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JAEA Reports

Compatibility tests between molten salts and metal materials, 2

Shiina, Yasuaki; Kuriki, Yoshiro*

JAERI-Tech 2003-070, 47 Pages, 2003/08

JAERI-Tech-2003-070.pdf:14.83MB

no abstracts in English

JAEA Reports

The Activity of sulfate reducing bacteria in bentonite and the effect of hydrogen sulfide on the corrosion of candidate materials for overpacks

Taniguchi, Naoki; Kawasaki, Manabu*; Fujiwara, Kazuo*

JNC TN8400 2001-011, 62 Pages, 2001/03

JNC-TN8400-2001-011.pdf:5.67MB

The corrosion of metallic materials used in natural environment are sometimes affected by microbial action. It is apprehended that microorganism living in deep underground or brought from ground surface during excavation makes an impact on overpack material for geological disposal of high-level radioactive waste. Sulfate reducing bacteria (SRB) is known to be one of the most representative microorganism which affects the corrosion of metals. In this study, the behavior of growth of SRB was investigated at first under the presence of bentonite as a main component of buffer material which encloses the overpack. The results of the tests showed that the population of SRB after the culture in synthetic sea water mixed with bentonite decreased with increasing the ratio of bentonite/solution. SRB was hardly grown in medium whose bentonite/solution ratio exceeded 1000g/l. As a conservative case, the effects of sulfide on the corrosion of overpack materials were also studied assuming high activity of SRB. Carbon steel, copper and titanium specimens were immersed in synthetic sea water purging 0.1MPa H$$_{2}$$S gas and the corrosion behavior was compared with the results in N$$_{2}$$ gas purging environment. Obvious effect of sulfide on the corrosion of carbon steel was not observed, but the corrosion rates of copper specimens were accelerated several hundred times by purging H$$_{2}$$S gas. The absorption of hydrogen into titanium specimens was not affected by purging H$$_{2}$$S gas, but the difference of hydrogen absorption between pure titanium and titanium alloy containing 0.06%-Pd was observed.

JAEA Reports

None

*; Akatsuka, Hiroshi*; *; Suzuki, Tatsuya*; *; *;

JNC TY9400 2000-009, 41 Pages, 2000/03

JNC-TY9400-2000-009.pdf:1.22MB

no abstracts in English

JAEA Reports

Investigations on the evaluation methods of the irradiation performance of FBR metallic fuel for the design study

;

JNC TN9400 2000-031, 15 Pages, 2000/03

JNC-TN9400-2000-031.pdf:0.53MB

For the irradiation performance of metallic fuel, many of the analyses were conducted in USA using EBR-l and EBR-II. ln this study, based on the published data and papers on the above results, the appropriate methods to the evaluation of the irradiation performance of FBR metallic fuel for the design study were considered, as the fbasibility study for FBR. The followings are the targets in this work; (1)deformation of cladding (2)deformation of fuel slug (3)FP gas release (4)fluctuation of the bonding Na level in the fuel pin (5)FCCI

JAEA Reports

Study on cathodic reaction control efficiency by low alloy steels

Akashi, Masatsune*; Fukaya, Yuichi*; Asano, Hidekazu*

JNC TJ8400 2000-015, 46 Pages, 2000/02

JNC-TJ8400-2000-015.pdf:2.96MB

Difference of hydrogen generation phenomena on the surface of the Steels were not observed between carbon steel, atmospheric corrosion resisting steel and 5%-Ni steel. Rust layer was formed on these three-type of steels by steam oxidation method. And the chemical composition of the rust for the steels were basically two (2) layers structure for the previous two steels as hematite (Fe$$_{2}$$O$$_{3}$$) based for the outer layer and magnetite (Fe$$_{3}$$O$$_{4}$$) based for the inner layer. And for the last steel, it had three (3) layer in the rust as hematite (Fe$$_{2}$$O$$_{3}$$) based for the outer layer, magnetite (Fe$$_{3}$$O$$_{4}$$) based for the intermediate layer and Ni based layer for the inner layer. These steels showed mostly same Tafel gradient in their cathodic polarization curves compare with that for no rust specimens. However, the exchange current density which reaction is assumed as a hydrogen generation reaction was largely increased. The cathodic reaction for each steels whose surface is covered by magnetite layer might be accelerated, then the corrosion rate was considered as accelerated, too.

