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JAEA Reports

Corrosion test of Fugen pressure tube (Zr-2.5wt%Nb alloy) under the sub-surface disposal environment, 2; Examination of long-term corrosion rate by 5 years keeping sample

Sugaya, Toshikatsu; Nakatani, Takayoshi; Sakai, Akihiro

JAEA-Technology 2017-032, 21 Pages, 2018/01

[The article has been found to have a problem about reliability of the corrosion data acquisition, and thus it is unavailable to download the full text in accordance with authors' intentions to retract the report.] For the purpose of the setting of the rate of nuclide elution necessary to safety assessment, we planned the gas-accumulating type corrosion test on Zr-2.5wt%Nb alloy in order to obtain long-term corrosion rate under low temperature, low oxygen and alkaline conditions assuming the disposal environment. A corrosion rate over a testing period of 5 years is acquired with the aim to grasp a long-term corrosion rate behavior in this report. This corrosion rate is compared with the same data that was previously acquired over a testing period of 2 years. As a result, it is confirmed that an evaluation method that is proportional to the minus cubic root of corrosion time squared can be applicable to the corrosion rate behavior acquired this time over a testing period of 5 years, which is the same result in evaluating the corrosion rate behavior acquired over a testing period of 2 years.

Journal Articles

Evaluation of source term parameters for spent fuel disposal in foreign countries, 2; Dissolution rates of spent fuel matrices and construction materials for fuel assemblies

Kitamura, Akira; Chikazawa, Takahiro*; Akahori, Kuniaki*; Tachi, Yukio

Genshiryoku Bakkuendo Kenkyu (CD-ROM), 23(1), p.55 - 72, 2016/06

The Japanese geological disposal program has started researching disposal of spent nuclear fuel (SF) in deep geological strata (hereafter "direct disposal of SF") as an alternative management option other reprocessing followed by vitrification and geological disposal of high-level radioactive waste. We conducted literature survey of dissolution rate of SF matrix and constructing materials (e.g. zircaloy cladding and control rods) selected in safety assessment reports for direct disposal of SF in Europe and United States. We also investigated basis of release rate determination and assignment of uncertainties in the safety assessment reports. Furthermore, we summarized major conclusions proposed by some European projects governed by European Commission. It was found that determined release rates are fairly similar to each other due to use of similar literature data in all countries of interest. It was also found that the determined release rates were including conservativeness because it was difficult to assign uncertainties quantitatively. It is expected that these findings are useful as fundamental information for determination of the release rates for the safety assessment of Japanese SF disposal system.

JAEA Reports

Passivation condition of carbon steel in bentonite/sand mixture

Taniguchi, Naoki; Kawakami, Susumu; *

JNC TN8400 2001-025, 27 Pages, 2002/03

JNC-TN8400-2001-025.pdf:1.16MB

It is essential to understand the corrosion type of carbon steel under the repository conditions for the lifetime assessment of carbon steel overpack used for geological isolation of high-level radioactive waste. According to the previous study, carbon steel is hard to passivate in buffer material assuming a chemical condition range of groundwater in Japan. However, concrete support will be constructed around the overpack in the case of repository in the soft rock system and groundwater having a higher pH may infiltrate to buffer material. There is a possibility that the corrosion type of carbon steel will be influenced by the rise of the pH in groundwater. In this study, anodic polarization experiments were performed to understand the passivation condition of carbon steel in buffer material saturated with water contacted with concrete. An ordinary concrete and a low-alkalinity concrete were used in the experiment. The results of the experiments showed that the carbon steel can passivate under the condition that water having pH $$>$$ 13 infiltrate to the buffer material assuming present property of buffer material. If the low-alkalinity concrete is selected as the support material, passivation can not occur on carbon steel overpack. The effect of the factors of buffer material such as dry density and mixing ratio of sand on the passivation of carbon steel was also studied. The results of the study showed that the present property of buffer material is enough to prevent passivation of carbon steel.

JAEA Reports

The 3rd technological meeting of Tokai reprocessing plant

Maki, Akira; ; Taguchi, Katsuya; ; Shimizu, Ryo; Shoji, Kenji;

JNC TN8410 2001-012, 185 Pages, 2001/04

JNC-TN8410-2001-012.pdf:9.61MB

"The third technological meeting of Tokai Reprocessing plant (TRP)" was held in JNFL Rokkasyo site on March 14$$^{th}$$, 2001. The technical meetings have been held in the past two times. The first one was about the present status and future plan of the TRP and second one was about safety evaluation work on the TRP. At this time, the meeting focussed on the corrosion experrience, in-service inspection technology and future maintenance plan. The report contains the proceedings, transparancies and questionnaires of the meeting are contained.

