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Terakado, Tsuguo; Izawa, Osamu
UTNL-R-0466, p.8_1 - 8_11, 2008/03
no abstracts in English
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.
Terakado, Tsuguo; Hoshino, Katsuaki; Suzuki, Shinya; Ito, Hideaki; Aoki, Hiroshi; Odo, Toshihiro
JNC TN9410 2004-008, 55 Pages, 2004/03
JNC-TN9410-2004-008.pdf:1.82MB
The automatic control rod operation system was developed to control the JOYO reactor power automatically in all operation modes(critical approach, cooling system heat up, power ascent and power descent), development began in 1989. Prior to applying, we are examined possibility of apply to the automatic control rod operation guide system which developed in MK-2 operation to get the control rod operation guide data in MK-3 performance tests. The main results are as follows: (1).Critical approach mode in control rod operation guide function will be need tuning of fuzzy algorisms structure for changed MK-3 reactor critical point. (2).Cooling system heet up mode, power ascent mode and power descent mode will be supply to good guidance at MK-3 reactor operation. Because, power change rate and cooling system heet up rate same MK-2 reactor operation. (3).Plant operation guide function will be need change, based on MK-3 reactor operation manual. (4).The automatic control rod operation guide system will be need renewal for system maintainability.
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.
; ; ; Okubo, Toshiyuki
JNC TN9410 99-021, 51 Pages, 1999/10
The automatic control rod operation system was developed to control the JOYO reactor power automatically in all operation modes (critical approach cooling system heat up. power ascent, power descent), development began in 1989. Prior to applying the system verification tests of the automatic control rod operation guide system was conducted during 32nd duty cycles of "JOYO" from Dec.1997 to Feb.1998. The automatic control rod operation guide system consists of the control rod operation guide function and the plant operation guide function. The control rod operation guide function provides information on control rod movement and position, while the plant operation guide function provide guidance for plant operations corresponding to reactor power changes (power ascent or power descent). Control rod insertion or withdrawing are predicted by fuzzy algorisms. The main results obtained via the verification tests are as follows: (1)Control rod operation guide function provided adequate information on control rod operation in all operation modes. (2)Plant operation guide function provided adequate guidance for the plant operation. (3)The technical themes were specificed for the verification tests of the automatic control rod operation system. (4)It was concluded that the automatic control rod operation system can be used to automatically control the JOYO reactor power.
; Sumino, Kozo; Yasu, Tetsunori; ; ; ; Terunuma, Seiichi
PNC TN9410 91-376, 79 Pages, 1991/11
None
PNC TN9410 90-022, 36 Pages, 1989/10
In order to improve operational safety reliability and to reduce operator's load, an automatic control rod system has been developed since 1986 using JOYOO. The phase 1 program, the first stage for the development of the automatic reactor operation system, is to derelop a control rod operation guidance system (Rod Guider) which provided information on control rod operation to plant operator in all the plant operation modes (approaching criticality. heating up. increasing, decreasing and adjusting power). The development of the Rod Guider began in April 1986 and completed in September 1989. All functions of the guider were tested for verification during the 16th duty cycle operation in August 1988. The test result confirm that the guider has an excellent performance to guide the control rod and plant operation during all the plant modes. Interlocking of control rod in case plant operational parameters exceed the limited core characteristics or thermal transient was added to the phase 1. The modified system was tested for verification in a full-scope operator trainning simulator. The test results demenstrated the designed interlocking and confirmed the reguired performance. Items of the limited plant parameters for interlocking on the control rod operation are as follows. (1)Period time : 
50 seconds (apply to heating up mode) (2)Heating up rate at the reactor vessel inlet ; 
20
C/h (apply to heating up and increasing power mode) (3)Temperature difference between the overflow tank and the reactor ressel outlet : 80C (apply to heating up and ...
*; ; *; *; *; *;
PNC TN9410 89-138, 50 Pages, 1989/08
Cover gas monitorring system was installed for obtaining the information of impurities concentration in the primary and secondary cover gas on JOYO, and it has been operated to these days. The experience results are as follows; (1)Increasing of impurities concentration in the cover gas were detected quickly by this system. (2)This system was able to detected the impurities concentration continuously, so it is very useful for investigation the cause of abnormal condition and observation the effect of cover gas purge. (3)This system was modified some points, consequently the measurement performance and reliability of data were advanced more than old one.
; *; *; *; *; *
PNC TN9410 89-052, 54 Pages, 1989/03
Control rod operation guidance system (named Rod Guider) has been developed for the development of the automatic control rod system in experimental reactor Joyo from 1986. The first step of this development was completed. The four sphere's programs (Critical approach, Power ascent, Power adjustment, Power descent) had already been completed and the system heat-up program, remained last sphere's program, was developed continuously. And, Menu program was completed in order to unite five sphere's programs. During the 16th 100 MW duty cycle operation of Joyo, all programs (five sphere's program) were verified. Rod Guider gave adequate guidances for the operators. The results of these developments are following. (1)The program of system heat-up had a very good control. (2)New functions that give various plant operating guidances to the operators, excepting control rod operating guidance, were good. (3)All sphere's programs had a good contact to the menu program. (4)All sphere's programs (Critical approach, System heat-up, Power ascent, Power adjustment, Power descent) were completed.
*; Kotaka, Yoshinori; ; *; ; *; *
PNC TN9410 89-038, 75 Pages, 1989/03
JOYO has been operated smoothly since the initial criticality in 1977. This report describes the actual operation experience of JOYO electric power supply system till Dec. 1988. Major results obtained from operation experience are as follows. (1)Accumulated electric power: 371,290,600 kWh (Oct. 1973-Dec. 1988) (2)The average electric power consumption of several reactor conditions. (a)Operation : about 4,460kW (b)Shut Down : about 3,350kW (c)Periodic Inspection : about 3,000kW (3)Number of loss of external electric power : total 10 times in the following items. (a)Operation : 8 times (b)Shut Down and Periodic Inspection : 2 times
Yamamoto, Masaya; Kawahara, Hirotaka; Terakado, Tsuguo; Aoyama, Takafumi; Sato, Ikken; Ohshima, Hiroyuki
no journal, ,
CDF caused by ATWS (Anticipated Transient Without Scram) event and PLOHS (Protected Loss of Heat Sink) event are majority of CDF in probabilistic safety study at Joyo. Evaluation of these values by reactor dynamic characteristics analysis and natural convection analysis are conducted with a detailed success standard. It was found from evaluation result that CDF are quite low and a dominant core damage accident is UTOP (Unprotected Transient Over Power) event.
Yamamoto, Masaya; Kawahara, Hirotaka; Terakado, Tsuguo; Maeda, Shigetaka; Saito, Hiroto; Aoyama, Takafumi
no journal, ,
Frequency of ATWS (Anticipated Transient Without Scram) and PLOHS(Protected Loss of Heat Sink) are relatively high in Joyo. To identificate the most important accident and to select the subject of Joyo's level 2 PSA (Probabilistic Safety Assessment), frequency of these accidents were estimated through dynamics characteristic analysis and natural circulation analysis with detailed success standard. Moreover, consequence of these accidents were also evaluated. As a results of these evaluation, the most important accident is identified as UTOP and this accident is selected to the subject of Joyo's level 2 PSA.
