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Aoyagi, Kazuhei; Sakurai, Akitaka; Miyara, Nobukatsu; Sugita, Yutaka; Tanai, Kenji
Shigen, Sozai Koenshu (Internet), 6(2), 7 Pages, 2019/09
no abstracts in English
Yokota, Wataru
Kigyo Sapoto Gumma, P. 12, 2004/07
no abstracts in English
Yamaki, Tetsuya; Asano, Masaharu; Yoshida, Masaru
Kogyo Zairyo, 51(4), p.39 - 42, 2003/04
no abstracts in English
; Fujisaku, Kazuhiko*; *; ; Koyama, Tomozo
JNC TN8410 2001-013, 255 Pages, 2001/05
JNC-TN8410-2001-013.pdf:24.24MB
Mock-ups of acid recovery evaporators which are made of Ti-5% Ta alloy and Zr were tested under inactive condition for forty thousands hours to improve a corrosion resistance of acid recovery evaporator in Tokai reprocessing plant (TRP). The mock-up unit was designed and produced referring to the specification of acid recovery evaporator in TRP and the evaporation performance of the mock-up was 1/27 of TRP. A long-term durability of both evaporators was demonstrated by results of operation data, evaporation performance and corrosion resistance. The mock-up unit did not suffer from any trouble during the running test and the operation data such as temperature, flow, concentrations of nitric acid and metal ions were fairly stable within standard condition. As for the corrosion resistance, cracks and local corrosion such as intergranular attack were not observed on both evaporators after the running test, and a corrosion of weld was not selective. The average corrosion rates at measuring points were less than 0.1mm/yr, respectively, however, thickness of the Ti-5% Ta alloy evaporator was slightly reduced at all points of vapor phase region. In addition, from the result by test coupon, it is found that both materials have low susceptibility to stress corrosion cracking in this environment. The destructive inspection showed that the mechanical properties of both materials were not degraded during the running test. Finally, the total running time of the mock-up unit is much more than a maximum running time of acid recovery evaporator made of stainless steel in TRP (nearly 15,000 hours). On the basis of the test results, an excellent durability of Ti-5% Ta alloy and Zr evaporators under was successfully demonstrated throughout the mock-up test from an engineering perspective.
Hama, Katsuhiro; Taniguchi, Naoki; Honda, Akira
JNC TN7430 2000-002, 25 Pages, 2001/01
JNC-TN7430-2000-002.pdf:3.32MB
The burial tests of mild steel and pure titanium were performed in a gallery at Tono mine to assess the corrosion resistance of these materials under goundwater environment. Specimens were placed in the container and immersed into groundwater. After the immersion period, the apperance of the surface of these specimens were observed. The corrosion product of mild steel specimen was analysed by various methods. The average corrosion rate of mild steel for 10 years was assessed by the measurement of the weight loss of carbon steel specimen. The results of the test were summerised as follows : (1)The average corrosion rate of mild steel for 10 years was assessed to be 4.36 
10
mm/y by the weight loss of the specimen. (2)The corrosion product consists of outer porous substance and inner tight corrosion product film. The former contains ferric oxide such as goethite and the latter contains ferrous oxide such as magnetite. (3)The evidence of the initiation of localised corrosion was not observed on the titanium specimens.
Hama, Katsuhiro; Mitsui, Seiichiro; Aoki, Rieko*; Hirose, Ikuro
JNC TN7430 2000-001, 47 Pages, 2000/12
JNC-TN7430-2000-001.pdf:4.09MB
Long-term immersion tests of glass material at ambient temperature (about 18 
C) for 10 years were performed in a gallery at the Tono mine in Japan, in order to assess durability of glass matelial contacted with natural groundwater. The gallery was constructed at a depth of 130 m below ground surface in the Toki Granite. Monolithic glass blocks with dimensions of 10 10 10 mm (cubic type) and of 25 mm in diameter and 8 mm in thickness (disk type: The wall of sample was covered by stainless steel of 1 mm thick.) were used for the tests. Both type of samples with and without clay were put in Teflon vessels, which have small holes on the wall, and inserted into boreholes excavated at the gallery floor. In addition to the immersion tests, static leaching test with cubic type glass and ground water was also performed at the gallery. The samples of each test were collected in time intervals of 6 months, 1 year, 2 years, 3 years and 10 years and were subjected to weight loss measurement and several surface analyses. The results were as follows: (1)Weight losses of each sample were proportional to time intervals. This result is attributable to constant dissolved silica concentration in the ground water during tests. (2)The weight losses of disk type glass were slightly larger than those of cubic type glass. This result is attributable to elemental release from internal cracks of disk type glass, instead of effect of stainless steel on the glass dissolution. (3)The weight losses for the tests with clay were slightly smaller than those for tests without clay. This result is attributable to higher concentration of dissolved silica in pore water of clay.
