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Journal Articles

Low temperature heat capacity of Cs$$_{2}$$Si$$_{4}$$O$$_{9}$$

Suzuki, Eriko; Nakajima, Kunihisa; Osaka, Masahiko; Oishi, Yuji*; Muta, Hiroaki*; Kurosaki, Ken*

Journal of Nuclear Science and Technology, 57(7), p.852 - 857, 2020/07

https://doi.org/10.1080/00223131.2020.1727374
 Times Cited Count：4 Percentile：44.4(Nuclear Science & Technology)

The low temperature heat capacity of Cs$$_{2}$$Si$$_{4}$$O$$_{9}$$, which is one of the cesium chemisorbed compounds onto stainless steel during severe accident of the light water nuclear reactor, was experimentally determined for the first time in the temperature range of 1.9 - 302 K. The experimentally determined heat capacity, $$C_{p}$$$$^{o}$$ (298.15K), and the standard entropy, $$S^{o}$$ (298.15K), were 249.4 $$pm$$ 1.1 J K$$^{-1}$$ mol$$^{-1}$$ and 322.1 $$pm$$ 1.3 J K$$^{-1}$$ mol$$^{-1}$$, respectively. The standard Gibbs energy of formation of Cs$$_{2}$$Si$$_{4}$$O$$_{9}$$ at high temperatures, $$Delta$$$$_{f}$$$$G^{o}$$($$T$$), were reevaluated by using the presently obtained $$S^{o}$$ (298.15K) and the previously reported experimental results of the standard enthalpy of formation, $$Delta$$$$_{f}$$$$H^{o}$$ (298.15K), and the standard enthalpy increments at high temperatures, $$H^{o}$$($$T$$)-$$H^{o}$$ (298.15K).

Journal Articles

Thermophysical properties of molten stainless steel containing 5mass%B$$_{4}$$C

Fukuyama, Hiroyuki*; Higashi, Hideo*; Yamano, Hidemasa

Nuclear Technology, 205(9), p.1154 - 1163, 2019/09

https://doi.org/10.1080/00295450.2019.1578572
 Times Cited Count：33 Percentile：97.42(Nuclear Science & Technology)

An electromagnetic-levitation technique performed in a static magnetic field was used to measure the density, surface tension, normal spectral emissivity, heat capacity, and thermal conductivity of molten 316L stainless steel (SS316L) and SS316L that contained 5mass%B$$_{4}$$C. The addition of 5mass%B$$_{4}$$C to SS316L yielded reductions of 111 K, 6%, 19%, and 6% in the liquidus temperature, density, normal spectral emissivity, and thermal conductivity at the liquidus temperature of SS316L, respectively. The heat capacity increased by 5% with this addition. Although the 5mass%B$$_{4}$$C addition had no clear effect on the surface tension, sulfur dissolved in the SS316L resulted in a significant decrease in the surface tension.

Journal Articles

Thermal property measurements on Li$$_{2}$$TiO$$_{3}$$ added with TiO$$_{2}$$

Hoshino, Tsuyoshi; Kobayashi, Takeshi*; Nashimoto, Makoto*; Kawamura, Hiroshi; Dokiya, Masayuki*; Terai, Takayuki*; Yamawaki, Michio*; Takahashi, Yoichi*

JAERI-Conf 2004-012, p.140 - 147, 2004/07

https://jopss.jaea.go.jp/pdfdata/JAERI-Conf-2004-012.pdf

no abstracts in English

Journal Articles

High-temperature thermophysical property measurements on non-stoichiometric composition of Li$$_{2}$$TiO$$_{3}$$

Hoshino, Tsuyoshi; Kobayashi, Takeshi*; Nashimoto, Makoto*; Kawamura, Hiroshi; Terai, Takayuki*; Yamawaki, Michio*; Takahashi, Yoichi*

Journal of the Ceramic Society of Japan, Supplement, Vol.112, No.1 (CD-ROM), p.S354 - S357, 2004/05

no abstracts in English

Journal Articles

Heat capacities of technetium metal and technetium-ruthenium alloy

Shirasu, Yoshiro; Minato, Kazuo

Journal of Alloys and Compounds, 337(1-2), p.243 - 247, 2002/05

https://doi.org/10.1016/S0925-8388(01)01933-8
 Times Cited Count：3 Percentile：29.88(Chemistry, Physical)

no abstracts in English

Journal Articles

Enthalpy and heat capacity of (Ca$$_{1-x}$$Pu$$_{x}$$)TiO$$_{3}$$(x=0 and 0.20)

