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Journal Articles

Phase transitions of sodium peroxide investigated by DSC

Kikuchi, Shin; Koga, Nobuyoshi*

Journal of Thermal Analysis and Calorimetry, 150(1), p.585 - 590, 2025/01

 Times Cited Count:0 Percentile:0.00(Thermodynamics)

Journal Articles

Multistep kinetics of the thermal dehydration/decomposition of metakaolin-based geopolymer paste

Shindo, Manami*; Ueoku, Aya*; Okamura, Wakana*; Kikuchi, Shin; Yamazaki, Atsushi*; Koga, Nobuyoshi*

Thermochimica Acta, 738, p.179801_1 - 179801_12, 2024/08

 Times Cited Count:0 Percentile:0.00(Thermodynamics)

Journal Articles

Thermal decomposition of perlite concrete under different water vapor pressures

Iwasaki, Shun*; Sakai, Yasuhiro*; Kikuchi, Shin; Koga, Nobuyoshi*

Journal of Thermal Analysis and Calorimetry, 147(11), p.6309 - 6322, 2022/06

 Times Cited Count:10 Percentile:53.10(Thermodynamics)

The influence of atmospheric water vapor on the multistep thermal decomposition of perlite concrete was investigated in detail by separating the component reaction steps using kinetic deconvolution analysis (KDA). The retardation of thermal decomposition of Ca(OH)$$_{2}$$ and the acceleration of thermal decomposition of CaCO$$_{3}$$ were identified as specific effect of atmospheric water vapor.

Journal Articles

Influence of atmospheric CO$$_{2}$$ on the thermal decomposition of perlite concrete

Sakai, Yasuhiro*; Iwasaki, Shun*; Kikuchi, Shin; Koga, Nobuyoshi*

Journal of Thermal Analysis and Calorimetry, 147(10), p.5801 - 5813, 2022/05

 Times Cited Count:13 Percentile:60.17(Thermodynamics)

The influence of atmospheric CO$$_{2}$$ on the multistep thermal decomposition of perlite concrete was investigated in detail by separating the component reaction steps using kinetic deconvolution analysis (KDA). The carbonation of Ca(OH)$$_{2}$$ and the retardation of the thermal decomposition of CaCO$$_{3}$$ were identified as specific effect of atmospheric CO$$_{2}$$.

Journal Articles

Thermal behavior and kinetics of the reaction between liquid sodium and calcium hydroxide

Kikuchi, Shin; Koga, Nobuyoshi*

Journal of Thermal Analysis and Calorimetry, 147(7), p.4635 - 4643, 2022/04

 Times Cited Count:2 Percentile:9.80(Thermodynamics)

In a sodium-cooled fast reactor (SFR), sodium-concrete reaction (SCR) may probably occur when liquid sodium from cooling system spilled into the floor may lead to fail the steel liner as protector of the structural concretes. The structural concretes of SFR comprises siliceous concreate as main body of reactor structure and perlite concrete placed between the steel liner and the siliceous concrete serving as a protector and an insulator, respectively. Therefore, the reaction behaviour between the perlite concrete and liquid sodium in the early stage of SCR should be focused. In this study, for the first step of elucidation on SCR, thermal behaviour of sodium-calcium hydroxide reaction was investigated using a differential scanning calorimetry (DSC). It was revealed that the reaction between Na(l) and Ca(OH)$$_{2}$$(s) initiates at approximately 550 K, producing the product layer composed of CaO(s) and NaOH(s), which is evident from XRD pattern of solid product after DSC measurement. The kinetic consideration of the cited reaction was carried out to obtain the activation energy.