Takachi, Kazuhiko; Suzuki, Hideaki*
JNC TN8400 99-041, 76 Pages, 1999/11
The buffer material is expected to maintain its low water permeability, self-sealing properties, radionuclides adsorption and retardation properties, thermal conductivity, chemical buffering properties, overpack supporting properties, stress buffering properties, etc. over a long period of time. Natural clay is mentioned as a material that can relatively satisfy above. Among the kinds of natural clay, bentonite when compacted is superior because (1)it has exceptionally low water permeability and properties to control the movement of water in buffer, (2)it fills void spaces in the buffer and fractures in the host rock as it swells upon water uptake, (3)it has the ability to exchange cations and to adsorb cationic radioelements. In order to confirm these functions for the purpose of safety assessment, it is necessary to evaluate buffer properties through laboratory tests and engineering-scale tests, and to make assessments based on the ranges in the data obtained. This report describes the procedures, test conditions, results and examinations on the buffer material of unconfined compression tests, one-dimensional consolidation tests, consolidated-undrained triaxial compression tests and consolidated-undrained triaxial creep tests that aim at getting hold of static mechanical properties. We can get hold of the relationship between the dry density and tensile stress etc. by Brazillian tests, between the dry density and unconfined compressive strength etc. by unconfined compression tests, between the consolidation stress and void ratio etc. by one-dimensional consolidation tests, the stress pass of each effective confining pressure etc. by consolidated-undrained triaxial compression tests and the axial strain rate with time of each axial stress etc. by consolidated-undrained triaxial creep tests.
Kanari, Moriyasu*; Abe, Tetsuya; Tanzawa, Sadamitsu; Shimizu, Katsusuke*; *; *
JAERI-Research 99-012, 21 Pages, 1999/02
JAERI-Research-99-012.pdf:2.26MB
no abstracts in English
; ; Ishibashi, Yuzo; Takeda, Seiichiro; *; Fujisaku, Kazuhiko*; *
PNC TN8410 98-116, 147 Pages, 1998/08
None
; Kano, Shigeki; ; Tachi, Yoshiaki; Hirakawa, Yasushi; Yoshida, Eiichi
PNC TN9410 98-021, 68 Pages, 1998/02
Engineering ceramics have excellent properties such as high strength, high hardness and high heat resistance compared with metallic matelials. To apply the ceramic in fast reactor environment, it is necessary to evaluate the sodium compatibility and the influence of sodium on the mechanical properties of ceramics. In this study, the influence of high temperature sodium on the mechanical properties of sintered ceramics of conventional and high purity Al
O
, SiC, SiAlON, AlN and unidirectional solidified ceramics of AlO/YAG eutectic composite were investigated by means of flexure tests. Test specimens were exposed in liquid sodium at 823K and 923K for 3.6Ms. There were no changes in the flexural strength of the conventional and high purity AlO, AlN and AlO/YAG eutectic composite after the sodium exposure at 823K. On the contrary, the decrease in the flexural strength was observed in SiC and SiAlON. After the sodium exposure at 923K, there were also no changes in the flexural strength of AlN and AlO/YAG eutectic composite. In the conventional and high purity AlO and SiC, the flexural strength decreased and signs of grain boundary corrosion were detected by surface observation. The flexural strength of SiAlON after the sodium exposure at 923K increased instead of severe corrosion. In the specimens those showed no changes in the flexural strength, further exposure in sodium is needed to verify whether the mechanical properties degrade or not. For SiAlON, it is necessary to clarify the reason for the increased strength after the sodium exposure at 923K.
Sazarashi, Masami*; *; Ikeda, Yasuhisa*; Kumagai, Mikio*; *; *
PNC TJ1564 97-002, 20 Pages, 1997/03
None
Tanaka, Satoru*; Nagasaki, Shinya*; *; *; Muraoka, Susumu; *; *; *; *; *; et al.
Nihon Genshiryoku Gakkai-Shi, 39(12), p.1008 - 1018, 1997/00
Times Cited Count：3 Percentile：30.37(Nuclear Science & Technology)no abstracts in English
Sazarashi, Masami*; Ikeda, Yasuhisa*; Kumagai, Mikio*; *; *
PNC TJ1564 96-002, 19 Pages, 1996/03
None
; Kanazawa, Hiroyuki; Togashi, Yoshihiro; ; Nishino, Yasuharu; ; Nakata, Masahito; Amano, Hidetoshi;
JAERI-Research 94-008, 20 Pages, 1994/08
JAERI-Research-94-008.pdf:1.8MB
no abstracts in English
Hayashi, Takumi; Okuno, Kenji
Materials for Advanced Energy Systems & Fission and Fusion Engineering '94, p.205 - 207, 1994/06
no abstracts in English
Iriya, Keishiro*; *
PNC TJ1201 94-004, 335 Pages, 1994/03
no abstracts in English
; ; *; *; Yoshida, Eiichi;
PNC TN9450 92-004, 37 Pages, 1992/06
High Strength Ferritic/Martensitic Steel is one of the cardidate core materials for largescale FBR because of excellent resistance to swelling. This report are presented about the internal pressure creep of High Strength Ferritic/Martensitic Steel based on the R&D results obtained through the activities of material tests. Contents of the data sheet are as follows; (1) Material: High Strength Ferritic/Martensitic Steel Fuel cladding tube (
6.50.47.mm
) (2) Environment: In Air and In Sodium (3) Test temperature: 600 and 650C (4) Hoop stress: 9.48
32.43 kgf/㎜
(5) Number of data: 13 points
Saito, Makoto; Yamada, Kazuo; Kitano, Mitsuaki; Kuroha, Mitsuhiko; Seimiya, Hiroshi
PNC TN8410 92-056, 43 Pages, 1992/03
None