Sato, Tsuyoshi*; Yamazaki, Satoshi*; Yamashita, Toshiyuki; Matsui, Tsuneo*; Nagasaki, Takanori*

Journal of Nuclear Materials, 294(1-2), p.135 - 140, 2001/04

https://doi.org/10.1016/S0022-3115(01)00470-6
 Times Cited Count：2 Percentile：19.6(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

CompalisonoFnlermohydraulicCharacteristicsintheuseofvariousCoolants

; ; *; Yamaguchi, Akira

JNC TN9400 2000-109, 96 Pages, 2000/11

JNC-TN9400-2000-109.pdf:9.56MB

Numerical calculations were carried out for a free surface sloshing, a thermal stratification, a thermal striping, and a natural convection as key phenomena of in-vessel thermohydraulics in future fast reactor systems with various fluids as coolants. This numerical work was initiaied based on a recognition that the fundamental characteristics of the phenomena have been unsolved quantitatively in the use of various coolants. From the analysis for the phenomena, the following results were obtained. [Free Surface Sloshing phenomena] (1)Ther is no remarkable difference betweeen liquid sodium and luquid Pb-Bi in characteristics of internal flows and free surface charatristics based on Fr number. (2)the AQUA-VOF code has a potentiall enough to evaluate gas entrainment behavior from the free surface including the internal flow characteristics. [thermal Stratification Phenomena] (1)On-set position of thermal entainment process due to dynamic vortex flows was moved to downstream direction with decreasing of Ri number. 0n the other hand, the position in the case of C0$$_{2}$$ gas was shifted to upstream side with decreasing of Ri number. (2)Destruction speed of the thermal stratyification interface was dependent on thermal diffusivity as fluid properties. therefor it was concluded that an elimination method is necessary for the interface generated in C0$$_{2}$$ gas. [thermal Striping Phenomena] (1)Large amplitudes of fluid temperature fluctuations was reached to down stream area in the use of CO$$_{2}$$ gas, due to larger fluid viscosity and smaller thermal diffusivity, compared with liquid sodium and liquid Pb-Bi cases. (2)To simulate thermal striping conditions such as amplitude and frequency of the fluid temperature fluctuations, it isnecessary for coincidences of Re number for the amplitude and of velocity value for the frequency, in various coolants. [Natural Convection Phenomena] (1)Fundamental behavior of the natural convection in various coolant follows buoyant jet ....

Journal Articles

Thermal conductivity of actinide mononitride solid solutions

Arai, Yasuo; Nakajima, Kunihisa; Suzuki, Yasufumi

Journal of Alloys and Compounds, 271-273, p.602 - 605, 1998/00

https://doi.org/10.1016/S0925-8388(98)00168-6
 Times Cited Count：16 Percentile：67.98(Chemistry, Physical)

no abstracts in English

Journal Articles

Thermophysical and thermodynamic properties of actinide mononitrides and their solid solutions

Suzuki, Yasufumi; Arai, Yasuo

Journal of Alloys and Compounds, 271-273, p.577 - 582, 1998/00

https://doi.org/10.1016/S0925-8388(98)00160-1
 Times Cited Count：39 Percentile：85.49(Chemistry, Physical)

no abstracts in English

JAEA Reports

Effects of pitching and rolling on reactor power; Reactor noise analysis on a voyage for the N.S. Mutsu power-up tests

*; Kyoya, Masahiko; *; *

JAERI-M 91-021, 61 Pages, 1991/03

JAERI-M-91-021.pdf:1.79MB

no abstracts in English

Journal Articles

High temperature heat capacities and electrical conductivities of boron carbides

Matsui, Tsuneo*; *; *; Imai, Hisashi

Journal of Nuclear Materials, 186, p.7 - 12, 1991/00

https://doi.org/10.1016/0022-3115(91)90345-8
 Times Cited Count：13 Percentile：78.38(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Analysis of plant thermohydraulic response for the Monju PRA study; Evaluation of decay heat removal capability of auxiliary cooling system

