Journal of Engineering for Gas Turbines and Power: Recent submissions
Now showing items 4621-4640 of 9564
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A Once-Through Fuel Cycle for Fast Reactors
(The American Society of Mechanical Engineers (ASME), 2010)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 ... -
Characteristics of the New Embrittlement Correlation Method for the Japanese Reactor Pressure Vessel Steels
(The American Society of Mechanical Engineers (ASME), 2010)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 ... -
FAST Code System: Review of Recent Developments and Near-Future Plans
(The American Society of Mechanical Engineers (ASME), 2010)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-, ... -
Risk-Informed Approach for the Regulation of Decommissioning of Nuclear Facilities
(The American Society of Mechanical Engineers (ASME), 2010)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 ... -
Three Dimensional Modeling of the Hydrodynamics of Oblique Droplet-Hot Wall Interactions During the Reflood Phase After a LOCA
(The American Society of Mechanical Engineers (ASME), 2010)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 ... -
Upgrading of Waste Heat for Combined Power and Hydrogen Production With Nuclear Reactors
(The American Society of Mechanical Engineers (ASME), 2010)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, ... -
Integration of Degradation Models Into Generation Risk Assessment: Challenges and Modeling Approaches
(The American Society of Mechanical Engineers (ASME), 2010)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 ... -
Modeling of Fe–Cr Martensitic Steels Corrosion in Liquid Lead Alloys
(The American Society of Mechanical Engineers (ASME), 2010)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 ... -
Competitiveness of Small-Medium, New Generation Reactors: A Comparative Study on Decommissioning
(The American Society of Mechanical Engineers (ASME), 2010)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 ... -
Chromatography Column System With Controlled Flow and Temperature for Engineering Scale Application
(The American Society of Mechanical Engineers (ASME), 2010)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 ... -
Effect of Oxygen Potential on Crack Growth in Alloys for Advanced Energy Systems
(The American Society of Mechanical Engineers (ASME), 2010)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 ... -
Measurement and Analysis for Rewetting Velocity Under Post-BT Conditions During Anticipated Operational Occurrence of BWR
(The American Society of Mechanical Engineers (ASME), 2010)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 ... -
Experimental Study on Gas Entrainment Due to Nonstationary Vortex in a Sodium Cooled Fast Reactor—Comparison of Onset Conditions Between Sodium and Water
(The American Society of Mechanical Engineers (ASME), 2010)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 ... -
Recent Moisture Separator Reheater Design Technologies
(The American Society of Mechanical Engineers (ASME), 2010)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 ... -
Hydrogen Peroxide-Based Gas Generator Design and Performance Testing as an Aircraft Emergency Power Unit
(The American Society of Mechanical Engineers (ASME), 2010)Hydrazine monopropellant is often used with a spontaneous catalyst a high-performance aircraft emergency power unit (EPU) and in aerospace propulsion; however, it is toxic and requires special ... -
Steady Propagation of the Vaporization Front in Metastable Liquid
(The American Society of Mechanical Engineers (ASME), 2010)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 ... -
Residual Life Assessment of Steam Generators With Alloy 600 TT Tubing: Methods and Application
(The American Society of Mechanical Engineers (ASME), 2010)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 ... -
Linear and Nonlinear Stability Analysis of a Supercritical Natural Circulation Loop
(The American Society of Mechanical Engineers (ASME), 2010)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 ... -
Investigation of Hydrogen Emissions in Partially Premixed Diesel Combustion
(The American Society of Mechanical Engineers (ASME), 2010)Partially premixed combustion strategies offer many advantages for compression ignition engines. One such advantage for those operating on diesel fuels is the simultaneous reduction in soot and ... -
ASTEC, COCOSYS, and LIRIC Interpretation of the Iodine Behavior in the Large-Scale THAI Test Iod-9
(The American Society of Mechanical Engineers (ASME), 2010)The large-scale iodine test Iod-9 of the German Thermal hydraulics, Hydrogen, Aerosols, Iodine (THAI) program was jointly interpreted by means of post-test analyses within the THAI Circle of the ...