JAEA Reports

Effect of magnetite as a corrosion product on the corrosion of carbon steel overpack

Taniguchi, Naoki; ; Kawasaki, Manabu*; Masugata, Tsuyoshi*

JNC TN8400 2001-001, 56 Pages, 2000/12

JNC-TN8400-2001-001.pdf:2.05MB

It is necessary to clear the effects of corrosion products on the corrosion life time of carbon steel overpack for geological isolation of high-level radioactive waste(HLW). Especially, it is important to understand the effects of magnetite because magnetite as a simulated corrosion product is reported to accelerate the corrosion rate of carbon steel. In this study, corrosion tests to reproduce the acceleration of corrosion due to magnetite was performed and the mechanism of the acceleration was investigated to evaluate the effects of magnetite as a corrosion product. Based on the results of experiments, following conclusions are obtained ; (1)Magnetite powder accelerates the corrosion rate of carbon steel. The main reaction of corrosion under the presence of magnetite is the reduction of Fe(III) in magnetite to Fe(II), but the reaction of hydrogen generation is also accelerated. The contribution of hydrogen generation reaction was estimated to be about 30% in the total corrosion reaction based on the experimental result of immersion test under the presence of magnetite. (2)Actual corrosion products containing magnetite generated by the corrosion of carbon steel protect the metal from the propagation of corrosion. The corrosion depth of carbon steel overpack due to magnetite was estimated to be about 1 mm based on the results of experiments. Even if the effect of magnetite is taken into the assessment of corrosion lifetime of overpack, total corrosion depth in 1000 years is estimated to be 33 mm, which is smaller than the corrosion allowance of 40 mm described in the second progress report on research and development for the geological disposal of HLM/ in Japan. It was concluded that the effect of magnetite on the corrosion life time of carbon steel overpack is negligible.

JAEA Reports

Sodium combustion analysis for the secondary heat transport system of prototype fast breeder reactor MONJU

; Ohno, Shuji;

JNC TN2400 2000-006, 56 Pages, 2000/12

JNC-TN2400-2000-006.pdf:1.22MB

Sodium combustion analyses were performed using ASSCOPS version 2.1 in order to obtain background data for evaluating the validity of the mitigation system against secondary sodium leak of MONJU. The calculated results are summarized as follows. (1)Peak atmospheric pressure $$sim$$ 4.3 kPa[gage] (2)Peak floor liner temperature $$sim$$ 870$$^{circ}$$C, Maximum thinning of liner $$sim$$2.6mm (3)Peak hydrogen concentration <2% (4)Peak floor liner temperature in the spilt sodium storage eell $$sim$$ 400$$^{circ}$$C , Peak floor concrete temperature in the spilt sodium storage cell $$sim$$ 140$$^{circ}$$C.

JAEA Reports

Development of testing device for analyzing low temperature plasma surface reaction

Saburi, Tei; Ogawa, Hiroaki; Ueda, Satoshi*; Kiuchi, Kiyoshi

JAERI-Tech 2000-057, 23 Pages, 2000/10

JAERI-Tech-2000-057.pdf:5.28MB

no abstracts in English

JAEA Reports

Corrosion of iron buried in clay

Sumiyama, Morio*

JNC TJ8400 2000-009, 138 Pages, 2000/02

JNC-TJ8400-2000-009.pdf:3.0MB

To evaluate corrosion behavior of carbon steel, a candidate materials of overpack, buried in soil for a long time, the water pipes buried in freshwater clay for a long time we digged out and the soil environment and the corrosion weight loss of pipes have been researched. From the results, a corrosion model (an empirical equation), an oxygen reduction reaction rate-determing step type, of carbon steel buried in soil was introduced. The corrosion data of under ground pipe collected by the Japan Community Gas Associations was used to increase reliability of the corrosion model equation. These data are one of researches of corrosion behavior of carbon steel buried in soil for a long time studied by at home and abroad. 38 samples buried freshwater clay were selected in 171 samples. With estimating the corrosion velocities and the soil environment factors of the above data, the maximum depth of pit corrosion was calculated by the statistical method of the extreme values using the area of overpack as the recurrent time. The correlation between the soil environment factors and the corrosion weight loss was obtained by the correlation analysis. The corrosion model of the maximum depth of pit corrosion at 0.99 of cumulative probability was compared between the under ground pipe data and the above data. On the reference data and the above data, the corrosion model equation; H = aY$$^{n}$$ was compared with the maximum depth of pit corrosion at 0.99 cumulative probability. The data of water pipes and community gas pipes at 0.99 cumulative probability showed the reasonable values when these data were compared with the reference data. So that the model was proved as a good corrosion model m the neutral low dissolved oxygen environment.

JAEA Reports

Inspection about the corrosion of metallic archaeological artifacts in ground

Honda, Takashi*; *

JNC TJ8400 2000-007, 200 Pages, 2000/02

JNC-TJ8400-2000-007.pdf:14.84MB

In general, it is very difficult to evaluate the residual state of metallic iron and the original shape of iron-base archaeological artifacts, as these are covered by thick oxide films formed in the ground during over several hundred years. The purpose of this research is to quantify the corrosion of an artifact such as base, knife, and nail, which was digged out of the relics about 500-1,000 years old. (1)The outer oxide film layer and the inner metallic iron can be quantitatively divided by using X-ray CT method. Furthermore, the original surfaces of artifacts can be estimated from the obtained images, even if the metallic iron has corroded completely. The X-ray CT images were also compared with those obtained by X-ray transmission inspection. (2)The corrosion amounts and rates were evaluated on the basis of thicknesses, densities, and iron concentrations of oxide films. (3)The characteristic differences between ancient iron and modern carbon steel were evaluated by analyzing the ancient iron slag.

