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Terauchi, Makoto; Watanabe, Toshio; Sakakibara, Yasuhide; Tanaka, Teruhisa*; Masudaya, Kosei*
Shiseki "Suzu Tokigama Ato" Kuni Shitei Kinen Shimpojiumu Hokokusho, p.85 - 112, 2010/03
JAEA has had many kinds of meetings for technology exchange willingly as an activity to widely make use of the accumulation of the results of research and development on the way to develop FBR "Monju" in general industry. In this report, one of the local traditional industries of Fukui Prefecture, "Echizen pottery" is featured to show an activity of technological exchange. JAEA established a "technological exchange group on Echizen pottery" to scientifically find out the process until firing ends by analyzing behaviors including temperature distribution and flow condition of the inside of anagama with an analyzing technology (thermal Hydraulics), one of our representative research results. This is a report to show the content which has been discussed and evaluated based on the results of firing experiments and their analysis in this group.
Watanabe, Tomoo; Ozawa, Kazumasa; Otsuka, Jiro; Sasaki, Kazuichi; Sawada, Makoto
JNC TN4440 2005-001, 40 Pages, 2005/07
JNC-TN4440-2005-001.pdf:1.85MB
no abstracts in English
Watanabe, Tomoo; Ozawa, Kazumasa; Otsuka, Jiro; SASAKI, Kazuhito; Sawada, Makoto
JNC TN4410 2004-003, 20 Pages, 2004/07
JNC-TN4410-2004-003.pdf:0.66MB
The FBR cycle training facility consists of sodium handling training facility and maintenance training facility, and is being contributed to train for the operators and maintenance workers of the prototype fast breeder reactor "Monju". So far, some training courses have been added to the both training courses of sodium handling technologies maintenance technologies in every year in order to carry out be significant training for preparation of Monju restarting. As encouragement of the sodium handling technology training in 2003FY, the sodium heat transfer basic course was equipped as the 9th sodium handling training course with the aims of learning basic principal technology regarding sodium heat transfer. While, for the maintenance training course, a named "Monju Systems Learning Training Course", which aims to learn necessary knowledge as the engineers related Monju development, was provided newly in this year as an improvement concerned the maintenance course. In 2003FY, nine sodium handling technology training courses were carried out total 33 times and 235 trainees took part in those training courses. Also, nine training courses concerning the maintenance technology held 15 times and total 113 trainees participated. On the other hand, the 4th special lecture related sodium technology by France sodium school instructor was held on Mar. 15-17 and 34 trainees participated. Consequently, a cumulative trainees since October in 2000 opened the FBR cycle training facility reached to 1,236 so for.
Watanabe, Tomoo; Ozawa, Kazumasa; Sasaki, Kazuichi; Sawada, Makoto
JNC TN4410 2003-010, 21 Pages, 2003/11
JNC-TN4410-2003-010.pdf:1.36MB
The FBR cycle training facility consists of sodium handling training facility and maintenance training facility, and is being contributed training of engineer included operators and maintenance workers for the prototype fast breeder reactor Monju mainly. Both training courses of sodium handling technology and maintenance technology have been improved in every year to provide for Monju restarting. In 2002FY, as a result of reflecting of learning a lesson from the Joyo maintenance building fire accident occurred in Oct.31, 2001 due to spontaneous ignition of sodium, the sodium handling technology license course was added/ Besides, regarding on maintenance training, the general maintenance technology course and the ultrasonic testing course as one of non-destructive inspection course were also added with aims of expanding maintenance training. Consequently, as the present training course concerning FBR cycle training in 2002FY, eight training courses are provided as the sodium training course and also the maintenance training course has the 9 training courses. These training courses were held total 47 times for both sodium and maintenance training courses, i.e. sodium course is 30 times and 17 times is as maintenance course. Concerning total participated numbers of the FBR cycle training in 2002FY is 363 trainees, its breakdown is 247 trainees for 30 times of sodium training courses and 116 trainees is for 17 times of maintenance training courses. In consequence, total participated numbers for three years so far reached to 888 trainees(616 for sodium courses and 272 for maintenance courses).