Journal Articles

Thermally stimulated liquid Na-CaCO$$_{3}$$ reaction; A Physicogeometrical kinetic approach toward the safety assessment of Na-cooled fast reactors

Koga, Nobuyoshi*; Kikuchi, Shin

Industrial & Engineering Chemistry Research, 61(7), p.2759 - 2770, 2022/02

 Times Cited Count:2 Percentile:10.86(Engineering, Chemical)

Journal Articles

Thermal behavior of perlite concrete used in a sodium-cooled fast reactor; Multistep reaction kinetics and melting for safety assessment

Koga, Nobuyoshi*; Kikuchi, Shin

Journal of Thermal Analysis and Calorimetry, 138(2), p.983 - 996, 2019/10

 Times Cited Count:12 Percentile:44.29(Thermodynamics)

Detailed understanding of the thermal decomposition of the structural concretes used in the sodium-cooled fast reactor is essentially important to simulate the possible phenomena that occurs under postulated severe accident of the nuclear power plant. In this study, the thermal decomposition behaviour of a perlite concrete and two siliceous concretes used in a sodium-cooled fast reactor was comparatively investigated.

Journal Articles

Comparative study on the thermal behavior of structural concretes of sodium-cooled fast reactor

Kikuchi, Shin; Koga, Nobuyoshi*; Yamazaki, Atsushi*

Journal of Thermal Analysis and Calorimetry, 137(4), p.1211 - 1224, 2019/08

 Times Cited Count:10 Percentile:37.74(Thermodynamics)

In this study, two siliceous concretes with similar specification as structural concretes of SFR were selected for the comparative study of the thermal behavior. The thermal behavior of the structural concretes was investigated in a temperature range from room temperature to 1900 K using TG-differential thermal analysis (DTA) and other supplementary techniques. The softening and melting of the concretes initiated in the thermal decomposition product of the cement portion in the temperature range 1400-1600 K. Because the compositional difference between the cement portion of two different siliceous concretes was characterized by different Ca(OH)$$_{2}$$/CaCO$$_{3}$$ ratios, the melting temperature ranges of those thermal decomposition products are not so significantly different. On the other hand, the melting of the aggregate is directly influenced by the initial composition of SiO$$_{2}$$ compounds.

Journal Articles

Thermal behavior of sodium hydroxide-structural concrete composition of sodium-cooled fast reactor

Kikuchi, Shin; Koga, Nobuyoshi*

Journal of Thermal Analysis and Calorimetry, 131(1), p.301 - 308, 2018/01

 Times Cited Count:10 Percentile:35.54(Thermodynamics)

Under postulated accidental condition of sodium-cooled fast reactor (SFR), liquid sodium spill into the floor may lead to fail the steel liner resulting in sodium-concrete reaction (SCR). In this study, the sodium hydroxide (NaOH)-silica (SiO$$_{2}$$) reaction as one of possible secondary stage reactions was investigated for safety assessment of SFR. Thermal behavior of NaOH-SiO$$_{2}$$ reaction such as reaction onset was determined using a differential scanning calorimetry (DSC). As a result of DSC measurement, it was revealed that NaOH-SiO$$_{2}$$ reaction occurs as rapid reaction right after NaOH melting at 583 K. Therefore, it was expected that NaOH-SiO$$_{2}$$ reaction is dominant in the time frame of secondary stage of SCR if significant amount of NaOH has been generated during the initial stage reaction.

Journal Articles

Experimental study and kinetic analysis on sodium oxide-silica reaction

Kikuchi, Shin; Koga, Nobuyoshi*; Seino, Hiroshi; Ohno, Shuji

Journal of Nuclear Science and Technology, 53(5), p.682 - 691, 2016/05

 Times Cited Count:17 Percentile:81.15(Nuclear Science & Technology)

In a sodium-cooled fast reactor (SFR), if considering hypothetical severe accidental condition such as the steel liner failure of structural concrete caused by intensive leakage of liquid sodium (Na) coolant, the liquid sodium-concrete reaction (SCR) may take place. The major consequences of SCR are hydrogen release, energy release and concrete ablation. Thus, it is important to understand the phenomenology of SCR. As a part of a series of studies on SCR, this study focused on the reaction between sodium oxide (Na$$_{2}$$O) and silica (SiO$$_{2}$$). Through thermoanalytical and X-ray diffraction measurements, it was revealed that Na$$_{2}$$O-SiO$$_{2}$$ reaction to form sodium orthosilicate (Na$$_{4}$$SiO$$_{4}$$) occurs at significantly lower temperature in comparison with Na-SiO$$_{2}$$ reaction.

