Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Morihira, Masayuki; Ozawa, Takayuki; ; Suzuki, Masahiro; Shigetome, Yoshiaki; Kihara, Yoshiyuki; Kono, Shusaku
JNC TN8400 2004-014, 193 Pages, 2004/07
JNC-TN8400-2004-014.pdf:24.52MB
The collaboration project concerning sphere-pac fuel among JNC, Swiss PSI (Paul Scherrer Institut) and Dutch NRG (Nuclear Research and Consultancy Group) is in progress.Final target of the project is comparative irradiation tests of Sphere-pac fuel in the HFR (High Flux Reactor) in Petten in the Netherlands with pellet type fuel and vipack fuel. Total 16 fuel segments (8 pins) of these three types of fuel are planned to be irradiated. Two sphere-pac fuel segments contain 5%Np in addition to 20%Pu-MOX. Other segments contain no Np. Fabrication of irradiation test pins was completed till May 2003 in PSI. After transportation of the fuel pins to Petten, two times of irradiation were performed in January to March in 2004 and now post irradiation tests are in progress. Later two irradiations will be done till the autumn in 2004.This report summarized the basic plan, fuel design, and fabrication of irradiation test pins concerning this collaboration project.
Seki, Masayuki; Kono, Shusaku
Nihon Genshiryoku Gakkai Wabun Rombunshi, 3(1), p.95 - 105, 2004/03
None
Seki, Masayuki; Kono, Shusaku; Kihara, Yoshiyuki; Kaito, Takeji; Ukai, Shigeharu; Hirako, Kazuhiko*
Journal of Nuclear Materials, 329-333, p.1534 - 1538, 2004/00
Times Cited Count：33 Percentile：87.58(Materials Science, Multidisciplinary)Welding technology for fuel cladding and end-plugs made of ODS steel has been developed to apply for the fast reactor fuel pin fabrication at Tokai-works of JNC. A pressurized resistance welding (PRW) method is utilized as solid phase welding. The method is based on electrical resistance heating of the components while maintaining a continuous force sufficient to forge weld without melting of the components. The contact force between cladding and end-plug is given by pneumatic-hydraulic system. The welding parameters, e.g. electric current, voltage and contact force, are controlled by a programmable system. The appropriate conditions are selected to be a 700 Kgf contact load with 16 kA current for 20 ms after holding for pre-heating by 6 kA current. For relieving the residual stress, the post-welded heat-treatment is performed in the condition of tempering at 1053 K for 10 min. A metallugically bonded welds has been formed by the PRW method, keeping the original dispersed distributio
Kono, Shusaku; Seki, Masayuki; Fujio, Ishibashi,; Hirako, Kazuhiko*; Tsukada, Tatsuya*
JNC TN8430 2003-010, 28 Pages, 2003/07
JNC-TN8430-2003-010.pdf:2.18MB
The defect occurred at the resistance welding zone is very minute and therefore cannot be identified by X-ray inspection. Then, the ultrasonic examination method, in which the resolution of the defect is higher than that of the X-ray inspection method, has been developed. The ultrasonic wave sounds straight easier in the material than X rays, excels in defecting the micro defect. However, the pulse amplitude of ultrasonic wave is influenced by the shape and direction of the defect. Then, the ultrasonic inspection equipement, in which the ultrasonic probe and the sample rotation axis are controlled to drive with the pulse motor and the defect data (position and size)are analized by image processing ultrasonic signal, was developed to measure the shape and the position of defect accurately. However, an ultrasonic examination method is the comparative inspection method. Therefore, the standard test block or the reference block is indispensable to guarantee the defectability and the ultrasonic echo sensibility of the inspection device. The standard test block is provided in JIS etc, it is needed to defect the peculiar defect occurred at the resistance welding zone. Then, the method of processing a standard test block is examined, the standard test block was made experimentally by electric discharge processing and diffusion junction method. The ultrasonic echo sensitivity and the threshold for image processing were proofread by using the standard test block, the ultrasonic inspection and metallographic inspection were executed. Comparing the ultrasonic inspection results with the metallographic inspection results, the detectability of defect depth and the measurement accuracy were proved to be 3
m and with errors less than 10m respectively. From these results, the effectireness of proofreading the ultrasonic inspection condition by the standard test block was confirmed. Moreover, it was confirmed that there was a peculiar relationship between the depth ...
