Advanced Nuclear Process Heat Concepts and Applications

2006 ◽  
Author(s):  
Reiner W. Kuhr ◽  
Charles Bolthrunis ◽  
Michael Corbett ◽  
Ed Lahoda
Keyword(s):  
High Temperature ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Carbon Utilization ◽  
Nuclear Process ◽  
High Temperature Process ◽  
Process Plant ◽  
Screening Study ◽  
Process Heat

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.

Verification of Alarm Displays for the Nuclear Power Plant With Two Modular High-Temperature Gas-Cooled Reactors

2018 ◽  
Author(s):  
Jia Qianqian ◽  
Guo Chao ◽  
Li Jianghai ◽  
Qu Ronghong
Keyword(s):  
High Temperature ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Modular Design ◽  
Early Stage ◽  
Integrated System ◽  
Alarm System ◽  
Control Room ◽  
High Temperature Gas

The nuclear power plant with two modular high-temperature gas-cooled reactors (HTR-PM) is under construction now. The control room of HTR-PM is designed. This paper introduces the alarm displays in the control room, and describes some verification and validation (V&V) activities of the alarm system, especially verification for some new human factor issues of the alarm system in the two modular design. In HTR-PM, besides the regular V&V similar to other NPPs, the interference effect of the alarm rings of the two reactor modules at the same time, and the potential discomfort of the two reactor operators after shift between them are focused. Verifications at early stage of the two issues are carried on the verification platform of the control room before the integrated system validation (ISV), and all the human machine interfaces (HMIs) in the control room, including the alarm system are validated in ISV. The test results on the verification platform show that the alarm displays and rings can support the operators understand the alarm information without confusion of the two reactors, and the shift between the two reactor operators have no adverse impact on operation. The results in ISV also show that the alarm system can support the operators well.

scholarly journals Thermal analysis of heat and power plant with high temperature reactor and intermediate steam cycle

2015 ◽  
Vol 36 (1) ◽  
pp. 3-18
Author(s):  
Adam Fic ◽  
Jan Składzień ◽  
Michał Gabriel
Keyword(s):  
Thermal Analysis ◽  
High Temperature ◽  
Heat Exchanger ◽  
Power Plant ◽  
Heat Pump ◽  
Nuclear Reactor ◽  
Temperature Level ◽  
High Temperature Process ◽  
Process Heat ◽  
Steam Cycle

Abstract Thermal analysis of a heat and power plant with a high temperature gas cooled nuclear reactor is presented. The main aim of the considered system is to supply a technological process with the heat at suitably high temperature level. The considered unit is also used to produce electricity. The high temperature helium cooled nuclear reactor is the primary heat source in the system, which consists of: the reactor cooling cycle, the steam cycle and the gas heat pump cycle. Helium used as a carrier in the first cycle (classic Brayton cycle), which includes the reactor, delivers heat in a steam generator to produce superheated steam with required parameters of the intermediate cycle. The intermediate cycle is provided to transport energy from the reactor installation to the process installation requiring a high temperature heat. The distance between reactor and the process installation is assumed short and negligable, or alternatively equal to 1 km in the analysis. The system is also equipped with a high temperature argon heat pump to obtain the temperature level of a heat carrier required by a high temperature process. Thus, the steam of the intermediate cycle supplies a lower heat exchanger of the heat pump, a process heat exchanger at the medium temperature level and a classical steam turbine system (Rankine cycle). The main purpose of the research was to evaluate the effectiveness of the system considered and to assess whether such a three cycle cogeneration system is reasonable. Multivariant calculations have been carried out employing the developed mathematical model. The results have been presented in a form of the energy efficiency and exergy efficiency of the system as a function of the temperature drop in the high temperature process heat exchanger and the reactor pressure.

PBMR as an Ideal Heat Source for High-Temperature Process Heat Applications

2006 ◽  
Author(s):  
Michael Correia ◽  
Renee´ Greyvenstein ◽  
Fred Silady ◽  
Scott Penfield
Keyword(s):  
High Temperature ◽  
Heat Source ◽  
Oil Sands ◽  
Generation Process ◽  
Steam Methane ◽  
High Temperature Process ◽  
Process Plant ◽  
Process Heat ◽  
Oil Sands Bitumen ◽  
Cycle Efficiency

The Pebble Bed Modular Reactor (PBMR) is an advanced helium-cooled, graphite-moderated High Temperature Gas-cooled Reactor (HTGR). A 400 MWt PBMR Demonstration Power Plant (DPP) for the production of electricity is being developed in South Africa. This PBMR technology is also an ideal heat source for process heat applications, including Steam Methane Reforming, steam for Oil Sands bitumen recovery, Hydrogen Production and co-generation (process heat and/or electricity and/or process steam) for petrochemical industries. The cycle configuration used to transport the heat of the reactor to the process plant or to convert the reactor’s heat into electricity or steam directly influences the cycle efficiency and plant economics. The choice of cycle configuration depends on the process requirements and is influenced by practical considerations, component and material limitations, maintenance, controllability, safety, performance, risk and cost. This paper provides an overview of the use of a PBMR reactor for process applications and possible cycle configurations are presented for applications which require high temperature process heat and/or electricity.

Very high temperature behaviour of a typical concrete from a nuclear power plant

2005 ◽  
Vol 90 (9) ◽  
pp. 117-124
Author(s):  
Sophie Malaval ◽  
Chistophe Journeau ◽  
Agnès Smith ◽  
Jean-Pierre Bonnet
Keyword(s):  
High Temperature ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Temperature Behaviour ◽  
Very High

NUCALLOY ALLOYS 453 and 488

Alloy Digest ◽  
1997 ◽  
Vol 46 (6) ◽  
Keyword(s):  
Fracture Toughness ◽  
Wear Resistance ◽  
High Temperature ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Corrosion And Wear ◽  
Cobalt Alloys ◽  
Temperature Performance ◽  
Nickel Base

Abstract NUCALLOY ALLOYS 453 and 488 are nickel-base hardfacing alloys designed to replace the traditional cobalt alloys for nuclear plant applications. These alloys have been used in Japanese commercial nuclear power plant service. This datasheet provides information on composition, physical properties, hardness, and tensile properties as well as fracture toughness. It also includes information on high temperature performance, corrosion and wear resistance as well as joining. Filing Code: Ni-528. Producer or source: Stoody Deloro Stellite Inc.

Sign in / Sign up

Export Citation Format

Share Document