Reheat-Air Brayton Combined Cycle Power Conversion Design and Performance Under Nominal Ambient Conditions

Andreades, Charalampos; Scarlat, Raluca O.; Dempsey, Lindsay; Peterson, Per F.

doi:10.1115/1.4026506

Cited by 19 publications

(10 citation statements)

References 6 publications

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“…The turbine exhaust is routed to an HRSG with a triple pressure steam bottoming cycle. The above modifications are discussed in detail in a companion paper [1]. The design-point (International Organization of Standards (ISO) conditions) performance characteristics of the RACC are shown in Table 1.…”

Section: Baseline Design Selectionmentioning

confidence: 99%

“…Berkeley, sponsored by the U.S. Department of Energy, has identified approaches to achieve net thermal efficiency above 40% with heat provided by fluoride-saltcooled, high temperature reactors (FHRs), molten salt reactors (MSRs), and high-temperature concentrating solar power (CSP) heat sources. This reheat air combined cycle (RACC), described in a companion paper [1], uses external heating of the air, with a single stage or two stages of reheat. The injection of natural gas or other fuels after the last reheat stage can be used to boost power output, to provide peaking power and other grid reliability, and support services such as frequency regulation.…”

Section: Introductionmentioning

confidence: 99%

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Reheat Air-Brayton Combined Cycle Power Conversion Off-Nominal and Transient Performance

Andreades

Dempsey

Peterson

2014

Journal of Engineering for Gas Turbines and Power

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Because molten fluoride salts can deliver heat at temperatures above 600 °C, they can be used to couple nuclear and concentrating solar power heat sources to reheat air combined cycles (RACC). With the open-air configuration used in RACC power conversion, the ability to also inject natural gas or other fuel to boost power at times of high demand provides the electric grid with contingency and flexible capacity while also increasing revenues for the operator. This combination provides several distinct benefits over conventional stand-alone nuclear power plants and natural gas combined cycle and peaking plants. A companion paper discusses the necessary modifications and issues for coupling an external heat source to a conventional gas turbine and provides two baseline designs (derived from the GE 7EB and Alstom GT24). This paper discusses off-nominal operation, transient response, and start-up and shutdown using the GE 7EB gas turbine as the reference design.

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Section: Baseline Design Selectionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Reheat Air-Brayton Combined Cycle Power Conversion Off-Nominal and Transient Performance

Andreades

Dempsey

Peterson

2014

Journal of Engineering for Gas Turbines and Power

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“…The first molten-salt reactor was built for the Aircraft Nuclear Propulsion Program in the 1950s, with a sodium intermediate loop to transfer heat from the reactor to aircraft jet engines-partly because sodium enabled design of very efficient sodium-to-air heat exchangers within the jet engine. Today there is an interest in coupling salt reactors to nuclear air-Brayton combined cycle power systems that have high efficiency and the ability to rapidly vary power levels [Andreades 2014, Forsberg 2016, Fathi 2018. For such systems, sodium is one candidate for the intermediate loop between reactor and power cycle.…”

Section: Sodium System Heat Storage Optionsmentioning

confidence: 99%

Heat Storage Options for Sodium, Salt and Helium Cooled Reactors to Enable Variable Electricity to the Grid and Heat to Industry with Base-Load Reactor Operations