Yamawaki, Michio*; Konashi, Kenji*; Kono, Shusaku; Kitamura, Ryoich
JNC TY8400 2003-006, 38 Pages, 2003/05
JNC-TY8400-2003-006.pdf:2.66MB
The actinide-hydride fuel is an excellent integral fuel - moderator system. The concentration of hydrogen in the actinide hydride is comparable to that of hydrogen in liquid water of LWR cores. We have proposed new type of reactor core to reduce the amoun
Kono, Shusaku; Seki, Masayuki; Ishibashi, Fujio; Hirako, Kazuhiko*; Tsukada, Tatsuya*
JNC TN8410 2003-009, 108 Pages, 2003/05
JNC-TN8410-2003-009.pdf:9.54MB
The welding condition and the heat-treatment condition were optimized to evaluate welding properties of the martensitic ODS steel cladding tube. The test pieces for evaluation of strength properties of the welded zone were produced by the optimized welding condition. In order to evaluate the strength of the welded zone, the internal creep rapture test, the single axis creep rapture test, the burst test and the tensile test were conducted. Following results were obtained in these tests. (1) Weld ability. An excellent welding characteristic was observed. The micro cracks, etc. were not served at the joint starting point. The joint starting poonts were connected uniformly with errors less than 0.05mm. It is considered that an excellent welding characteristic was result of homogeneous micro structure of cladding material. (2) End plug material. In case of the material of end plug was martensitic ODS steel as same as that of cladding tube, the micro structure and the precipitation state carbide near the welded zone were found to be almost same as that of cladding tube. (3) Optimization of heat-treatment condition. The heat treatments of normalizing (10501
C) and tempering (780C) were performed after welding and the micro structure near the welded zone was the isometric structure with low dislocation density, the precipitation state of carbide was uniform as same as that of cladding tube. These heat treatments can relax the residual stress accumulated when welding; it is considered that these heat treatments after welding are indispensable. (4) Strength of welded zone. The strength of the welded zone was found to be equal to that of cladding tube in all the strength tests. Therefore, it is concluded that the welding technology for the martensitic ODS steel is completed.
Kato, Masato; ; ; *; Tamura, Tetsuya*; Sunaoshi, Takeo*; *
JNC TN8400 2003-014, 151 Pages, 2003/05
JNC-TN8400-2003-014.PDF:11.66MB
JNC has been developing low decontaminated MOX fuel containing Miner Actinide (MA) for advanced FBR. It is very important for the fuel development to investigate sintering properties and physical properties of the fuel. In this paper, the influence of oxygen partial pressure during sintering on sintering behavior and migration of MA and FPs in MOX pellets containing Np/Am and simulated FP have been studied. The results of the examination are as follows. (1)The pellets sintered in atmosphere of high oxygen partial pressure have homogeneous composition and large grain size. Additive Ln elements promote homogenization and restrain grain growth in the pellets. (2)O/M ratio of the sintered pellets could be controlled to 1.95 by heat treatment of appropriate temperature, time and oxygen partial pressure. Phase separation was observed in the pellets with O/M=1.95. (3)Pu-Am-Ln compounds precipitated in the pellets with Ln. The form of precipitation of Pu-Am-Ln compounds changed depending on sintering conditions. (4)Y and Zr were distributed homogeneously in the pellet not depending on the sintering condition and it is considered that Ru, Rh and Pd are precipitated with metallic particle or alloy of this particles.