*; *

PNC TN9410 88-130, 118 Pages, 1988/10

PNC-TN9410-88-130.pdf:5.42MB

In the Probabilistic Risk Assessment (PRA) of Monju, annual frequency of core damage was evaluated by the systems analysis for each accident category. Common mode or cause failure to open the stop valves of Auxiliary Cooling System (ACS) was found to be the most dominant contributor to the core damage frequency caused by Protected-Loss-Of-Heat-Sink (PLOHS) accidents. In this study, possibility of the recovery from the PLOHS condition by opening bypass valves has been investigated using Loop version of Super System Code (SSC-L). The bypass valve is located in parallel to the stop valve of ACS. Success criterion for the recovery has been proposed and general characteristics of the natural circulation decay heat removal have been pointed out. 0pening of the bypass valve in more than two loops is the proposed criterion for the successful decay heat removal by natural circulation. Based on a sensitivity analysis, it has been found that the grace time for the recovery action is sufficiently long. Upper bound of the pressure loss coefficient of the bypass valve has been also selected as a parameter for the sensitivity analysis to check the certainty of the conclusion. It has been found that the conclusion is supported within the uncertainty range of the pressure loss coefficient. In the situations where the stop valves are opened successfully, the decay heat can be removed by one loop natural circulation. Furthermore, the maximum coolant temperature reduces considerably by taking into account the mass heat capacity of the remaining two loops. The decay heat removal characteristics in the natural circulation mode are summarized as follows: (1)As the number of available heat transport loops lessens, the mass flow rate and heat removal capability per loop decreases. (2)The maximum coolant temperature is sensitive to the mass heat capacity of the plant system. Therefore, availability of the fluid and structural mass heat capacity should be investigated carefully ...

Journal Articles

Radiation heat transfer by solid suspension daminar flow with radiating fluid in a circular tube with constant wall temperature

*; ; *; Okamoto, Yoshizo

Nihon Genshiryoku Gakkai-Shi, 15(8), p.557 - 561, 1973/08

https://doi.org/10.3327/jaesj.15.557

no abstracts in English

Oral presentation

Study on eutectic melting behavior of control rod materials in core disruptive accidents of sodium-cooled fast reactors, 8; Emissivity, heat capacity and thermal conductivity of 10mass%B$$_{4}$$C-SS eutectic molten material

Higashi, Hideo*; Fukuyama, Hiroyuki*; Yamano, Hidemasa

no journal, , 

To develop thermosphysical property model to simulate eutectic reaction behavior of B$$_{4}$$C as control rod material and stainless steel (SS) in core disruptive accident of sodium-cooled fast reactor, this paper reports measurement results of emissivity, heat capacity and thermal conductivity of 10mass%B$$_{4}$$C-SS melt by noncontact laser modulation calorimetry with very high temperature physical property measurement system (PROSPECT).

Oral presentation

Heat capacity measurements of cement materials

Sasada, Yuto*; Miyazaki, Yuji*; Nakano, Motohiro*; Matsuo, Yusuke*; Walker, C.*; Sasamoto, Hiroshi; Mihara, Morihiro

no journal, , 

Cementitous materials are to be used in large quantities in the geological disposal of highly radioactive TRU waste. Thermodynamic data on cement hydrate minerals are important to model the long-term dissolution behavior of cement materials during the reaction of these materials with groundwater. Portlandite (Ca(OH)$$_{2}$$) is a major component (20 to 25 wt%) of hydrated Portland cement. Low temperature heat capacity measurements of three types of portlandite (low purity, high purity, and large crystal) showed purity dependence. The large crystal sample followed Debye's T$$^{3}$$ rule at low temperatures, while the high and low purity samples showed upturn of heat capacity, possibly due to difference in absorbed water vapor and/or calcite (CaCO$$_{3}$$) contamination. Heat capacities of the cement hydrates (ettringite:Ca$$_{6}$$(Al(OH)$$_{6}$$)$$_{2}$$(SO$$_{4}$$)$$_{3}$$(H$$_{2}$$O)$$_{n}$$ and monosulfate:Ca$$_{4}$$Al$$_{2}$$(OH)$$_{12}$$(SO$$_{4}$$)(H$$_{2}$$O)$$_{n}$$) exhibited phase transitions associated with the hydration water.

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