JAEA Reports

Study on cathodic reaction control efficiency by low alloy steels

Akashi, Masatsune*; Fukaya, Yuichi*; Asano, Hidekazu*

JNC TJ8400 2000-014, 22 Pages, 2000/02

JNC-TJ8400-2000-014.pdf:0.75MB

Difference of hydrogen generation phenomena on the surface of the Steels were not observed between carbon steel, atmospheric corrosion resisting steel and 5%-Ni steel. Rust layer was formed on these three-type of steels by steam oxidation method. And the chemical composition of the rust for the steels were basically two(2) layers structure for the previous two steels as hematite(Fe$$_{2}$$O$$_{3}$$) based for the outer layer and magnetite(Fe$$_{3}$$O$$_{4}$$) based for the inner layer. And for the last steel, it had three(3) layer in the rust as hematite(Fe$$_{2}$$O$$_{3}$$) based for the outer layer, magnetite(Fe$$_{3}$$O$$_{4}$$) based for the intermediate layer and Ni based layer for the inner layer. These steels showed mostly same Tafel gradient in their cathodic polarization curves compare with that for no rust specimens. However, the exchange current density which reaction is assumed as a hydrogen generation reaction was largely increased. The cathodic reaction for each steels whose surface is covered by magnetite layer might be accelerated, then the corrosion rate was considered as accelerated, too.

JAEA Reports

Study on low temperature plasma driven permeation of hydrogen

JAERI-Research 98-019, 181 Pages, 1998/03

JAERI-Research-98-019.pdf:5.85MB

no abstracts in English

JAEA Reports

None

*; *; *; *; *; *; *

PNC TJ1010 98-001, 221 Pages, 1998/02

PNC-TJ1010-98-001.pdf:16.09MB

None

JAEA Reports

Corrosion behaviors of ceramics against liquid sodium; Sodium corrosion characteristics of sintering additives

Tachi, Yoshiaki; Hirakawa, Yasushi; Kano, Shigeki; Yoshida, Eiichi

PNC TN9410 98-054, 57 Pages, 1998/01

PNC-TN9410-98-054.pdf:20.35MB

It has been progressed as the Frontier Materials Research to research and develop ceramics to apply for several components of fast breeder reactor using liquid sodium as coolant instead of metallic materials. Grain boundary of ceramics has peculiar properties compared with matrix because most of ceramics are produced by hardening and firing their raw powders. Some previous researchers indicated that ceramics were mainly corroded at grain boundaries by liquid sodium, and ceramics could not be used under corrosive environment. Thus, it is the most important for the usage of ceramics in liquid sodium to improve corrosion resistance of grain boundaries. In order to develop the advanced ceramics having good sodium corrosion resistance among fine ceramics, which have recently been progressed in quality and characteristics remarkably, sodium corrosion behaviors of typical sintering additives such as MgO, Y$$_{2}$$O$$_{3}$$ and AIN etc. have been examined and evaluated. As a result, the followings have been clarified and some useful knowledge about developing advanced ceramics having good corrosion resistance against liquid sodium has been obtained. (1)Sodium corrosion behavior of MgO depended on Si content. Samples containing large amount of Si were corroded severely by liquid sodium, whereas others with low Si contents showed good corrosion resistance. (2)Both Y$$_{2}$$O$$_{3}$$ and AIN, which contained little Si, showed good sodium corrosion resistance. (3)MgO, Y$$_{2}$$O$$_{3}$$ and AIN ale thought to be corroded by liquid sodium, if they contain some SiO$$_{2}$$. Therefore, in order to improve sodium corrosion resistance, it is very important for these ceramics to prevent the contamination of matrix with SiO$$_{2}$$ through purity contlol of their raw powders.

JAEA Reports

None

*; *; ; Takeda, Seiichiro

PNC TN8410 97-433, 49 Pages, 1997/12

PNC-TN8410-97-433.pdf:1.44MB

None

JAEA Reports

Evaluation of electronic states of implanted materials by molecular orbital calculation