; Seki, Masayuki; ; *; *
JNC TN8430 2003-003, 249 Pages, 2003/04
JNC-TN8430-2003-003.pdf:247.75MB
Irradiation test in BOR-60 at RIAR to judge practical use prospect of ODS cladding tube at early stage is planned as Japan-Russia a joint research. RIAR does fuel design of fuel pin used for this joint research. JNC manufactures ODS cladding tube and bar materials (two steel kind of martensite and ferrite), upper endplug production. They are welded by pressurized resistance welding, and are inspected in JNC Tokai, transported to RIAR. And RIAR manufactures vibration packing fuel pin. On the upper endplug welding by pressurized resistance welding method, we worked on the problems such as decision of welding condition by changing the size and crystallization of cladding tube and the design of endplug, and the chucking device remodeling to correspond to the long scale cladding tube welding system (included handling) and of quality assurance method. Especially, use of long scale cladding tube caused problem that bending transformation occurred in cladding tube by welding pressure. However, we solved this problem by shortening the distance of cladding tube colette chuck and pressure receiving, and by putting the sleeve in an internal spece of welding machine, losing the bending of cladding tube. Moreover, welding defects were occurred by the difference of an inside state, an inside defect, and recrystallization of cladding tube. We solved the problem by inside grinding for the edge of tube, angle beam method by ultrasonic wave, and ultrasonic wave form confirmation. Manufacturing process with long scale claddng tube including heat-treatment to remove combustion return and remaining stress was established besides, Afterwards, welding of ODS cladding tube and upper endplug. As the quality assurance system, we constructed [Documented procedure (referred to JOYO)] based on [Document of the QA plan] by OEC. Welding and inspection were executed by the document procedure. It is thought that the quality assurance method become references for the irradiation test in JOYO ...
; ; Shigetome, Yoshiaki; Kono, Shusaku;
JNC TN8410 2003-002, 29 Pages, 2003/02
Japan Nuclear Cycle Development institute (JNC) has conducted the collaboration concerning vibro-packed fuels with Paul Scherrer Institut (PSI) in Switzerland and Nuclear Research & consultancy Group (NRG) in the Netherlands. The project "Research and Development of Advanced Sphere-pac fuel" is called FUJI (FUel irradiations for JNC and PSI) Project. In this project, three types of fuels that are sphere-pac fuels, vipac fuels, and pelletized fuels will be irradiated in the High Flux Reactor (HFR) to compare the fuel performance. Based on the drawing which has been agreed among three parties, fabrication of the pin components and welding of the upper and lower connection endplugs were performed in accordance with ISO-9001 in JNC. This report describes data of fabricated pin components, results of welding qualification tests, and quality assurance of the welded components. The fabrication of pin components was successfully completed and they were delivered to PSI in October 2002.
; Seki, Masayuki; ; *; *
JNC TN8410 2002-013, 88 Pages, 2003/01
JNC-TN8410-2002-013.pdf:39.21MB
In the internal creep rapture test, the breakage was caused at the resistance welded area of ODS steel cladding tube. In order to investigate the cause of the breakage, the microstructure of the replica specimens extracted from the welded area was observed by transmission electron microscopy (TEM), and the residual stress near the welded area was measured by X-ray diffraction method (XRD). Following results were obtained in this test. (1)Presumption of the cause of the breakage in the internal creep rapture test for ferritic ODS steel. The breakage was supposed to cause by the stress concentration of the micro crack in the folded area of welding boundary resistance welding, and the grain sliding along the elongated grain boundary. These can be improved by optimizing welding conditions as plunging length of cladding, angle melting face etc. (2)Presumption of the cause of the breakage in the internal creep rapture test for martensitic ODS steel. The breakage was supposed to cause by the declination of high temperature strength of ferritic steel for end plug, the micro crack caused at the folded area of melding and the strength declination of the melded boundary. These can be improved by use of ODS steel for end plug, stress release or re-annealing and re-tempering at about 780C after melding in order to reduce coarsening of aggregation of carbide. (3)Measurement results of residual stress. The residual stress both of ferritic and martensitic ODS steel at the resistance-welded area was 500MPa at a maximum. In heat treating applied after melding, the residual stress was 64MPa and for ferritic ODS steel it was 150MPa at the surface, and 170MPa at the cross section of the resistance-welded area, and at a maximum. Therefore heat treatment conditions need to be adjusted as lengthening more heat treatment time etc.