Watanabe, Tomoo; Ozawa, Kazumasa; ; ;
JNC TN4410 2002-002, 17 Pages, 2002/07
JNC-TN4410-2002-002.pdf:2.49MB
The FBR Cycle Training Facility has been operating since Sep. 2000 for staff of FBR "Monju" and ATR "Fugen" and fireman of the local community, etc.. In 2000, 6 courses of the sodium handling training were held 22 times and a1so eight courses of the maintenance training were 11 times and total participants were 305. In order to grade up the trainings for providing restarting of "Monju", the corresponding training course on sodium piping leakage accident was added as newly sodium handling training course and partial contents of some courses were devised based on some comments by the training discussing committee organized in our center. In 2001, seven sodium handling training courses were carried out 25 times and eight maintenance courses were conducted 11 times and total participated number was 220, i.e. 157 trainees for sodium training courses and 63 trainees for maintenance training courses. Additionally, since a new licensed sodium training course for sodium handling workers included head of worker will be introduced from next year owing to the fire accident of maintenance building in the experimental fast reactor "JOYO" occurred Oct. in 2001, which was coursed by sodium spontaneous combustion due to inefficient handling on tidy up of the sodium handling working, training curriculum, training text and questions for examination are provided as for preparing its course cooperated with Oarai Engineering Center.
Sawada, Makoto; Watanabe, Tomoo; Iwasaki, Ryoji*; Sakakibara, Yasuhide; Nagai, Fumio*
JNC TN4410 2001-006, 53 Pages, 2001/06
JNC-TN4410-2001-006.pdf:9.03MB
The FBR Cycle Comprehensive Training Facility constructed in the International Cooperation and Technology Development Center (in Shiraki area) was opened in earnest since October in 2000. The facility is mainly with the aim of encouraging in technical skills of the operators and maintenance engineers in the prototype fast breeder rector Monju and also is offered to another center in JNC and the local community as a global training facility. Its facility consists of the called sodium school and maintenance school. It is able to study widely sodium huddling technologies, such as chemical and physical properties of sodium, sodium loop operating skill, sodium fire extinguish and treatment sodium compound, and counter training for sodium piping leakage at the sodium school. While the nine study models are installed in the maintenance school and the trainees can learn not only related Monju inherent maintenance technology but also some general maintenance skills. During for six months, October 2000 to March 2001, the six sodium training courses were held 22 times and the eight maintenance courses were carried out 11 times. Total participated number is 305 and 75 trainees among of them joined from the community. To do the training effectively, as the evaluation and analysis system of training result, the skill confirmation test of which aims to have a grasp training results quantitatively by themselves was devised and was introduced. Almost of the training course's results were improved remarkably such as that average point after getting training were risen level of 80 point from level of 40 point before training. Like this, it is obvious that their skills of the Monju operators and maintenance engineers are advancing toward to Monju restarting.
Watanabe, Tomoo; Ueda, Masashi; ; ; Terunuma, Seiichi
Saikuru Kiko Giho, (9), p.17 - 28, 2000/12
None
Miyahara, Shinya; ; Watanabe, Tomoo; Haga, Kazuo; Himeno, Yoshiaki
Nuclear Technology, 97(2), p.177 - 185, 1992/02
Times Cited Count：7 Percentile：57.42(Nuclear Science & Technology)None
Haga, Kazuo; ; Watanabe, Tomoo; ; Himeno, Yoshiaki
PNC TN9410 91-091, 13 Pages, 1991/01
A series of tests has been conducted to obtain gas-liquid equilibrium partition coefficient Kd of volatile fission products such as cesium,iodine,and tellurium in sodium. In the test a sodium pool mixed with an FP simulant was heated by an electric furnace and the solvent of trapped vapors by filters was quantitatively analyzed. The results are,(1)Cs shows the highest Kd (20-100), (2)Kd of iodine scatters as wide as 0.02-0.5at 450
and 0.3-0.8 at 650,(3)the Kd values of Cs and I agree well with the theoretical ones reported by Castleman et al., and (4)if a sodium-telluride which is hard to vaporize than pure Te is assumed, measured Kd of Te agrees with that theoretical.