Saito, Junichi; Kano, Shigeki

PNC TN9410 97-073, 69 Pages, 1997/07

PNC-TN9410-97-073.pdf:1.74MB

In order to understand the effect of implanted atom in ceramics and metals on the sodium corrosion, the electronic structures of un-implanted and implanted materials were calculated using DV-X$$alpha$$ cluster method which was one of molecular orbital calculations. The calculated materials were $$beta$$-Si$$_{3}$$N$$_{4}$$, $$alpha$$-SiC and $$beta$$-SiC as ceramics, and f.c.c.Fe, b.c.c.Fe and b.c.c. Nb as metals. An Fe, Mo and Hf atom for ceramics, and N atom for metals were selected as implanted atoms. It is known that these metallic elements have exhibited the excellent corrosion resistance against liquid sodium in previous experiments. The summary of results is shown as follows. Energy levels of implanted atom appeared in or near energy band gap in ceramics. The change of ionicities of each element which showed amount of transferred charges and bond order which showed the covalent bond strength between atoms depended on substrates and implanted atoms. The strength of ionic bonding between atoms reduced in $$beta$$-Si$$_{3}$$N$$_{4}$$, as ionicities of constituent atom decreased by the implanted atom. The decreases of ionicity depended on implanted atoms and Hf implantation showed the largest decrease in implanted atoms. The bond order in $$beta$$-Si$$_{3}$$N$$_{4}$$ and $$alpha$$-SiC decreased by the implantation. When the implanted atom occupied at substitutional site in $$beta$$-SiC, the ionicities decreased but the bond order increased. Electron state densities of s and p components of implanted N atom appeared lower energy level than that of d component of constituent Fe (or Nb) atoms. The charge transfer took place to N atom from surrounding Fe (or Nb) atoms. Thus the ionicity of N atom was larger than mother metal. The bond order between mother elements reduced by N implantation. In particularly, there were significant decreases of bond order in b.c.c. Fe and b.c.c. Nb. Hence, the bond order in whole cluster decreased largely except for f.c.c. Fe. Consequently, it is ...

JAEA Reports

None

*; *; *; *; *; *; *

PNC TJ1010 97-002, 170 Pages, 1997/02

PNC-TJ1010-97-002.pdf:7.94MB

None

JAEA Reports

Materials properties data sheet (No.B 01); Tensile properties data on FBR grade SUS316 (Base Metal)

; ; *; *; *; *; Yoshida, Eiichi

PNC TN9450 91-008, 38 Pages, 1991/09

PNC-TN9450-91-008.pdf:0.75MB

In order to advancement in materials strength standard on elevated temperature design guide of the FBRs and evaluation method of materials strength behavior, this report are presented about the tensile properties of FBR grade SUS316, based on the R&D results obtained through the activities of material tests. Contents of the data sheet are as follows; (1)Material : FBR grade SUS316 (Base Metal) B7 Heat 1,000mm$$times$$1,000㎜$$times$$50mm$$^{t}$$(Plate) B8 Heat 1,000㎜$$times$$1,000mm$$times$$40mm$$^{t}$$(Plate) B9 Heat 1,000mm$$times$$1,000㎜$$times$$25㎜$$^{t}$$(Plate) (2)Test temperature : RT$$sim$$750$$^{circ}$$C (3)Test method : According to JIS and FBR Metallic Materials Test Methods (4)Number of deta : 64 points

JAEA Reports

Data on Trapping and Re-emission of Energetic Hydrogen Isotopes and Helium in Materials

*; Ozawa, K.; ; *

JAERI-M 82-118, 73 Pages, 1982/08

JAERI-M-82-118.pdf:1.2MB

no abstracts in English

Journal Articles

Blanket structual material selection and development for tokamak fusion reactor

Shiraishi, K.

Nihon Genshiryoku Gakkai-Shi, 21(6), p.471 - 479, 1979/00

 Times Cited Count:0

no abstracts in English

Journal Articles

Metallurgical aspects of the material development for process-heating HTR ; Overseas status in 1972

Kondo, Tatsuo

Nihon Genshiryoku Gakkai-Shi, 15(5), p.295 - 304, 1973/05

no abstracts in English

Journal Articles

Metals for high temperature reactors

*; Ogawa, Yutaka

Nihon Genshiryoku Gakkai-Shi, 14(11), p.626 - 632, 1972/11

no abstracts in English

Journal Articles

Radiation Damage in Metals

Zairyo Kagaku, 9(3), p.135 - 140, 1972/06

no abstracts in English

Journal Articles

Corrosion fatigue data for design uses, chapter4; Eflect of environmental condition.

Kondo, Tatsuo; *; *

Fushoku Tsukare Ni Kansuru Chosa Kenkyu Bunkakai Hokoku, p.26 - 35, 1972/00

no abstracts in English

Journal Articles

On the refractory metal and alloy fir nuclear reactor

Nagasaki, R.

Kogyo Reametaru, (49), p.99 - 102, 1972/00

no abstracts in English

24 (Records 1-20 displayed on this page)