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Fujiwara, Masayuki; Mizuta, Shunji;
JNC TN9400 2000-050, 19 Pages, 2000/04
JNC-TN9400-2000-050.pdf:0.82MB
For evaluating the fast reactor system technology, it is important to evaluate the practical feasibility of ODS ferritic cdaddings, which is the most promising matelials to attain the goal of high coolant temperature and more than 150 GWd/t. Based on the results of their technology development, mass production process with highly economically benefit as well as manufacturing cost estimation of ODS ferritic claddings were preliminarily conducted. From the view point of future utility scale, the cost for manufacturig mother tubes has a dominant factor in the total manufacturing cost. The method to reduce the cost of mother tube manufacturing was also preliminarily investigated.
Akino, Norio; Suzuki, Tomio
Nihon Kikai Gakkai 2000-Nendo Nenji Taikai Koen Rombunshu, Vol.1, p.557 - 558, 2000/00
no abstracts in English
*; *; Tanai, Kenji
JNC TN8400 99-047, 54 Pages, 1999/11
This paper reports on the design process for a carbon-steel overpack as a key component in the engineered barrier system of a deep geological repository described in the 2nd progress report. The results of the research and development regarding design requirements, configuration, manufacturing and inspection of overpack are also described. The concept of a composite overpack composed of two different materials is also considered. First, the design requirements for an overpack and presume environmental and design conditions for a repository are provided. For a candidate material of carbon steel overpack, forging material is selected considering enough experience of using this material in nuclear power boilers and other components. Second, loading conditions after emplacement in a repository are set and the pressure-resistant thickness of overpack is calculated. The corrosion thickness to achieve an assigned 1000 year life time and the required thickness to prevent radiolysis of ground water which might enhance corrosion rate are also determined. As aresult, the total required thickness of a carbon-steel overpack is conservatively estimated to 190 mm. This is a reduction of about 30% from the previous estimate provided in the 1st Progress Report. Additional items that must be considered in manufacturring and operating overpacks (i.e. sealing of vitrified waste, examination of main body and sealing welding, mechanism of handling) are evaluated on the basis of current technology, specific future data needs are identified. With respect to the concept of composite overpack (i.e., an outer vessel to provide corrosion-allowance or corrosion-resistant performance and an inner vessel to provide pressure-resistance), the differences in design concepts between the carbon-steel overpack and such composite overpacks are analyzed. Future data needs and analytical capabilities with respect to overpacks are also summarized.
; ; Ishibashi, Yuzo; Takeda, Seiichiro; *; Fujisaku, Kazuhiko*; *
PNC TN8410 98-116, 147 Pages, 1998/08
None
Koi, Mamoru
PNC TN9410 90-105, 163 Pages, 1990/07
Fatigue and creep crack growth data of SUS304 stainless steel, 2.25Cr-1Mo steel and Mod.9Cr-1Mo steel, which were accumulated in PNC in last several years, were treated as a data base. Average trend equations of crack growth rate were proposed and also statistical analysis was carried out. Finite Elements analysis of center cracked tensioned plate was performed and simplified prediction method of modified J-integral J'(C 
) was developed. 0btained results are summerized as follows: (1)In all tested materials, fatigue crack growth rate and creep crack growth rate were successfully represented using cyclic J-integral range 
J and modified J-integral J', respectivery. (2)In all tested materials, meaningful difference of crack growth rate could not be detected between hot rolled plate and forged material, and also between base metal and welded material. (3)Averaged trend equations of fatigue crack growth rate and creep crack growth rate of all tested materials were proposed on the basis of power low with cyclic J-integral range and modified J-integral, respectively. (4)Assuming that the coefficient and exponent of the above power low obey joint normal distribution, statistical analysis of crack growth rate was carried out and relationship between variance and J, J' were obtained. (5)Simplified method was developed to predict modified J-integral of center cracked tensioned plate. Prediction results show good agreement with experimental results, and this fact suggests that J-integral evaluation method of 3-dimensional surface crack, which has been developed in PNC, has good prediction accuracy.
*
PNC TN9410 90-094, 80 Pages, 1990/06
It is needed for FBR design to know physical properties of the structural materials that will be used for FBR-reactor vessels, -steam generators, and -pipes. In this report, six types of steels that are noted as the structural materials for next steps of FBR are taken up. The six types of steels are as follows ; [SUS 304] [SUS 316 (conventional)] [FBR grade SUS316] [SUS321] [2.25Cr-1Mo steel] [Mod.9Cr-1Mo steel (ASTM A387-91).] Physical properties of the steels are measured on rolled plates made by mills. The measured physical properties are as follows ; [Specific gravity] [Specific heat] [Thermal conductivity] [Thermal expansion] [Young's modulus] [Poisson's ratio.] And also the same kinds of physical properties of S.R. (Stess Relieving) heat treated 2.25Cr-1Mo and Mod.9Cr-1Mo steel plates are measured. Measurement of the physical properties of forgings, pipes, and weld metals of selected types of steels of them will be also carried out in 1990 and all summarized data that will contain the results of this report will be used to determin the criteria design values of the physical properties for the next steps of FBR. (Caution) This report only shows the measurement results of the physical properties of the rolled steel plates but doesn't give the design standards of the physical properties for the next steps of FBR.
JAERI-M 9930, 105 Pages, 1982/02
no abstracts in English
Yamaguchi, Koichi; *; Machi, Sueo
JAERI-M 5455, 43 Pages, 1973/11
no abstracts in English
; ;
Zairyo, 18(162), p.194 - 202, 1967/00
no abstracts in English
; ;
Nihon Genshiryoku Gakkai-Shi, 2, P. 6, 1960/00
no abstracts in English
Tokunaga, Kazutoshi*; Nomiyama, Yukino*; Fukuda, Makoto*; Ezato, Koichiro*; Hirano, Koichiro
no journal, ,
The surface modification of tungsten materials exposed by multiple irradiations of a negative hydrogen ion beam is examined to investigate the influence of the repeated short pulse heat loading. Grid-like cracks are formed on the sample surfaces which the surface is perpendicular to the rolling direction. On the other hand, ellipsoidal cracks are formed on the sample surfaces which the surface is parallel to the rolling direction. These results show crack formation is different depending on the orientation of grain boundaries. The surface modification by plastic formation due to the repeated heat loading in the center area surrounded by the cracks is observed. Furthermore, in the case of high heat loading conditions, a number of cone-like protuberances are melted and resolidified, and deep cracks are formed in the vicinity. The peculiar surface such as the deep cracks and the cone-like protuberances are formed.
Wakai, Eiichi; Noto, Hiroyuki*; Makimura, Shunsuke*; Ishida, Taku*; Furuya, Kazuyuki*; Shibayama, Tamaki*
no journal, ,
Recently, high-entropy alloys have been vigorously researched and developed by research institutes around the world because of their higher strength and ductility than conventional materials due to their atomic mixing ratio and composition. In this study, titanium-based high-entropy alloys (HEAs), TiVCrZrTa, TiVZrTaAl, and TiVCrZrW, were melted by the cold crucible surface melting method and subjected to homogenization heat treatment at 1200
C for 5 hours. Mechanical property tests and properties of these HEAs were investigated, and it was found that the TiVCrZrTa HEAs have relatively better hot-rollability and hot-forgeability than other titanium-based HEAs. The Vickers hardness of these titanium-based HEAs was also found to be considerably higher than that of normal titanium alloys.