*; *
PNC TN9410 86-104, 216 Pages, 1986/08
Failure propagation tests have been conducted by use of the Steam Generator Safety Test Facility (SWAT-3) at O-arai Engineerng Center since 1979 to validate the design basis leak (DBL) for a steam generator of a prototype LMFBR, Monju. Reported here are the results and conclusions of Runs 18 and 19, performed in March 1983 and April 1984, respectively. Run 18 simulated the fallure propagation under superheater conditions using austenitic stainless steel JIS-SUS321 as a tube material. Test results revealed that the leak progression in the superheater was so slow that reactor operators will have sufficient time to shut down the steam generator system before it reached a large leak. Run 19 was planned to clarify the potential of overheating failure of the tubes in the evaporator ipper region. In the test, no failure occurred on the tubes where prototypical thermal conditions lncluding tube cooling from inside were simulated. It was concluded, therefore, that the potential was extremely low in the actual plant owing to the internal cooling effect. The failure propagation test program for Monju terminated by Run 19. The following conclusions were obtained from the entire program: (1)Scenarios of leak progression from a small leak to a large leak were clarified under the Monju steam generator conditions. (2)The leak propagation analysjs code, LEAP, were validated by use of the SWAT-3 test data. Furthermore, the LEAP analysis ensured sufficient conservatism of the Monju DBL, 1+3 DEGs.
*; *; *
PNC TN941 85-127, 92 Pages, 1985/08
RECT-II (the Removal test of reaction products by cold trap) was conducted by use of SWAT-3 (the Steam Generator Safety Test Facility) at PNC in order to construct the post-accident operation of steam generators of the prototype FBR Monju and a larger plant following it. In prior to the test, some amount of the sodium-water reaction products (SWRP) generated in the water injection test (Run 18) was remained in the sodium system. An objective of the test is to confirm the purifying method to remove SWRP by hot sodium circulating through a cold trap (CT). A meshless type cold trap was selected to avoid choking by impurities and to enable efficient SWRP removal. RECT-II started on April 4, 1984 and terminated on April 26 when the plugging temperature decreased to 187
C. Major results obtained in the test are as follows: (1)Post-test observation revealed that the SWRP having remained at the bottom of the evaporator and the sodium outlet pipe were completely removed through the purification operation. (2)Hence, it is concluded that after the hot draining the SWRP of 14 kg-H
0 remained in the sodium system out of that generated by the 42 kg-H0 injection and that almost all of the former was removed through the operation. (3)However, some amount of the hydrocarbon-oxide and SWRP in the slit articles simulating crevice and stagnant region still remained after the operation. Then it is concluded that it is insufficient to remove SWRP in crevice and stagnant region by the circulation of hot sodium. (4)A mass transfer coefficient of oxygen is evaluated as 2 
10
[g/(mm H ppm)] if the cross section of the evaporator and inner surface of the 8 inch horizontal pipe are assumed to be the entire surface area of SWRP. (5)Since the choking of the cold trap degrades the efficient SWRP removal, it is essential to develop a cold trap which hardly chokes and easily regenerates even after choking; one of answers for this request is a ...
*; *; *; *; *; *
PNC TN941 80-27, 272 Pages, 1980/02
A series of intermediate leak wastage tests were conducted using Large Leak Sodium-Water Reaction Test Rig (SWAT-1) at O-arai Engineering Center. The purpose of these tests was to clarify the mechanism of failure propagation to adjacent heat transfer tubes due to the flame jet of leak water in the steam generator of LMFBR. Then the value of the design basis leak for the steam generator should be proposed. The wastage rate, the size of secondary failure, and the multi-tube wastage phenomenon were mainly discussed on the basis of eleven test results, in which the water leak rate was in the range of 10
200 g/sec. Findings are as follows ; (1)The wastage rate depends on L/D (L: nozzle to target distance, D : nozzle diameter) and has a maximum value of 7 10
mm/sec at L/D=2030. (2)The time of secondary failure occurring in the tube bunk structure does not depend on the water leak rate. (3)The maximum diameter of the penetration hole obtained in these tests was 19mm
. (4)The dominant mechanism of the failure propagation is not overheating but wastage in the intermediate leak region. (5)The extent of multi-tube wastage increases with the increasing leak rate. Six tubes were damaged considerably at the leak rate of 200 g/sec.
Shiina, Akira; Yamashita, Takuya; Watanabe, Toshio; Imai, Yoshiyuki*; Ono, Koichi*
no journal, ,
no abstracts in English
