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Department of Fusion Engineering Research; Department of Materials Science
JAERI-Review 2005-012, 143 Pages, 2005/03
no abstracts in English
Watanabe, Shoichi; Miyoshi, Yoshinori; Yamane, Yuichi
JAERI-Tech 2002-043, 93 Pages, 2002/03
no abstracts in English
Katakai, Akio; Kasai, Noboru; Tamada, Masao; Hasegawa, Shin; Seko, Noriaki; Kawabata, Yukiya*; Onuma, Kenji*; Takeda, Hayato*; Sugo, Takanobu
JAERI-Tech 2002-040, 79 Pages, 2002/03
The present report dealt with experimental methods of adsorbents synthesis, recovery, elution, analysis in experimental equipment for recovery of rare metals from seawater to evaluate performance of the adsorbent synthesized by radiation-induced graft-polymerization. In the adsorbent synthesis, monomers of acrylonitrile and methacryl acid were continuously co-grafted into polymer nonwoven fabric irradiated with electron beam. The grafted nonwoven fabric was amidoximated and treated with alkaline solution in batch processing. The obtained adsorbent fabrics which were cut into 116 sheets of the square, 160 mm 290 mm, were alternatively stacked with spacers to make an adsorbent cassette. In recovery process, a large-sized cage packing 144 pieces of the adsorbent cassette was dipped into sea in the depth of 20 m by using an experimental marine equipment. In the case of a small-sized cage, there are 36 adsorbent cassettes in it. In elution step, first, marine animals which were adhered on the adsorbent cassette were washed out immediately after the adsorbent cassettes were recovered from sea. From every 72 adsorbent cassettes packed into elution unit, second, alkaline and rare metals were fractionally eluted by changing acid concentration in fractional elution equipment. The eluted metals were adsorbed onto a commercial chelate resin to transport them to purificatory factory. Concentrations of metals in eluent and waste solution were analyzed with inducticely coupled plasma atomic emission and mass spectrometry (ICP-AES and ICP-MS). The rare metal distribution in the adsorbent was evaluated by using the same analytical methods.
*; Tanai, Kenji; *
JNC TN8420 2001-007, 86 Pages, 2002/02
The objectives of this study is to identify the research issues, which are to be conducted in the future underground research laboratory, about operation and logistics systems for the planning of future research and development program. The research programs and experiments,etc. were investigated for the geological disposal projects in overseas sedimentary rocks and coastal geological environments aiming to reflect in the future underground research facility plan in Japan. In the investigation, information on the engineered-barrier performance, design and construction of underground facilities, tunnel support, transportation and emplacement, and backfilling technology, etc. were collected. Based on these informations, the purpose, the content, and the result of each investigations and tests were arranged. The strategy and the aim in the entire underground research facility, and the flow of investigations and tests, etc. were also arranged from the purpose, the relations and the sequence of each investigation and experiment, and the usage of results, etc.
; *; ; ; Aoto, Kazumi;
JNC TN9400 2000-059, 43 Pages, 2000/05
The purpose of this study is to understand the material properties of manufacturable high-purity iron and high-purity iron-based alloy in present technology and to get an applicable prospect for the structural and functional material of the frontier fast reactor. Then the about 10kg high-purity iron and iron-based alloy were melted using a cold-crucible induction melting furnace under the ultra-high vacuum. Subsequent to that, the compatibility between the melted material and the high-temperature sodium environment which is a special feature of the fast reactor and tensile property at room and elevated temperatures were investigated using the melted materials. Also, the creep test using the high-purity 50%Cr-Fe alloy at 550C in air in order to understand the high temperature creep property. ln addition, the material properties such as thermal expansion coefficient, specific heat and electrical resistance were measured and to evaluate the outlook for the structural material for the fast reactor. The following results were obtained based on the property test and evaluation. (1)lt was possible to melt the about 10kg high-purity ingot and high-purity 50%Cr-Fe alloy ingot using a cold-crucible induction melting furnace under the ultra-high vacuum. (2)The tensile tests of the high-purity 50%Cr-Fe alloy were performed at room and elevated temperatures in order to understand the deformation behavior. From the experimental results, it was clear that the high-purity 50%Cr-Fe alloy possesses high strength and good ductility at elevated temperatures. (3)The physical properties (the thermal expansion coefficient and specific heat etc.) were measured using the high-purity 50%Cr-Fe alloy. lt was clear that the thermal expansion coefficient of high-purity 50%Cr-Fe alloy was smaller than that of SUS304. (4)From the corrosion test in liquid sodium, the ordinary-purity iron showed the weight loss after corrosion test. However the high-purity iron showed ...
