribution measurement and the evaluation in the Joyo core.
Ishida, Koichi; Ito, Hideaki; Aoyama, Takafumi
no journal, ,
no abstracts in English
Ito, Chikara; Ishida, Koichi; Aoyama, Takafumi; Iguchi, Tetsuo*
no journal, ,
no abstracts in English
Okawachi, Yasushi; Maeda, Shigetaka; Kawahara, Hirotaka; Ishida, Koichi; Aoyama, Takafumi
no journal, ,
no abstracts in English