The use of water in a fusion power core

Tillack, M. S.; Humrickhouse, P. W.; Malang, S.; Rowcliffe, A. F.

doi:10.1016/j.fusengdes.2014.12.013

Title: The use of water in a fusion power core

Abstract

Water has both advantages and disadvantages as a coolant in conceptual designs of future fusion power plants. In the United States, water has not been chosen as a fusion power core coolant for decades. Researchers in other countries continue to adopt water in their designs, in some cases as the leading or sole candidate. In this article, we summarize the technical challenges resulting from the choice of water coolant and the differences in approach and assumptions that lead to different design decisions amongst researchers in this field.

Authors:

Tillack, M. S. ^[1]; Humrickhouse, P. W. ^[2]; Malang, S. ^[3]; Rowcliffe, A. F. ^[4]

Univ. of California, San Diego, CA (United States)
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Fusion Nuclear Technology Consulting, Linkenheim (Germany)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

Publication Date:: Sun Feb 01 00:00:00 EST 2015

Research Org.:: Idaho National Lab. (INL), Idaho Falls, ID (United States)

Sponsoring Org.:: USDOE Office of Science (SC), Fusion Energy Sciences (FES)

OSTI Identifier:: 1177633

Alternate Identifier(s):: OSTI ID: 1249907

Report Number(s):: INL/JOU-15-34847
Journal ID: ISSN 0920-3796; TRN: US1500074

Grant/Contract Number:: AC07-05ID14517; FG02-04ER54757

Resource Type:: Accepted Manuscript

Journal Name:: Fusion Engineering and Design

Additional Journal Information:: Journal Volume: 91; Journal ID: ISSN 0920-3796

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; Thermonuclear Reactors; Reactor Cores; DESIGN; COOLANTS; WATER; FUSION POWER CORE; BLANKETS; DIVERTORS; POWER PLANTS

Citation Formats


                    Tillack, M. S., Humrickhouse, P. W., Malang, S., and Rowcliffe, A. F. The use of water in a fusion power core.  United States: N. p., 2015. 
Web.  doi:10.1016/j.fusengdes.2014.12.013.

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                    Tillack, M. S., Humrickhouse, P. W., Malang, S., & Rowcliffe, A. F. The use of water in a fusion power core.  United States.  https://doi.org/10.1016/j.fusengdes.2014.12.013

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                    Tillack, M. S., Humrickhouse, P. W., Malang, S., and Rowcliffe, A. F. Sun .  
"The use of water in a fusion power core".  United States.  https://doi.org/10.1016/j.fusengdes.2014.12.013.  https://www.osti.gov/servlets/purl/1177633.

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@article{osti_1177633,

  title        = {The use of water in a fusion power core},

  author       = {Tillack, M. S. and Humrickhouse, P. W. and Malang, S. and Rowcliffe, A. F.},

  abstractNote = {Water has both advantages and disadvantages as a coolant in conceptual designs of future fusion power plants. In the United States, water has not been chosen as a fusion power core coolant for decades. Researchers in other countries continue to adopt water in their designs, in some cases as the leading or sole candidate. In this article, we summarize the technical challenges resulting from the choice of water coolant and the differences in approach and assumptions that lead to different design decisions amongst researchers in this field.},

  doi          = {10.1016/j.fusengdes.2014.12.013},

  journal      = {Fusion Engineering and Design},

  number       = ,

  volume       = 91,

  place        = {United States},

  year         = {Sun Feb 01 00:00:00 EST 2015},

  month        = {Sun Feb 01 00:00:00 EST 2015}

}

Copy to clipboard

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https://doi.org/10.1016/j.fusengdes.2014.12.013

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Works referencing / citing this record:

Blanket/first wall challenges and required R&D on the pathway to DEMO
journal, November 2015

Abdou, Mohamed; Morley, Neil B.; Smolentsev, Sergey
Fusion Engineering and Design, Vol. 100
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text, January 2019

Fulton, George; Lunev, Artem
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Title: The use of water in a fusion power core

Abstract

Citation Formats

DEMO design activities in the broader approach under Japan/EU collaboration journal, October 2014

Overview of EU DEMO design and R&D activities journal, October 2014

The ARIES-CS Compact Stellarator Fusion Power Plant journal, October 2008

Spherical torus concept as power plants—the ARIES-ST study journal, February 2003

The ARIES-AT advanced tokamak, Advanced technology fusion power plant journal, January 2006

The ARIES Advanced and Conservative Tokamak Power Plant Study journal, January 2015

Overview of the ITER TBM Program journal, August 2012

Overview and status of ITER internal components journal, October 2014

Power plant conceptual studies in Europe journal, October 2007

Development of the water cooled lithium lead blanket for DEMO journal, October 2014

Development of a helium-cooled divertor: Material choice and technological studies journal, August 2007

Design of a water cooled monoblock divertor for DEMO using Eurofer as structural material journal, October 2014

Blanket and divertor design for the Steady State Tokamak Reactor (SSTR) journal, December 1991

Compact DEMO, SlimCS: design progress and issues journal, July 2009

Helical reactor design FFHR-d1 and c1 for steady-state DEMO journal, October 2014

ITER safety and licensing update journal, August 2012

Chemical reactivity and mobilization of beryllium exposed to steam journal, November 1997

