scholarly journals High-Temperature Solar Options for Electric Utilities and Users of Process Heat

1980 ◽  
Author(s):  
Alan Skinrood
2015 ◽  
Author(s):  
Charles Forsberg ◽  
Lin-wen Hu ◽  
Per Peterson ◽  
Kumar Sridharan

2010 ◽  
Vol 34 (10) ◽  
pp. 1455-1462 ◽  
Author(s):  
Kee-Nam Song ◽  
Heong-Yeon Lee ◽  
Chan-Soo Kim ◽  
Seong-Duk Hong ◽  
Hong-Yoon Park

2020 ◽  
Vol 1 (8) ◽  
pp. 100135 ◽  
Author(s):  
Daniel S. Codd ◽  
Matthew D. Escarra ◽  
Brian Riggs ◽  
Kazi Islam ◽  
Yaping Vera Ji ◽  
...  

2011 ◽  
Vol 133 (5) ◽  
Author(s):  
Hyeong-Yeon Lee ◽  
Kee-Nam Song ◽  
Yong-Wan Kim ◽  
Sung-Deok Hong ◽  
Hong-Yune Park

A process heat exchanger (PHE) transfers the heat generated from a nuclear reactor to a sulfur-iodine hydrogen production system in the Nuclear Hydrogen Development and Demonstration, and was subjected to very high temperature up to 950°C. An evaluation of creep-fatigue damage, for a prototype PHE, has been carried out from finite element analysis with the full three dimensional model of the PHE. The inlet temperature in the primary side of the PHE was 950°C with an internal pressure of 7 MPa, while the inlet temperature in the secondary side of the PHE is 500°C with internal pressure of 4 MPa. The candidate materials of the PHE were Alloy 617 and Hastelloy X. In this study, only the Alloy 617 was considered because the high temperature design code is available only for Alloy 617. Using the full 3D finite element analysis on the PHE model, creep-fatigue damage evaluation at very high temperature was carried out, according to the ASME Draft Code Case for Alloy 617, and technical issues in the Draft Code Case were raised.


Author(s):  
M. E. Beesing

This paper describes a solar energy collector system for providing process heat to a textile drying process in a WestPoint Pepperell mill in Fairfax, Alabama. The solar collector system uses 24 single axis tracking parabolic trough concentrating collectors to heat water in a high temperature water loop. The high temperature water fuels a steam generator to provide process steam. The process that was solarized is a textile drying process using cylindrical can dryers. The dryers are utilized in the slashing operation, a textile process where yarn is treated with sizing in preparation for weaving.


Author(s):  
Matt Richards ◽  
Arkal Shenoy

Process heat from a high-temperature nuclear reactor can be used to drive a set of chemical reactions, with the net result of splitting water into hydrogen and oxygen. For example, process heat at temperatures in the range 850°C to 950°C can drive the sulfur-iodine (SI) thermochemical process to produce hydrogen with high efficiency. Electricity can also be used to split water, using conventional, low-temperature electrolysis (LTE). An example of a hybrid process is high-temperature electrolysis (HTE), in which process heat is used to generate steam, which is then supplied to an electrolyzer to generate hydrogen. In this paper we investigate the coupling of the Modular Helium Reactor (MHR) to the SI process and HTE. These concepts are referred to as the H2-MHR. Optimization of the MHR core design to produce higher coolant outlet temperatures is also discussed.


Author(s):  
Reiner W. Kuhr ◽  
Charles Bolthrunis ◽  
Michael Corbett ◽  
Ed Lahoda

This paper presents a summary of a screening study to select the most advantageous applications for nuclear process heat. The review is focused on the application of the Pebble Bed Modular Reactor (PBMR) technology adapted for process heat applications. This technology is unique in its smaller modular size and ability to deliver high temperature process heat at conditions that allow higher value applications. The implementation of projects for nuclear process heat and hydrogen production will require collaboration between nuclear power plant operators and process plant owners who will benefit from lower costs of heat delivery. Heat and hydrogen from nuclear water splitting can be used to displace expensive fuels, extend carbon utilization for products and reduce CO2 emissions and other environmental impacts.


Author(s):  
Pavel V. Tsvetkov ◽  
David E. Ames ◽  
Ayodeji B. Alajo ◽  
Tom G. Lewis

As highly efficient advanced nuclear systems, Generation IV Very High Temperature Reactors (VHTR) can be considered in a variety of configurations for electricity generation and process heat applications. Simultaneous delivery of electricity, low-temperature process heat (for potable water production, district heating, etc.) and high temperature process heat (for hydrogen production, etc.) by a single cogeneration system offers unique deployment options as “all-in-one” power stations. This paper is focused on the VHTR-based systems for autonomous co-generation applications. The analysis is being performed within the scope of the U.S. DOE NERI project on utilization of higher actinides (TRUs and partitioned MAs) as a fuel component for extended-life VHTR configurations. It accounts for system performance characteristics including VHTR physics features, control options and energy conversion efficiencies. Utilization of TRUs in VHTRs is explored to stabilize in-core fuel compositions (core self-stabilization) leading to extended single-batch OTTO (Once-Through-Then-Out) modes of operation without intermediate refueling.


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