Transactions of the ASME . Journal of engineering for gas turbines and power, Vol. 132 N° 10. Journal of engineering for gas turbines and power - Octobre 2010
| Titre : | Transactions of the ASME . Journal of engineering for gas turbines and power, Vol. 132 N° 10. Journal of engineering for gas turbines and power - Octobre 2010 |
| Type de document : | Bulletin |
| Paru le : | 06/09/2011 |
Dépouillements
Article : texte imprimé
Julian K. Benz, Auteur ;
Ji Hyun Kim, Auteur ;
Ronald G. Ballinger, Auteur
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The effect of oxygen partial pressure on crack growth rates in Alloy 617 has been studied using both static and fatigue loadings at 650°C over the oxygen partial pressure range 10−19−10−3 atm. Tests were conducted at either the constant stress [...]
Article : texte imprimé
Ian de Curieres, Auteur ;
Marie-Christine Meunier, Auteur ;
Pierre Joly, Auteur
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The aim of the paper is to introduce methods to estimate the residual life of steam generators with alloy 600 thermally treated (TT) tubing, taking into account primary water stress corrosion cracking (PWSCC) as the main contributor damage. The [...]
Article : texte imprimé
Sou Watanabe, Auteur ;
Ichiro Goto, Auteur ;
Yuichi Sano, Auteur
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The Japan Atomic Energy Agency is conducting research and development study on the engineering scale extraction chromatography system, which uses silica-based adsorbents impregnated with an extractant for the minor actinides (Am and Cm) recovery[...]
Article : texte imprimé
Manish Sharma, Auteur ;
P. K. Vijayan, Auteur ;
D. S. Pilkhwal, Auteur
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Supercritical water (SCW) has excellent heat transfer characteristics as a coolant for nuclear reactors. Besides it results in high thermal efficiency of the plant. However, the flow can experience instabilities in supercritical water cooled rea[...]
Article : texte imprimé
Jun Manabe, Auteur ;
Jiro Kasahara, Auteur ;
Issaku Fujita, Auteur
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The moisture separator reheater (MSR) is a key piece of equipment in reheat systems in nuclear steam turbines that use saturated main steam, where it helps improve turbine efficiency and suppress flow-accelerated corrosion. Fundamental to achiev[...]
Article : texte imprimé
Giorgio Locatelli, Auteur ;
Mauro Mancini, Auteur
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Small-medium reactors (SMRs) are going to be important players in the worldwide nuclear renaissance. The economy of scale plays against the development of this kind of reactors, even if sometimes its influence is overestimated so that SMRs appea[...]
Article : texte imprimé
S. P. Aktershev, Auteur ;
V. V. Ovchinnikov, Auteur
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The boiling up of a metastable liquid when the vaporization fronts appear is considered theoretically and experimentally. Boiling up occurs usually on the surface of a heater. At the first stage, the growth of a spherical vapor bubble is observe[...]
Article : texte imprimé
Nobuyuki Kimura, Auteur ;
Toshiki Ezure, Auteur ;
Hiroyuki Miyakoshi, Auteur
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An innovative sodium cooled fast reactor has been investigated as part of the fast reactor cycle technology development project. In the reactor, a compact reactor vessel (R/V) with increased sodium flow velocity was designed to reduce the constr[...]
Article : texte imprimé
Sibamoto Yasuteru, Auteur ;
Maruyama Yu, Auteur ;
Nakamura Hideo, Auteur
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A series of experiments was performed for rewetting phenomena on dried-out fuel rod surfaces under post-boiling transition (post-BT) conditions with high-pressure and high-water flow rate simulating anticipated operational occurrences of a BWR. [...]
Article : texte imprimé
Yukihiro Iguchi, Auteur ;
Masami Kato, Auteur
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During decommissioning of nuclear facilities, it is generally thought that the risk is relatively low after high activity inventory such as the spent fuel is removed. However, dismantlement works may be carried out with nonmultiple barriers with[...]
Article : texte imprimé
C. Zamfirescu, Auteur ;
G. F. Naterer, Auteur ;
I. Dincer, Auteur
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This paper presents a new heat upgrading method that utilizes waste heat from nuclear reactors for thermochemical water splitting with a copper-chlorine (Cu–Cl) cycle. Through combined power, hydrogen, and oxygen generation, the exergy efficienc[...]
