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Journal Articles

Chromium(VI) adsorption-reduction using a fibrous amidoxime-grafted adsorbent

Hayashi, Natsuki*; Matsumura, Daiju; Hoshina, Hiroyuki*; Ueki, Yuji*; Tsuji, Takuya; Chen, J.*; Seko, Noriaki*

Separation and Purification Technology, 277, p.119536_1 - 119536_8, 2021/12

 Times Cited Count:14 Percentile:62.75(Engineering, Chemical)

Journal Articles

Sequestration and oxidation of Cr(III) by fungal Mn oxides with Mn(II) oxidizing activity

Suzuki, Ryohei*; Tani, Yukinori*; Naito, Hirotaka*; Miyata, Naoyuki*; Tanaka, Kazuya

Catalysts, 10(1), p.44_1 - 44_15, 2020/01

 Times Cited Count:10 Percentile:40.35(Chemistry, Physical)

We prepared biogenic Mn oxides (BMOs) using ${it Acremonium strictum}$ strain KR21-2, and subsequently conducted single or repeated treatment experiments in Cr(NO$$_{3}$$)$$_{3}$$ at pH6.0. Under aerobic conditions, newly formed BMOs exhibited a rapid production of Cr(VI) without a significant release of Mn(II), demonstrating that newly formed BMO mediates a catalytic oxidation of Cr(III) with a self-regeneration step of reduced Mn. In anaerobic solution, newly formed BMOs showed a cessation of Cr(III) oxidation in the early stage of the reaction, and subsequently had a much smaller Cr(VI) production with significant release of reduced Mn(II).

Journal Articles

HCM12A Cr-rich oxide layer investigation using 3D atom probe

Kikuchi, Kenji*; Okada, Noriyuki*; Kato, Mikio*; Uchida, Hiroshi*; Saito, Shigeru

Journal of Nuclear Materials, 450(1-3), p.237 - 243, 2014/07

 Times Cited Count:3 Percentile:23.92(Materials Science, Multidisciplinary)

Three-dimensional atom probe techniques were applied to the investigation on the oxide scale in 12Cr ferritic-martensitic steel, HCM12A. A duplex oxide scale was formed in lead bismuth eutectic at 450-500$$^{circ}$$C, during 5500 h. Samples were located 500-700 nm away from the boundary between magnetite and Fe-Cr spinel layers, while the total oxide layer thickness is 18 $$mu$$m. It detected super enrichment of Cr with a size of ten nm roughly, as well as depletion of Fe and enrichment of O at the same site. Surrounding the Cr super enrichment area, enrichment of Si was newly noticed due to the scanned profile of detected atom counts. It is also confirmed that Pb and Bi concentration in the observed spinel region is almost null or less than 0.01 atomic percent, which is possible detecting lowest limit.

Journal Articles

The Characterization of HIP and RHIP consolidated NiAl intermetallic compounds containing chromium particles

Ishiyama, Shintaro; Buchkremer, H. P.*; St$"o$ver, D.*

Nihon Kinzoku Gakkai-Shi, 68(9), p.831 - 837, 2004/09

 Times Cited Count:0 Percentile:0.01(Metallurgy & Metallurgical Engineering)

NiAl intermetallics with dispersive Cr particles consolidated by the Hot Isostaic Press(HIP) and Reactive HIP(RHIP) techniques, has been investigated. Mechanical properties of HIPed and RHIPed materials with various Cr concentrations ranging form 0 to 30 mass.%Cr, were examined at various temperatures. The consolidation temperature of RHIP materials decreases with Cr addition; when RHIPing NiAl+xCr compounds with 25 mass% has attained, remarkable high ductility over 17% elongation and over 400MPa tensile strength at 873K. A very high tensile strength of HIPed NiAl+20wt.%Cr about 600MPa with 10% elongation was achieved at 873K.

Journal Articles

The Characterization of HIP and RHIP consolidated NiAl intermetallic compounds containing chromium particles

Ishiyama, Shintaro; Buchkremer, H. P.*; St$"o$ver, D.*

Materials Transactions, 44(4), p.759 - 765, 2003/04

 Times Cited Count:0 Percentile:0.01(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Development of ceramic coating as tritium permeation barrier

Nakamichi, Masaru; Kawamura, Hiroshi; Teratani, Takema*

Fusion Science and Technology, 41(3), p.939 - 942, 2002/05

no abstracts in English

Journal Articles

Recent progress and future R&D for high-chromium iron-base and chromium-base alloys

Hishinuma, Akimichi; Takaki, Seiichi*; Abiko, Kenji*

Physica Status Solidi (A), 189(1), p.69 - 78, 2002/01

 Times Cited Count:13 Percentile:55.67(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Magnetic properties of some transition metal perovskite oxide systems; Transition metal = Ti, Cr, and Co