Morimoto, Kyoichi; Kato, Masato; Nishiyama, Motokuni; Endo, Hideo; Kono, Shusaku; Uno, Hiroki*; Tamura, Tetsuya*; Sugata, Hiromasa*
JNC TN8400 2003-011, 32 Pages, 2003/01
JNC-TN8400-2003-011.pdf:0.62MB
MOX fuel containing Neptunium is being developed as candidate fuel for an advanced nuclear fuel recycle. In this report, influence of Np on the sintering behavior, phase separation behavior of MOX fuel pellets and the homogeneity of MOX fuel pellets were evaluated. It was observed that the high Np containing pellets had a low sintered density and the microstructure changes of the pellets during the sintering were slow compared with MOX without Np. The pellets were also analyzed via Ceramography, X-ray diffraction measurement and an electron probe microanalysis. The phase separation behavior of MOX with Np was similar to that of MOX. The homogeneity of the pellet produced with this experiment was acceptable to the fuel specification.
Morimoto, Kyoichi; Kato, Masato; Kono, Shusaku; Sugata, Hiromasa*; Sunaoshi, Takeo*
Abstract, PB63, (PB63), 0 Pages, 2003/00
None
Seki, Masayuki; ; Ukai, Shigeharu; Kaito, Takeji; Hirako, Kazuhiko*
Proceedings of 11th International Conference on Fusion Reactor Materials (ICFRM-11), 87 Pages, 2003/00
None
Shigetome, Yoshiaki; Kono, Shusaku; Hellwig, C.*; Heimgartner, P.*
Proceedings of International Conference on Advanced Nuclear Energy and Fuel Cycle Systems (GLOBAL 2003) (CD-ROM), p.1342 - 1347, 2003/00
None
Suzuki, Masahiro; ; Ojima, Hisao
CIMTEC2002(2rd International Conference:Computational Modelling and Simulation of Materials), 0 Pages, 2002/00
None
Ozawa, Takayuki; Abe, Tomoyuki; Kono, Shusaku; Franz, I.*; Hannu Wall*
P.279, P. 279, 2002/00
None
; ; ; ; ; *; *
JNC TN8400 2001-026, 29 Pages, 2001/12
JNC-TN8400-2001-026.pdf:0.99MB
The measurement condition by spectrophotometry was evaluated to measure Np content in MOX fuel containing Np. The Np concentration was obtained by measuring the 727nm absorption peak, after the valence of Np in the sample solution was adjusted to the Np(Ⅳ). The calibration curve showed the linearity up to Np concentration 0.8mg/ml. Though Pu and U quantity were respectively added to the Np solution to 30 times and 60 times of Np concentration, there was no effect to the Np analysis. By using this method, relative standard deviation (RSD) of the analyzed values of Np content for 2%Np - MOX fuel was about 4%. In addition, It was confirmed that the Np content could be measured without separating Np from Pu and U. This method can be sufficiently applied as a quick simple method to analyze Np content in MOX fuel containing Np.
; ; ; ; ; ;
JNC TY9400 2001-023, 362 Pages, 2001/07
JNC-TY9400-2001-023.pdf:16.74MB
no abstracts in English
; Kono, Shusaku; Ono, Kiyoshi
PROCEEDINGS(058), 0 Pages, 2001/00
None
Morimoto, Kyoichi; ; Kato, Masato; ;
Proceedings of International Conference on; Back-End of the Fuel Cycle; From Research to Solutions (GLOBAL 2001), 0 Pages, 2001/00
None