Article : texte imprimé
F. Balbaud-Célérier, Auteur ;
L. Martinelli, Auteur
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Among the Generation IV systems, sodium fast reactors (SFRs) are promising and benefits of considerable technological experience. However, the availability and acceptability of the SFR are affected by the problems linked with the sodium-water re[...]
Article : texte imprimé
P. K. Vijayan, Auteur ;
M. Sharma, Auteur ;
D. S. Pilkhwal, Auteur
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A one-dimensional theoretical model has been used to analyze the steady state and stability performance of a single-phase, two-phase, and supercritical natural circulation in a uniform diameter rectangular loop. Parametric influences of diameter[...]
Article : texte imprimé
D. Chatzikyriakou, Auteur ;
S. P. Walker, Auteur ;
B. Belhouachi, Auteur
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During the reflood phase, following a loss-of-coolant-accident (LOCA), the main mechanism for the precursory cooling of the fuel is by convective heat transfer to the vapor, with the vapor being cooled by the evaporation of the entrained saturat[...]
Article : texte imprimé
Konstantin Mikityuk, Auteur ;
Jiri Krepel, Auteur ;
Sandro Pelloni, Auteur
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The FAST code system is currently being developed and used at the Paul Scherrer Institut for static and transient analysis of the main Generation 4 fast-spectrum reactor concepts: sodium-, helium-, and gas-cooled fast reactors. The code system i[...]
Article : texte imprimé
Mikko I. Jyrkama, Auteur ;
Mahesh D. Pandey, Auteur ;
Stephen M. Hess, Auteur
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The main objective of generation risk assessment (GRA) is to assess the impact of equipment unavailability and failures on the ability of the plant to produce power over time. The system reliability models employed for this purpose are based on [...]
Article : texte imprimé
Kevan D. Weaver, Auteur ;
John Gilleland, Auteur ;
Charles Ahlfeld, Auteur
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A paradigm shift has altered the design targets for advanced nuclear energy systems that use a fast neutron spectrum. Whereas designers previously emphasized the ability of fast reactors to extend global reserves of fissile fuels, the overriding[...]
Article : texte imprimé
Naoki Soneda, Auteur ;
Akiyoshi Nomoto, Auteur
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Neutron irradiation embrittlement of reactor pressure vessel steels is an important aging issue for the long-term operation of light water reactors. A new embrittlement correlation method was developed by Central Research Institute of Electric P[...]
Article : texte imprimé
Norimichi Yamashita, Auteur ;
Masanobu Iwasaki, Auteur ;
Koji Dozaki, Auteur
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Neutron irradiation embrittlement of reactor pressure vessel steels (RPVs) is one of the important material aging issues. In Japan, almost 40 years have past since the first plant started its commercial operation, and several plants are expected[...]
Article : texte imprimé
Wen xi Tian, Auteur ;
Sui-zheng Qiu, Auteur ;
Guang-hui Su, Auteur
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Single vacuum bubble collapse in subcooled water has been simulated using the moving particle semi-implicit (MPS) method in the present study. The liquid is described using moving particles, and the bubble-liquid interface was set to be the vacu[...]
Article : texte imprimé
R. Vijayashree, Auteur ;
R. Veerasamy, Auteur ;
Sudheer Patri, Auteur
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Prototype fast breeder reactor is U–PuO2 fueled sodium cooled pool type fast reactor and it is currently under construction at Kalpakkam, India. Prototype fast breeder reactor is equipped with two independent fast acting and diverse shutdown sys[...]
Article : texte imprimé
Tomio Okawa, Auteur ;
Takahiro Harada, Auteur ;
Yuta Kotsusa, Auteur
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Using a static contact angle of a vertical heated wall as a main experimental parameter, a photographic study was carried out to elucidate the mechanisms to determine the vapor bubble dynamics during subcooled pool boiling. The test fluid was di[...]
Article : texte imprimé
Peng Wang, Auteur ;
Libo Qian, Auteur ;
Dalin Zhang, Auteur
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The new concept molten salt reactor is the only liquid-fuel reactor of the six Generation IV advanced nuclear energy systems. The liquid molten salt serves as the fuel and coolant simultaneously and causes one important feature: the delayed neut[...]
Article : texte imprimé
Xiaoyang Gaus-Liu, Auteur ;
Alexei Miassoedov, Auteur ;
Thomas Cron, Auteur
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Core melt solidification phenomena in the lower plenum of pressurized reactor vessel during external reactor vessel cooling is investigated in late in-vessel phase experiment tests under different external cooling conditions and melt pouring pos[...]
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