Yoshii, Kenji; Nakamura, Akio

Recent Research Developments in Physics, 3, p.758 - 776, 2002/00

no abstracts in English

Journal Articles

Magnetic properties of La$$_{1-x}$$Pr$$_{x}$$CrO$$_{3}$$

Yoshii, Kenji; Nakamura, Akio; Ishii, Yoshinobu; Morii, Yukio

Journal of Solid State Chemistry, 162(1), p.84 - 89, 2001/11

 Times Cited Count:100 Percentile:96.55(Chemistry, Inorganic & Nuclear)

no abstracts in English

Journal Articles

Magnetic properties of perovskite GdCrO$$_{3}$$

Yoshii, Kenji

Journal of Solid State Chemistry, 159(1), p.204 - 208, 2001/08

 Times Cited Count:189 Percentile:99.17(Chemistry, Inorganic & Nuclear)

no abstracts in English

Journal Articles

Reversal of magnetization in La$$_{0.5}$$Pr$$_{0.5}$$CrO$$_{3}$$

Yoshii, Kenji; Nakamura, Akio

Journal of Solid State Chemistry, 155(2), p.447 - 450, 2000/12

 Times Cited Count:86 Percentile:95.44(Chemistry, Inorganic & Nuclear)

no abstracts in English

Journal Articles

Studies on interaction between cesium iodide and type 316 stainless steel in WIND project

Kudo, Tamotsu; Maruyama, Yu; Shibazaki, Hiroaki*; Hidaka, Akihide; Nakamura, Hideo; Chino, Eiichi; Yuchi, Yoko; Hashimoto, Kazuichiro

JAERI-Conf 2000-015, p.216 - 221, 2000/11

no abstracts in English

JAEA Reports

Ultra-High temperature strength properties on Mod.9Cr-1Mo steel

; Yoshida, Eiichi; Aoto, Kazumi

JNC TN9400 2000-042, 112 Pages, 2000/03

JNC-TN9400-2000-042.pdf:8.55MB

A sodium-water reaction drove from the single tube break in steam generator of FBR might overheat labor tubes rapidly under internal pressure loadings. lf the temperature of tube wall becomes too high, it has to be evaluated that the stress of tube does not exceed the material strength limit to prevent the propagation of tube rupture. This study clarified the tensile and creep properties of Mod.9Cr-1Mo steel at ultra-high temperature which will be used in evaluation of the tube burst by sodium-water reaction. The strain rates for tensile test are from 10%/min to 10%/sec, and creep-rupture time is maximum 277sec. The range of test temperature is 700$$^{circ}$$C to 1300$$^{circ}$$C. The main results obtained were as follows; (1)The evaluation data on the relationship between tensile strength and strain rate and creep-rupture strength in shorter time on Mod.9Cr-1Mo steel were acquired. (2)Short-term mechanical properties of Mod.9Cr-1Mo steel were evaluated based on the results of tensile and creep-rupture tests up to 1300$$^{circ}$$C. As a result of the evaluation, recommended equation of creep-rupture strength in the short-term was proposed. (3)Tensile and creep-rupture strength of Mod.9Cr-1Mo steel tube showed the value which was higher than the 2 1/4Cr-1Mo steel, and it was proven to have the superior properties.

JAEA Reports

lnvestigation for corrosion behavior of ferritic core materials in CO$$_{2}$$ gas cooled reactor

; ; Mizuta, Shunji

JNC TN9400 2000-040, 41 Pages, 2000/03

JNC-TN9400-2000-040.pdf:0.85MB

The corrosion behavior of ferritic stainless steels applied to core components under C0$$_{2}$$ gas environment was investigated in order to be helpful to fuel design in C0$$_{2}$$ gas cooled reactor as the feasibility study for fast breeder reactor. The dependence of the corrosion behavior, before a breakaway occurs, on C0$$_{2}$$ gas temperature, Si and Cr contents of ferritic steels was determined quantitatively. The following correlations to calculate the metal loss thickness was established. X = 4.4w w = √(k$$times$$t) k = $$alpha$$ $$times$$ exp( - 5.45[Si]) $$times$$ exp( - 1.09[Cr]) $$times$$ exp( - 11253/T) $$alpha$$ = 1.65 $$times$$ 10$$^{8}$$$$sim$$4.40 $$times$$ 10$$^{9}$$ X : metal loss thickness[$$mu$$ml, w : corrosion weight gain [mg/cm$$^{2}$$] k : parabola constant [(mg/cm$$^{2}$$)$$^{2}$$/hr], t : time [hr], $$alpha$$ : constant [Si] : Si content[wt.%], [Cr] : Cr content [wt.%], T : temperature [K]

