Tailoring the response of Autonomous Reactivity Control (ARC) systems

Qvist, Staffan A.; Hellesen, Carl; Gradecka, Malwina; Dubberley, Allen E.; Fanning, Thomas; Greenspan, Ehud

doi:10.1016/j.anucene.2016.09.036

Title: Tailoring the response of Autonomous Reactivity Control (ARC) systems

Authors:: Qvist, Staffan A.; Hellesen, Carl; Gradecka, Malwina; Dubberley, Allen E.; Fanning, Thomas; Greenspan, Ehud

Publication Date:: Sun Jan 01 00:00:00 EST 2017

Sponsoring Org.:: USDOE

OSTI Identifier:: 1397043

Grant/Contract Number:: NE0008455

Resource Type:: Publisher's Accepted Manuscript

Journal Name:: Annals of Nuclear Energy

Additional Journal Information:: Journal Name: Annals of Nuclear Energy Journal Volume: 99 Journal Issue: C; Journal ID: ISSN 0306-4549

Publisher:: Elsevier

Country of Publication:: United Kingdom

Language:: English

Citation Formats


                    Qvist, Staffan A., Hellesen, Carl, Gradecka, Malwina, Dubberley, Allen E., Fanning, Thomas, and Greenspan, Ehud. Tailoring the response of Autonomous Reactivity Control (ARC) systems.  United Kingdom: N. p., 2017. 
Web.  doi:10.1016/j.anucene.2016.09.036.

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                    Qvist, Staffan A., Hellesen, Carl, Gradecka, Malwina, Dubberley, Allen E., Fanning, Thomas, & Greenspan, Ehud. Tailoring the response of Autonomous Reactivity Control (ARC) systems.  United Kingdom.  https://doi.org/10.1016/j.anucene.2016.09.036

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                    Qvist, Staffan A., Hellesen, Carl, Gradecka, Malwina, Dubberley, Allen E., Fanning, Thomas, and Greenspan, Ehud. Sun .  
"Tailoring the response of Autonomous Reactivity Control (ARC) systems".  United Kingdom.  https://doi.org/10.1016/j.anucene.2016.09.036.

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@article{osti_1397043,

  title        = {Tailoring the response of Autonomous Reactivity Control (ARC) systems},

  author       = {Qvist, Staffan A. and Hellesen, Carl and Gradecka, Malwina and Dubberley, Allen E. and Fanning, Thomas and Greenspan, Ehud},

  abstractNote = {},

  doi          = {10.1016/j.anucene.2016.09.036},

  journal      = {Annals of Nuclear Energy},

  number       = C,

  volume       = 99,

  place        = {United Kingdom},

  year         = {Sun Jan 01 00:00:00 EST 2017},

  month        = {Sun Jan 01 00:00:00 EST 2017}

}

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Works referenced in this record:

An Autonomous Reactivity Control system for improved fast reactor safety
journal, November 2014

Qvist, Staffan; Greenspan, Ehud
Progress in Nuclear Energy, Vol. 77
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Autonomous Reactivity Control (ARC) — Principles, geometry and design process
journal, October 2016

Qvist, Staffan A.; Hellesen, Carl; Thiele, Roman
Nuclear Engineering and Design, Vol. 307
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Benchmark and demonstration of the CHD code for transient analysis of fast reactor systems
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The ADOPT code for automated fast reactor core design
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Qvist, Staffan; Greenspan, Ehud
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Title: Tailoring the response of Autonomous Reactivity Control (ARC) systems

Citation Formats

An Autonomous Reactivity Control system for improved fast reactor safety journal, November 2014

Autonomous Reactivity Control (ARC) — Principles, geometry and design process journal, October 2016

Influence of a positive sodium void coefficient of reactivity on the consequences of transient overpower and loss-of-flow accidents in a medium-sized fast reactor journal, July 1992

Optimizing the Design of Small Fast Spectrum Battery-Type Nuclear Reactors journal, July 2014

Performance of Metal and Oxide Fuel Cores during Accidents in Large Liquid-Metal-Cooled Reactors journal, February 1992

Trends Versus Reactor Size of Passive Reactivity Shutdown and Control Performance journal, October 1989

Stability analysis of a liquid-metal reactor and its primary heat transport system journal, November 1994

Inherent Shutdown Capabilities of Metal-Fueled Liquid-Metal-Cooled Reactors during Unscrammed Loss-of-Flow and Loss-of-Heat-Sink Incidents journal, May 1988

The Serpent Monte Carlo code: Status, development and applications in 2013 journal, August 2015

Benchmark and demonstration of the CHD code for transient analysis of fast reactor systems journal, November 2017

The ADOPT code for automated fast reactor core design journal, September 2014

Core design studies for a 1000MWth Advanced Burner Reactor journal, April 2009

Code assessment and modelling for Design Basis Accident analysis of the European Sodium Fast Reactor design. Part II: Optimised core and representative transients analysis journal, October 2014

ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology journal, December 2006

Development of a transient thermal-hydraulic code for analysis of China Demonstration Fast Reactor journal, May 2013

An Autonomous Reactivity Control system for improved fast reactor safety
journal, November 2014

Autonomous Reactivity Control (ARC) — Principles, geometry and design process
journal, October 2016

Influence of a positive sodium void coefficient of reactivity on the consequences of transient overpower and loss-of-flow accidents in a medium-sized fast reactor
journal, July 1992

Optimizing the Design of Small Fast Spectrum Battery-Type Nuclear Reactors
journal, July 2014

Performance of Metal and Oxide Fuel Cores during Accidents in Large Liquid-Metal-Cooled Reactors
journal, February 1992

Trends Versus Reactor Size of Passive Reactivity Shutdown and Control Performance
journal, October 1989

Stability analysis of a liquid-metal reactor and its primary heat transport system
journal, November 1994

Inherent Shutdown Capabilities of Metal-Fueled Liquid-Metal-Cooled Reactors during Unscrammed Loss-of-Flow and Loss-of-Heat-Sink Incidents
journal, May 1988

The Serpent Monte Carlo code: Status, development and applications in 2013
journal, August 2015

Benchmark and demonstration of the CHD code for transient analysis of fast reactor systems
journal, November 2017

The ADOPT code for automated fast reactor core design
journal, September 2014

Core design studies for a 1000MWth Advanced Burner Reactor
journal, April 2009

Code assessment and modelling for Design Basis Accident analysis of the European Sodium Fast Reactor design. Part II: Optimised core and representative transients analysis
journal, October 2014

ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology
journal, December 2006

Development of a transient thermal-hydraulic code for analysis of China Demonstration Fast Reactor
journal, May 2013