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Journal Articles

Calcium silicate hydrate (C-S-H) gel solubility data and a discrete solid phase model at 25$$^{circ}$$C based on two binary non-ideal solid solutions

Walker, C.; Suto, Shunkichi; Oda, Chie; Mihara, Morihiro; Honda, Akira

Cement and Concrete Research, 79, p.1 - 30, 2016/01

 Times Cited Count:69 Percentile:90.42(Construction & Building Technology)

Modeling the solubility behavior of calcium silicate hydrate (C-S-H) gel is important to make quantitative predictions of the degradation of hydrated ordinary Portland cement (OPC) based materials. Experimental C-S-H gel solubility data have been compiled from the literature, critically evaluated and supplemented with new data from the current study for molar Ca/Si ratios = 0.2-0.83. All these data have been used to derive a discrete solid phase (DSP) type C-S-H gel solubility model based on two binary non-ideal solid solutions in aqueous solution(SSAS). Features of the DSP type C-S-H gel solubility model include satisfactory predictions of pH values and Ca and Si concentrations for all molar Ca/Si ratios = 2.7 $$rightarrow$$ 0 in the C-S-H system, portlandite (CH) for Ca/Si ratios $$>$$ 1.65, congruent dissolution at Ca/Si ratios = 0.85, and amorphous silica (SiO$$_{2 (rm am)}$$) for Ca/Si ratios $$<$$ 0.55 as identified in the current study by IR spectroscopy.

Journal Articles

Studies in the PuO$$_{2}$$-ZrO$$_{2}$$ pseudo-binary phase diagram

Albiol, T.*; Serizawa, Hiroyuki; Arai, Yasuo

Journal of Nuclear Science and Technology, 39(Suppl.3), p.834 - 837, 2002/11

no abstracts in English

JAEA Reports

Estimation of thermochemical behavior of spallation products in mercury target

Kobayashi, Kaoru*; Kaminaga, Masanori; Haga, Katsuhiro; Kinoshita, Hidetaka; Aso, Tomokazu; Teshigawara, Makoto; Hino, Ryutaro

JAERI-Tech 2002-005, 118 Pages, 2002/02

JAERI-Tech-2002-005.pdf:9.71MB

In order to examine the radiation safety of a spallation mercury target system, it is necessary to clarify the chemical forms of spallation products generated by spallation reaction with proton beam. As for the chemical forms of spallation products in mercury that involves large amounts of spallation products, these forms were estimated by using the binary phase diagrams and the thermochemical equilibrium calculation based on the amounts of spallation product. Calculation results showed that the mercury would dissolve Al, As, B, Be, Bi, C, Co, Cr, Fe, Ga, Ge, Ir, Mo, Nb, Os, Re, Ru, Sb, Si, Ta, Tc, V and W in the element state, and Ag, Au, Ba, Br, Ca, Cd, Ce, Cl, Cs, Cu, Dy, Er, Eu, F, Gd, Hf, Ho, I, In, K, La, Li, Lu, Mg, Mn, Na, Nd, Ni, O, Pb, Pd, Pr, Pt, Rb, Rh, S, Sc, Se, Sm, Sn, Sr, Tb, Te, Ti, Tl, Tm, Y, Yb, Zn and Zr in the form of inorganic mercury compounds.

Journal Articles

Evaluation on chemical state of irradiated rock-like oxide fuels by nuclear and chemical modeling

Nitani, Noriko; Kuramoto, Kenichi; Yamashita, Toshiyuki; Omichi, Toshihiko*

Progress in Nuclear Energy, 38(3-4), p.435 - 438, 2001/02

 Times Cited Count:1 Percentile:11.99(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

None

Yamanaka, Shinsuke*; Abe, Kazuyuki

JNC TY9400 2000-004, 78 Pages, 2000/03

JNC-TY9400-2000-004.pdf:2.39MB

no abstracts in English

JAEA Reports

Thermochemical evaluation and preparation of cesium uranates

Takano, Masahide; Minato, Kazuo; Fukuda, Kosaku; Sato, Seichi*; Ohashi, Hiroshi*

JAERI-Research 97-021, 19 Pages, 1997/03

JAERI-Research-97-021.pdf:0.74MB

no abstracts in English

JAEA Reports

Development of DPS (Deformable Plasma Simulation) Code

Senda, Ikuo*; Shoji, Teruaki; Nishio, Satoshi; Tsunematsu, Toshihide; *; Fujieda, Hirobumi*

JAERI-Data/Code 95-010, 32 Pages, 1995/08

JAERI-Data-Code-95-010.pdf:1.02MB

no abstracts in English

Journal Articles

Development of high energy transport code HETC-3STEP applicable to the nuclear reaction with incident energies above 20MeV

Yoshizawa, Nobuaki*; *; Takada, Hiroshi

Journal of Nuclear Science and Technology, 32(7), p.601 - 607, 1995/07

 Times Cited Count:27 Percentile:90.45(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Development of the JFT-2M data analysis software system on the mainframe computer

Matsuda, Toshiaki; *; *; *; *

JAERI-M 90-201, 24 Pages, 1990/11

JAERI-M-90-201.pdf:0.76MB

no abstracts in English

Oral presentation

Chemical impacts of boron on the cesium release and transport behavior under severe accident conditions, 1; Prediction of chemical forms of cesium just after release from fuel in the presence of boron

Miwa, Shuhei; Yamashita, Shinichiro; Osaka, Masahiko

no journal, , 

The effects of temperature and atmosphere on cesium (Cs) chemical form just after release from fuel were estimated using chemical equilibrium calculation with consideration of the release kinetics of Cs, iodine (I), boron (B) and so on depending on temperature and atmosphere under a severe accident. The calculation results show that Cs vapor species changed according to temperature and atmosphere, and CsBO$$_{2}$$ vapor species was dominant with the existence of B regardless of temperature and atmosphere.

Oral presentation

Thermodynamic evaluation on chemical reaction between UO$$_{2}$$ and SiC in LWR conditions

Shirasu, Noriko; Kurata, Masaki

no journal, , 

After Fukushima Daiichi nuclear accident in 2011, enhancing the accident tolerance of light water reactor fuels became a very important issue and currently the development of accident-tolerant fuel (ATF) are in progress. SiC is an attractive candidate of ATF cladding material because of its high chemical stability, high radiation resistance and low neutron absorption. SiC reacts much less than Zircaloy with steam, the generation of heat and hydrogen gas would be extremely suppressed. Thermodynamic evaluation on chemical interactions between UO$$_{2}$$ and SiC were performed on various possible conditions of oxygen potential and temperature in severe accident. SiC is converted to SiO$$_{2}$$ by reaction with O$$_{2}$$. SiC is also converted to SiO$$_{2}$$ by reaction with H$$_{2}$$O. However, the fraction of the sub-reaction for forming SiO increases than in the case of reaction with O$$_{2}$$ when comparing the results at the same temperatures and the same oxygen potentials.

Oral presentation

Research and development on preceding processing methods for contaminated water management wasteat Fukushima Daiichi Nuclear Power Station, 24; Experimental and modeling studies on the dissolution behavior of cement solidified body with modified wastes

Kobayashi, Yutaro*; Haga, Kazuko*; Kaneda, Yoshihisa*; Sato, Tsutomu*; Kakuda, Ayaka; Osugi, Takeshi; Sone, Tomoyuki; Kuroki, Ryoichiro

no journal, , 

no abstracts in English

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