JAEA Reports

Evaluation of charpy impact property in high strength ferritic/martensitic steel (PNC-FMS)

;

JNC TN9400 2000-035, 164 Pages, 2000/03

JNC-TN9400-2000-035.pdf:3.67MB

High Strength Ferritic/Martensitic Steel (PNC-FMS : 0.12C-11Cr-0,5Mo-2W-0.2V-0.05Nb), developed by JNC, is one of the candidate materials for the long-life core of large-scale fast breeder reactor. Ductile brittle transition temperature (DBTT) was tentatively determined in 1992 in material design base standard of PNC-FMS. Howevcr, specimen size effect on impact property and upper shelf energy (USE) have not been evaluated. ln this study, effects of specimen size, thermal aging and neutron irradiation on the charpy impact property of PNC-FMS were evaluated, using together with recently obtained data. The design value of USE and DBTT as fabricated and each correlation of aging and irradiation effects were determined. The results are summarized as follows. (1)lt was found that USE is related to (Bb) as USE=m(Bb)$$^{n}$$, where B is specimen width, b is ligament size and both m and n are constant. For PNC-FMS, n value is equal to 1.4. It's possible to determine n value from USE (J) for full size specimen using the correlation: n=1.38$$times$$10$$^{-3}$$ USE + 1.20. (2)lt was clarified that DBTT is correlated with (BKt) as DBTT=p(log$$_{10}$$BKt)+q, where Kt is elastic stress concentration factor and both p and q are constant. For PNC-FMS, the correlation is as follows: DBTT=119(log$$_{10}$$BKt)-160. (3)DBTT estimated at the irradiation temperature from 350 to 650 $$^{circ}$$C for sub size specimen (width and height are 3 and 10 mm, respectively), was below 180 $$^{circ}$$C, based on the design value of DBTT as fabricated and each correlation of aging and irradiation effects.

JAEA Reports

The survey and evaluation of oxidation for core material of the austenitic stainless steels in carbon dioxide gas-cooled reactor

Mizuta, Shunji; ;

JNC TN9400 2000-032, 38 Pages, 2000/03

JNC-TN9400-2000-032.pdf:1.2MB

lt is necessary for feasibility study of fast reactor to evaluate the oxidation of the austenitic stainless steels in the case of using for core material in carbon dioxide gas-cooled reactor. The properties for oxidation of austenitic stainless steels in carbon dioxide were surveyed in literatures and the data were selected after evaluation of factors for oxidation in carbon dioxide. The equation of oxidation in carbon dioxide for PE16, 20Cr/25Ni/Nb, 18Cr-8Ni and JNC Cladding materials were proposed. The equation for oxidation of austenitic stainless steels were expressed as upper limit for the equation according to parabolic law. The equation for JNC cladding materials (PNC316, PNC1520, 14Cr-25Ni) was proposed based the oxidation behavior of 18Cr-8Ni which is same oxidation region for weight gain in three-component system of Fe-Cr-Ni, in addition to evaluate of effect for silicon content. The oxidation equation of 20Cr/25Ni/Nb was applied to the high Ni alloy of JNC cladding material. The obtained equation is as follows, X = 4.4W$$times$$1000, W = $$sqrt{(kp・t)}$$, kp = $$alpha$$ exp(-Q/(RT)), X: oxide thickness[$$mu$$m], W : weight gain[g$$times$$cm$$^{-2}$$], kp : parabolic rate constant[g$$^{2}$$$$times$$cm$$^{-4}$$$$times$$ s$$^{-1}$$], t :time[sec] $$alpha$$ : constant[g$$^{2}$$$$times$$cm$$^{-1}$$$$times$$S$$^{-1}$$], Q : activation energy[J・mol$$^{-1}$$], R : gas constant[8.314J $$times$$K$$^{-5}$$ $$times$$mol$$^{-1}$$], T : temperature[K] (1) PE16 : kp = 1.090$$times$$10$$^{-3}$$ exp(-192,500/(RD)), (2) 20Cr/25Ni/Nb : kp = 1.651$$times$$10$$^{-2}$$ exp(-201,300/(RT)) High Ni alloy (JNC), (3)18Cr-8Ni : kp = 1.503$$times$$10$$^{-8}$$ exp(-60,000/(RT)), (4) PNC316, PNC1520 : kp = 1.503$$times$$10$$^{-8}$$ exp(-60,000/(RT))$$times$$0.62$$^{2}$$ 14Cr-25Ni(JNC) The weight gain is (3)$$rangle$$(4)$$rangle$$(2)$$rangle$$(1) in order.