Steam-chemical reactivity for irradiated beryllium journal, October 1998

Steam chemical reactivity of Be pebbles and Be powder journal, December 2000

On the mechanisms associated with the chemical reactivity of Be in steam journal, December 2000

Oxidation of beryllium—a scanning Auger investigation journal, August 2005

A preliminary assessment of beryllium dust oxidation during a wet bypass accident in a fusion reactor journal, June 2009

The safety implications of tokamak dust size and surface area journal, September 1998

Stability of titanium beryllide under water vapor journal, August 2004

Surface reaction of titanium beryllide with water vapor journal, February 2006

Structural and Oxidation Studies of Titanium Beryllides journal, September 2007

Lithium alloy chemical reactivity with reactor materials: current state of knowledge journal, April 1991

Liquid metal chemical reaction safety in fusion facilities journal, January 1987

Development of the EU water-cooled Pb-17Li blanket journal, September 1998

A water cooled lithium–lead blanket without tritium permeation barriers: feasibility and economical analysis journal, November 2001

Demo blanket technology R&D results in EU journal, November 2002

Updated Modeling of Postulated Accident Scenarios in ITER journal, August 2009

Tritium Release from Nuclear Power Plants in Taiwan journal, March 2003

Evaluation of copper alloys for fusion reactor divertor and first wall components journal, October 1996

Irradiation performance of stainless steels for ITER application journal, December 1996

Materials R&D for a timely DEMO: Key findings and recommendations of the EU Roadmap Materials Assessment Group journal, October 2014

Stress corrosion cracking susceptibility of a reduced-activation martensitic steel F82H journal, April 2009

Physics and technology conditions for attaining tritium self-sufficiency for the DT fuel cycle journal, February 2006

The half-life of N16 journal, January 1964

Blanket/first wall challenges and required R&D on the pathway to DEMO journal, November 2015

Probing the correlation between phase evolution and growth kinetics in the oxide layers of tungsten using Raman spectroscopy and EBSD text, January 2019

DEMO design activities in the broader approach under Japan/EU collaboration
journal, October 2014

Overview of EU DEMO design and R&D activities
journal, October 2014

The ARIES-CS Compact Stellarator Fusion Power Plant
journal, October 2008

Spherical torus concept as power plants—the ARIES-ST study
journal, February 2003

The ARIES-AT advanced tokamak, Advanced technology fusion power plant
journal, January 2006

The ARIES Advanced and Conservative Tokamak Power Plant Study
journal, January 2015

Overview of the ITER TBM Program
journal, August 2012

Overview and status of ITER internal components
journal, October 2014

Power plant conceptual studies in Europe
journal, October 2007

Development of the water cooled lithium lead blanket for DEMO
journal, October 2014

Development of a helium-cooled divertor: Material choice and technological studies
journal, August 2007

Design of a water cooled monoblock divertor for DEMO using Eurofer as structural material
journal, October 2014

Blanket and divertor design for the Steady State Tokamak Reactor (SSTR)
journal, December 1991

Compact DEMO, SlimCS: design progress and issues
journal, July 2009

Helical reactor design FFHR-d1 and c1 for steady-state DEMO
journal, October 2014

ITER safety and licensing update
journal, August 2012

Chemical reactivity and mobilization of beryllium exposed to steam
journal, November 1997

Steam-chemical reactivity for irradiated beryllium
journal, October 1998

Steam chemical reactivity of Be pebbles and Be powder
journal, December 2000

On the mechanisms associated with the chemical reactivity of Be in steam
journal, December 2000

Oxidation of beryllium—a scanning Auger investigation
journal, August 2005

A preliminary assessment of beryllium dust oxidation during a wet bypass accident in a fusion reactor
journal, June 2009

The safety implications of tokamak dust size and surface area
journal, September 1998

Stability of titanium beryllide under water vapor
journal, August 2004

Surface reaction of titanium beryllide with water vapor
journal, February 2006

Structural and Oxidation Studies of Titanium Beryllides
journal, September 2007

Lithium alloy chemical reactivity with reactor materials: current state of knowledge
journal, April 1991

Liquid metal chemical reaction safety in fusion facilities
journal, January 1987

Development of the EU water-cooled Pb-17Li blanket
journal, September 1998

A water cooled lithium–lead blanket without tritium permeation barriers: feasibility and economical analysis
journal, November 2001

Demo blanket technology R&D results in EU
journal, November 2002

Updated Modeling of Postulated Accident Scenarios in ITER
journal, August 2009

Tritium Release from Nuclear Power Plants in Taiwan
journal, March 2003

Evaluation of copper alloys for fusion reactor divertor and first wall components
journal, October 1996

Irradiation performance of stainless steels for ITER application
journal, December 1996

Materials R&D for a timely DEMO: Key findings and recommendations of the EU Roadmap Materials Assessment Group
journal, October 2014

Stress corrosion cracking susceptibility of a reduced-activation martensitic steel F82H
journal, April 2009

Physics and technology conditions for attaining tritium self-sufficiency for the DT fuel cycle
journal, February 2006

The half-life of N16
journal, January 1964

Blanket/first wall challenges and required R&D on the pathway to DEMO
journal, November 2015

Probing the correlation between phase evolution and growth kinetics in the oxide layers of tungsten using Raman spectroscopy and EBSD
text, January 2019