Endo, Hideo; Seki, Masayuki; ; *; *
JNC TN8410 2000-007, 89 Pages, 2000/03
(1)Outline of examination. Various test specimens were made to evaluate and confirm the weld strength properties of the oxide dispersion strengthened (ODS) cladding tube material (martensitic and ferritic steel), which had been manufactured in JFY 1997. The examination consisted of tensile tests (RT,650C, 700C, 800C), internal pressure creep tests, internal pressure burst tests, and a rapid heating burst tests. (2)Examination results. The results of the tensile tests are as follows: (ferritic and martensitic) (a)All test specimens from RT to 700C failed in the tube. The weld zones had not failed. (b)The test specimens at 800C failed in the weld zones. There was little elongation. (ferritic) (a)The weld zone had fine grain structure and carbide precipitates. (martensitic) (a)Carbide had precipitated in the weld zone. From these results, the strength of weld zone decreased extremely at temperatures exceeding the endurance limit (700C) All of the internal pressure burst test specimens and the rapid heating burst test specimens failed in the tube and not the weld zone. (3)The quality assurance method of the test specimens. The weld reliability of the test specimens were confirmed by the process control of the welding conditions, by using control test specimens, and ultrasonic testing. Confirmation of the process control of the welding conditions; current wave, the voltage waveform, the accelerogram, and the displacement ripple in the welding process was recorded to assure an abnormal value had not occurred. (Process control of welding condition) The results the current waveform, voltage waveform, accelerogram, and the displacement waveform were excellent. (test specimens) The weld joint was excellent based on metallography examination. (Ultrasonic testing) The length of the weld joint was measured and found to be adequate. The reliability the weld joint can be assured by using the above-mentioned method.
JRR-3 Operation Division; Research Reactor Utilization Division
JAERI-Tech 2000-027, p.194 - 0, 2000/03
no abstracts in English
Ando, Masaki; Osugi, Toshitaka; Tsujimoto, Kazufumi
JAERI-Data/Code 98-012, 35 Pages, 1998/03
no abstracts in English
Inabe, Teruo; ; ; Yonomoto, Taisuke; *; Akutsu, Cho; ; Iwamura, Takamichi; Okubo, Tsutomu; Osugi, Toshitaka; et al.
JAERI-M 93-106, 104 Pages, 1993/05
no abstracts in English
; ; *; ; ; ; ; ; ; ; et al.
JAERI-M 83-206, 34 Pages, 1983/11
no abstracts in English
; Nekoya, Shinichi; Emori, Kouichi; Ogawa, Masuro; Ouchi, Mitsuo; Okamoto, Yoshizo; Sanokawa, Konomo; *; *; *; et al.
Nihon Genshiryoku Gakkai-Shi, 22(3), p.181 - 188, 1980/00
Times Cited Count:1 Percentile:22.79(Nuclear Science & Technology)no abstracts in English
Hishida, Makoto; Takizuka, Takakazu; Ogawa, Masuro; Nekoya, Shinichi; Emori, Kouichi; Ouchi, Mitsuo; Sanokawa, Konomo
Nihon Genshiryoku Gakkai-Shi, 22(5), p.326 - 334, 1980/00
Times Cited Count:2 Percentile:33.85(Nuclear Science & Technology)no abstracts in English
; ; ; ;
JAERI-M 8137, 113 Pages, 1979/03
no abstracts in English
; *; *
Hoken Butsuri, 5, p.63 - 68, 1970/00
no abstracts in English
Nihon Genshiryoku Gakkai-Shi, 13(4), p.182 - 189, 1970/00
no abstracts in English
JAERI 1139, 26 Pages, 1967/12
no abstracts in English
Yoshitomi, Hiroshi; Nishino, Sho; Tsuji, Tomoya; Fukami, Tomoyo; Takamine, Jun; Umino, Kazushige*; Murayama, Takashi; Tanimura, Yoshihiko
no journal, ,
no abstracts in English