Journal Articles

Application of thermal analysis in research and development of sodium-cooled fast reactor

Kikuchi, Shin; Koga, Nobuyoshi*

Netsu Sokutei, 43(1), p.11 - 18, 2016/00

This paper describes the study on sodium-concrete reaction behavior, which is one of the example of the application of thermal analysis in research and development of sodium-cooled fast reactor (SFR).

Journal Articles

Kinetic study on liquid sodium-silica reaction for safety assessment of sodium-cooled fast reactor

Kikuchi, Shin; Koga, Nobuyoshi*; Seino, Hiroshi; Ohno, Shuji

Journal of Thermal Analysis and Calorimetry, 121(1), p.45 - 55, 2015/07

 Times Cited Count:15 Percentile:46.66(Thermodynamics)

In this study, the kinetic behavior of the sodium (Na)-silica (SiO$$_{2}$$) reaction was investigated for an assessment method of reactivity/stability of siliceous concrete against the sodium-concrete reaction (SCR) by postulating a severe accidental condition in the sodium-cooled fast reactor (SFR). The reaction behavior was tracked using a differential scanning calorimetry (DSC) equipped with a videoscope for viewing the changes in the sample during the reaction. From detail kinetic analysis, it was revealed that the kinetic results determined from the kinetic data at the maximum reaction rate can be interpreted as is for the major reaction stage. In addition, the k value at a constant temperature calculated using the Arrhenius parameters determined by the simplified Kissinger method can be used for the reactivity/stability assessment of the siliceous concrete in view of the kinetics of the major reaction stage of the Na-SiO$$_{2}$$ reaction.

Oral presentation

Development of multi-level, multi-scenario simulation systems for sodium cooled fast reactor, 1; Overall plan for development of simulation systems

Ohshima, Hiroyuki; Takata, Takashi; Doda, Norihiro; Kikuchi, Shin; Koga, Nobuyoshi*; Deguchi, Yoshihiro*

no journal, , 

Development of multi-level, multi-scenario plant simulation systems has started as a fundamental technology to support mechanism elucidation of phenomena, design optimization, and innovative technology development toward the commercialization of sodium cooled fast reactors. In this presentation, the overall plan of this development project is introduced.

Oral presentation

Kinetic study of liquid sodium-calcite reaction for safety assessment of sodium cooled fast reactor

Kikuchi, Shin; Koga, Nobuyoshi*

no journal, , 

In a sodium-cooled fast reactor (SFR), sodium-concrete reaction (SCR) may probably occur when liquid sodium from cooling system spilled into the floor may lead to fail the steel liner as protector of the structural concretes. The structural concretes of SFR comprises siliceous concreate as main body of reactor structure and perlite concrete placed between the steel liner and the siliceous concrete serving as a protector and an insulator, respectively. Therefore, the reaction behaviour between the perlite concrete and liquid sodium in the early stage of SCR should be focused. In this study, for the first step of elucidation on SCR, thermal behaviour of sodium-calcite reaction was investigated using a differential scanning calorimetry. Comparative study for the reactions of pellet and powder of the reagent CaCO3 with sodium was performed from the viewpoints of thermal behaviour and reaction kinetics.

Oral presentation

Thermal decomposition of structural concretes used in the sodium-cooled fast reactor; Perlite and siliceous concretes

Koga, Nobuyoshi*; Kikuchi, Shin

no journal, , 

Detailed understanding of the thermal decomposition of the structural concretes used in the sodium-cooled fast reactor is essentially important to simulate the possible phenomena that occurs under postulated severe accident of the nuclear power plant. In this study, the thermal decomposition behaviour of a perlite concrete and two siliceous concretes used in a sodium-cooled fast reactor was comparatively investigated.