JAEA Reports

Physico-chemical studies on the disposal of miscellaneous radioactive waste through A single-step process (III)

Iwase, Masanori*

JNC TJ8400 2000-063, 78 Pages, 2000/03

JNC-TJ8400-2000-063.pdf:1.93MB

This study is aimed at controlling oxidation reaction of molten metal by ash in incineration systems, and at positively utilizing the oxidation reaction for decontamination of slag. In this year, in order to investigate physico-chemical properties of mixed fused salt containing alkali sulfates, with special focus on the behaviour of oxygen anion in the melts, Cu$$^{2+}$$ / Cu$$^{+}$$ redox equilibrium experiments were carried out. Among the effect of various parameters on Cu$$^{2+}$$ / Cu$$^{+}$$ ratio in binary and ternary alkali sulfate melts, the effect of partial pressures of oxygen and SO$$_{2}$$ was mainly investigated in the study. Variation in Cu$$^{2+}$$ / Cu$$^{+}$$ ratio were presented as the function of partial pressures of oxygen and SO$$_{2}$$, respectively. Possible thermodynamic interpretation were made on the experimental results. In addition, the dissolution of Cr$$_{2}$$O$$_{3}$$ in mixed alkali sulfates were also investigated as a first step to elucidate the mechanism of hot corrosion. With this investigation, an important finding was obtained that the solubility of Cr$$_{2}$$O$$_{3}$$ for melts with same average ionic radius, in other words, oxygen ion activity, were essentially identical under constant temperature and atmosphere.

JAEA Reports

Irradiation creep equation of the advanced austenitic stainless steels

Mizuta, Shunji; ;

JNC TN9400 99-082, 60 Pages, 1999/10

JNC-TN9400-99-082.pdf:1.52MB

The density measurement of the internal creep specimens irradiated in FFTF/MOTA (Fast Flux Test Facility / Material open Test Assembly) was conducted MMF (Materia1 Monitoring Facility) and accurate separation of swelling strain from total strain leaded in the derivation of the irradiation creep coefficients. Irradiation creep coefficients for PNC 316, 15Cr-20Ni base S.S. and 14Cr-25Ni base S.S. were systematically expressed, while thermal creep coefficients K, under irradiation were separately expressed for above three steels. The results obtained are follows, (1)The effect of stress induced swelling was recognized in the temperature range from 405 to 605$$^{circ}$$C. The swelling in high stress specimens have a tendency to increasing swelling. (2)The irradiation creep coefficients derived from PNC316 and l5Cr-20Ni are similar to that of derived from 20%CW316S.S., CW316Ti and CW15-15Ti which were reported by other authors. (3)The irradiation creep coefficient derived from gas pressurized tube irradiation using FFTF/MOTA expressed appropriately irradiation creep strain from fuel pins using FFTF/MFA-2(15Cr-2ONi base S.S.).

JAEA Reports

Development of Cr,Nd:GSGG laser as a pumping source of Ti:sapphire laser

Tamura, Koji; Arisawa, Takashi

JAERI-Tech 99-058, 13 Pages, 1999/08

JAERI-Tech-99-058.pdf:1.2MB

no abstracts in English

JAEA Reports

Simulation of creep test on 316FR stainless steel in sodium environment at 550$$^{circ}C$$

Satmoko, A.*;

JNC TN9400 99-035, 37 Pages, 1999/04

JNC-TN9400-99-035.pdf:1.54MB

In sodium environment, materia1 316FR stainless steel risks to suffer from carburization. In this study, an analysis using a Fortran program is conducted to evaluate the carbon influence on the creep behavior of 316FR based on experimental results from uni-axial creep test that had been performed at temperature 550$$^{circ}$$C in sodium environment simulating Fast Breeder Reactor condition. As performed in experiments, two parts are distinguished. At first, elastic-plastic behavior is used to simulate the fact that just before the beginning of creep test, specimen suffers from load or stress much higher than initial yield stress. In second part, creep condition occurs in which the applied load is kept constant. The plastic component should be included, since stresses increase due to section area reduction. For this reason, elastic-plastic-creep behavior is considered. Through time carbon penetration occurs and its concentration is evaluated empirically. This carburization phenomena are assumed to affect in increasing yield stress, decreasing creep strain rate, and increasing creep rupture strength of material. The model is capable of simulating creep test in sodium environment. Material near from surface risks to be carburized. Its material properties change leading to non-uniform distribution of stresses. Those layers of material suffer from stress concentration, and are subject to damage. By introducing a damage criteria, crack initialization can thus be predicted. And even, crack growth can be evaluated. For high stress levels, tensile strength criterion is more important than creep damage criterion. But in low stress levels, the latter gives more influence in fracture. Under high stress, time to rupture of a specimen in sodium environment is shorter than in air. But for stresses lower than 26 kgfmm$$^{2}$$, the time to rupture of creep in sodium environment is the same or little longer than in air. Quantitatively, the carburization effect at ...

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