Forsberg

Sabharwall

2018

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Electricity markets are changing rapidly because of (1) the addition of wind and solar and (2) the goal of a low-carbon electricity grid. These changes result in times of high electricity prices and very low or negative electricity prices. California has seen its first month where more than 20% of the time (mid-day) the wholesale price of electricity was zero or negative. This creates large incentives for coupling heat storage to advanced reactors to enable variable electricity and industrial-heat output (maximize revenue) while the reactor operates at base load (minimize cost).Recent studies have examined coupling various types of heat storage to Rankine and Brayton power cycles. However, there has been little examination of heat-storage options between (1) the reactor and (2) the power-conversion system or industrial customer. Heat-storage systems can be incorporated into sodium, helium-, and salt-cooled reactors. Salt-cooled reactors include the fluoride-salt-cooled high-temperature reactor (FHR) with its solid fuel and clean coolant and the molten salt reactor (MSR) with its fuel dissolved in the salt. For sodium and salt reactors, it is assumed that a heat-storage system would be in the secondary loop between the reactor and power cycle. For helium-cooled reactors, heat storage can be in the primary or secondary loop.This report is a first look at the rational and the heat storage options for deploying gigawatt-watt hour heat-storage systems with GenIV reactors. Economics and safety are the primary selection criteria. The leading heat-storage candidate for sodium-cooled systems (a low-pressure secondary system with small temperature drop across the reactor core) is steel in large tanks with the sodium flowing through channels to move heat in and out of storage. The design minimizes sodium volume in the storage and, thus, the risks and costs associated with sodium. For helium systems (high-pressure with large temperature drop across the core), the leading heat storage options are (1) varying the temperature of the reactor core, (2) steel or alumina firebrick in a secondary pressure vessel and (3) nitrate or hot-rock/firebrick at atmospheric pressure. For salt systems (low pressure, high temperatures, and small temperature drop across the reactor core) the leading heat-storage systems are secondary salts. In each case, options are identified and questions to be addressed are identified.In some cases there is a strong coupling between the heat-storage technology and the power cycle. The leading sodium heat-storage technology may imply changes in the power cycle. High-temperature salt systems couple efficiency to Brayton power cycles that may create large incentives for the heat storage to remain within the power cycle rather than in any intermediate heat transfer loop.iv v CANES PUBLICATIONSTopical and progress reports are published under seven series:

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“…The design of the NACC was performed using GE's extensive technical literature, while performance was estimated using Thermoflow's THERMOFLEX ® , a commercial power cycle modeling tool. Detailed design and performance estimation studies under nominal and off-nominal conditions of the NACC are provided by Andreades et al 7,8 Another ability of the NACC is to decouple power conversion transients from the reactor due to the open cycle configuration. This reduces risks involved with lossof-load events, for example, as the reactor will not feel this transient.…”

Section: Iia Nuclear Air-brayton Combined Cyclementioning

confidence: 99%

“…At 600°C and above, hydrogen isotope absorption on graphite occurs through chemisorption. If all of the tritium produced by the Mk1 were to be absorbed on the pebble and graphite fuel in the 1.4 years before discharge, then a loading of 2 to 10 parts per million by weight T/C would be achieved (depending on the initial enrichment of 7 Li in the coolant). Based on high-temperature absorption data from the gas phase onto nuclear graphite, this loading is likely to be achievable.…”

Section: Tritium Managementmentioning

confidence: 99%

Design Summary of the Mark-I Pebble-Bed, Fluoride Salt–Cooled, High-Temperature Reactor Commercial Power Plant

et al. 2016

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TitleDesign summary of the Mark-I pebble-bed, fluoride salt-cooled, high-temperature reactor commercial power plant Abstract -The University of California, Berkeley (UCB), has developed a preconceptual design for a commercial pebble-bed (PB), fluoride salt-cooled, high-temperature reactor (FHR) (PB-FHR). The baseline design for this Mark-I PB-FHR (Mk1) plant is a 236-MW(thermal) reactor. The Mk1 uses a fluoride salt coolant with solid, coated-particle pebble fuel. The Mk1 design differs from earlier FHR designs because it uses a nuclear air-Brayton combined cycle designed to produce 100 MW(electric) of base-load electricity using a modified General

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Reheat-Air Brayton Combined Cycle Power Conversion Design and Performance Under Nominal Ambient Conditions

Cited by 19 publications

References 6 publications

Reheat Air-Brayton Combined Cycle Power Conversion Off-Nominal and Transient Performance

Reheat Air-Brayton Combined Cycle Power Conversion Off-Nominal and Transient Performance

Heat Storage Options for Sodium, Salt and Helium Cooled Reactors to Enable Variable Electricity to the Grid and Heat to Industry with Base-Load Reactor Operations

Design Summary of the Mark-I Pebble-Bed, Fluoride Salt–Cooled, High-Temperature Reactor Commercial Power Plant

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