Oral presentation

Development of multi-level, multi-scenario simulation systems for sodium cooled fast reactor, 9; Fundamental experiment on sodium-concrete reaction

Kikuchi, Shin; Koga, Nobuyoshi*; Kurihara, Akikazu; Takata, Takashi; Ohshima, Hiroyuki

no journal, , 

Development of multi-level, multi-scenario simulation systems for the safety fundamental technology of sodium cooled fast reactor is under way. In this study, authors report the experimental results on sodium-concrete reaction as important specific events of sodium cooled fast reactor for code V&V.

Oral presentation

Kinetic behavior of the liquid sodium-calcium carbonate reaction

Koga, Nobuyoshi*; Kikuchi, Shin

no journal, , 

The reaction of liquid Na with CaCO$$_{3}$$ was studied kinetically as a model reaction of the liquid Na with structural concreate by postulating a severe accident in a sodium-cooled fast reactor. The reaction that occurs in the temperature range of 650-850 K was detected by the exothermic DSC peaks. In the case of liquid Na-CaCO$$_{3}$$ powder reaction, four exothermic peaks appeared by overlapping partially. The changes in the distribution of CaCO$$_{3}$$ powder in liquid Na and contact area of the reactants as the reaction advances are the possible reason for the apparent multistep reaction. For the liquid Na-CaCO$$_{3}$$ pellet reaction, the single DSC exothermic peak was observed as the result of the one-dimensional regulation of the reaction geometry.

Oral presentation

Kinetic study of liquid sodium-calcium hydroxide reaction for safety assessment of sodium cooled fast reactor

Kikuchi, Shin; Koga, Nobuyoshi*

no journal, , 

In a sodium-cooled fast reactor (SFR), sodium-concrete reaction (SCR) may probably occur when liquid sodium from cooling system spilled into the floor may lead to fail the steel liner as protector of the structural concretes. The structural concretes of SFR comprises siliceous concreate as main body of reactor structure and perlite concrete placed between the steel liner and the siliceous concrete serving as a protector and an insulator, respectively. Therefore, the reaction behaviour between the perlite concrete and liquid sodium in the early stage of SCR should be focused. In this study, for the first step of elucidation on SCR, thermal behaviour of sodium-calcium hydroxide reaction was investigated using a differential scanning calorimetry.

Oral presentation

Kinetic deconvolution analysis applied to liquid sodium-calcium carbonate reaction

Koga, Nobuyoshi*; Kikuchi, Shin

no journal, , 

In this study, the reaction of liquid Na with CaCO$$_{3}$$ was studied kinetically as one model reaction of the liquid Na with structural concreate by postulating a severe accident in a sodium-cooled fast reactor (SFR). The reaction that occurred in the temperature range of 650-850 K was tracked by the exothermic DSC peak and morphological observations for Na- CaCO$$_{3}$$ powder and Na- CaCO$$_{3}$$ pellet samples. In the case of liquid Na- CaCO$$_{3}$$ powder reaction, four exothermic peaks appeared by overlapping partially. Kinetic analysis of these overlapping reaction steps was carried out.

Oral presentation

Development of multi-level, multi-scenario simulation systems for sodium cooled fast reactor, 12-2; Fundamental experiment on sodium-concrete reaction

Kikuchi, Shin; Koga, Nobuyoshi*; Kurihara, Akikazu; Takata, Takashi; Ohshima, Hiroyuki

no journal, , 

Development of multi-level, multi-scenario simulation systems for the safety fundamental technology of sodium cooled fast reactor is under way. In this study, authors report the experimental results and analysis on sodium-concrete reaction as important specific events of sodium cooled fast reactor for code V&V.

34 (Records 1-20 displayed on this page)