JAEA Reports

Corrosion bihavior of carbon steel in high-temperature sodium compounds; Recommended equation for corrosion rate of the carbon steel in sodium compounds (Na$$_{2}$$O$$_{2}$$-NaOH System)

Yoshida, Eiichi; Aoto, Kazumi; Hirakawa, Yasushi;

JNC TN9400 2000-024, 42 Pages, 1999/10

JNC-TN9400-2000-024.pdf:1.63MB

For the purpose of improving the reliability of evaluation, the corrosion rate equation of the carbon steel SM400B (JIS G3106) in the high-temperature sodium compounds (NaOH-Na$$_{2}$$0$$_{2}$$ system) was revised. ln this revision, the data acquired after 1997 was used. Based on the experimental results, the evaluation was made to be an approach to the following; (1)Metal loss of carbon steel in NaOH-Na$$_{2}$$0$$_{2}$$ system was evaluated as increases in exposure to the time, which is linear rate law. (2)There were no significant effects of the experiment atmosphere and mixing speed of the reagent on corrosion rate. (3)The concentration of Na$$_{2}$$0$$_{2}$$ in sodium compound is considered for the evaluation. The concentration under experiment is made to be the over concentration necessary for maintaining the dominant reaction between Fe and Na$$_{2}$$20$$_{2}$$. As a result of the evaluation, the additional data are 67 points. The data for the revision of the evaluation equation became the total of 105 points, when existing data of 38 points were added. The statistical evaluation of 105 points was carried out, and following recommended equation was obtained. C$$_{R}$$ = C exp(-Q/RT) Where; C$$_{R}$$ : Corrosion rate, mm/h C : Material constant Q : Apparent activation energy, cal/mol R : Gas constant, 1.986 cal/mol K T ; Absolute temperature, K Q = 9.61 kcal/mol C = 148.29 (average), 262.11 (99% UCL), 83.90 (99% LCL)

Journal Articles

Corrosion tests of iron-silicon alloys in boiling sulfuric acid

Ioka, Ikuo; Onuki, Kaoru; Futakawa, Masatoshi; Kuriki, Yoshiro*; Nagoshi, Masayasu*; Nakajima, Hayato; Shimizu, Saburo

Ryusan To Kogyo, 52(4), p.1 - 6, 1999/04

no abstracts in English

JAEA Reports

None

*; *; ; Takeda, Seiichiro

PNC TN8410 97-433, 49 Pages, 1997/12

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

None

JAEA Reports

None

; ; *; ; Takeda, Seiichiro

PNC TN8410 97-425, 34 Pages, 1997/11

PNC-TN8410-97-425.pdf:0.97MB

None

JAEA Reports

None

*; *; ; *; *; Ito, Kenji

PNC TJ2164 97-004, 38 Pages, 1997/10

PNC-TJ2164-97-004.pdf:3.34MB

JAEA Reports

None

; *; ; ; Takeda, Seiichiro

PNC TN8410 97-104, 56 Pages, 1997/04

PNC-TN8410-97-104.pdf:2.06MB

None

JAEA Reports

Corrosion Resistance of Titanium for Nuclear Waste Container in Non-oxidizing Condition (I)

*; Nishimura, Tsutomu*; Shimogori, Kazutoshi*; *; Fujiwara, Kazuo*; *; *

PNC TJ1058 97-005, 49 Pages, 1997/03

PNC-TJ1058-97-005.pdf:5.06MB

None

JAEA Reports

Corrosion Resistance of Titanium for Nuclear Waste Container in Non-oxidizing Condition (I)

*; Nishimura, Tsutomu*; Shimogori, Kazutoshi*; *; Fujiwara, Kazuo*; *; *

PNC TJ1058 97-004, 179 Pages, 1997/03

PNC-TJ1058-97-004.pdf:19.14MB

None

JAEA Reports

None

Wada, Ryutaro*; Nishimura, Tsutomu*; Fujiwara, Kazuo*; *; *

PNC TJ1058 97-003, 33 Pages, 1997/03

PNC-TJ1058-97-003.pdf:2.63MB

None

JAEA Reports

None

Wada, Ryutaro*; Nishimura, Tsutomu*; Fujiwara, Kazuo*; *; *

PNC TJ1058 97-002, 430 Pages, 1997/03

PNC-TJ1058-97-002.pdf:24.97MB

None

JAEA Reports

None

Sumiyama, Morio*

PNC TJ1451 97-001, 133 Pages, 1997/02

PNC-TJ1451-97-001.pdf:90.3MB

None

31 (Records 1-20 displayed on this page)