Physics basis for the advanced tokamak fusion power plant, ARIES-AT
The advanced tokamak is considered as the basis for a fusion power plant. The ARIES-AT design has an aspect ratio of A ≡ R / a = 4.0 , an elongation and triangularity of κ = 2.20 , δ = 0.90 (evaluated at the separatrix surface), a toroidal beta of β = 9.1 % (normalized to the vacuum toroidal field a...
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| Veröffentlicht in: | Fusion engineering and design 2006, Vol.80 (1), p.25-62 |
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| creator | Jardin, S.C. Kessel, C.E. Mau, T.K. Miller, R.L. Najmabadi, F. Chan, V.S. Chu, M.S. LaHaye, R. Lao, L.L. Petrie, T.W. Politzer, P. St.John, H.E. Snyder, P. Staebler, G.M. Turnbull, A.D. West, W.P. |
| description | The advanced tokamak is considered as the basis for a fusion power plant. The ARIES-AT design has an aspect ratio of
A
≡
R
/
a
=
4.0
, an elongation and triangularity of
κ
=
2.20
,
δ
=
0.90
(evaluated at the separatrix surface), a toroidal beta of
β
=
9.1
%
(normalized to the vacuum toroidal field at the plasma center), which corresponds to a normalized beta of
β
N
≡
100
×
β
/
(
I
P
(
M
A
)
/
a
(
m
)
B
(
T
)
)
=
5.4
. These beta values are chosen to be 10% below the ideal MHD stability limit. The bootstrap-current fraction is
f
BS
≡
I
BS
/
I
P
=
0.91
. This leads to a design with total plasma current
I
P
=
12.8
MA, and toroidal field of 11.1 T (at the coil edge) and 5.8 T (at the plasma center). The major and minor radii are 5.2 and 1.3 m. The effects of H-mode edge gradients and the stability of this configuration to non-ideal modes is analyzed. The current drive system consists of ICRF/FW for on-axis current drive and a Lower Hybrid system for off-axis. Transport projections are presented using the drift-wave based GLF23 model. The approach to power and particle exhaust using both plasma core and scrape-off-layer radiation is presented. |
| doi_str_mv | 10.1016/j.fusengdes.2005.06.352 |
| format | Article |
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A
≡
R
/
a
=
4.0
, an elongation and triangularity of
κ
=
2.20
,
δ
=
0.90
(evaluated at the separatrix surface), a toroidal beta of
β
=
9.1
%
(normalized to the vacuum toroidal field at the plasma center), which corresponds to a normalized beta of
β
N
≡
100
×
β
/
(
I
P
(
M
A
)
/
a
(
m
)
B
(
T
)
)
=
5.4
. These beta values are chosen to be 10% below the ideal MHD stability limit. The bootstrap-current fraction is
f
BS
≡
I
BS
/
I
P
=
0.91
. This leads to a design with total plasma current
I
P
=
12.8
MA, and toroidal field of 11.1 T (at the coil edge) and 5.8 T (at the plasma center). The major and minor radii are 5.2 and 1.3 m. The effects of H-mode edge gradients and the stability of this configuration to non-ideal modes is analyzed. The current drive system consists of ICRF/FW for on-axis current drive and a Lower Hybrid system for off-axis. Transport projections are presented using the drift-wave based GLF23 model. The approach to power and particle exhaust using both plasma core and scrape-off-layer radiation is presented.</description><identifier>ISSN: 0920-3796</identifier><identifier>EISSN: 1873-7196</identifier><identifier>DOI: 10.1016/j.fusengdes.2005.06.352</identifier><language>eng</language><publisher>Elsevier B.V</publisher><subject>Advanced tokamak ; Fusion power plant ; Physics basis ; Reactor studies</subject><ispartof>Fusion engineering and design, 2006, Vol.80 (1), p.25-62</ispartof><rights>2005 Elsevier B.V.</rights><lds50>peer_reviewed</lds50><oa>free_for_read</oa><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c395t-5354a326fb7be87a636754e14e3afdf7befba126a8ee70719e196695395864d13</citedby><cites>FETCH-LOGICAL-c395t-5354a326fb7be87a636754e14e3afdf7befba126a8ee70719e196695395864d13</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://www.sciencedirect.com/science/article/pii/S0920379605004175$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>314,776,780,3537,4010,27900,27901,27902,65306</link.rule.ids></links><search><creatorcontrib>Jardin, S.C.</creatorcontrib><creatorcontrib>Kessel, C.E.</creatorcontrib><creatorcontrib>Mau, T.K.</creatorcontrib><creatorcontrib>Miller, R.L.</creatorcontrib><creatorcontrib>Najmabadi, F.</creatorcontrib><creatorcontrib>Chan, V.S.</creatorcontrib><creatorcontrib>Chu, M.S.</creatorcontrib><creatorcontrib>LaHaye, R.</creatorcontrib><creatorcontrib>Lao, L.L.</creatorcontrib><creatorcontrib>Petrie, T.W.</creatorcontrib><creatorcontrib>Politzer, P.</creatorcontrib><creatorcontrib>St.John, H.E.</creatorcontrib><creatorcontrib>Snyder, P.</creatorcontrib><creatorcontrib>Staebler, G.M.</creatorcontrib><creatorcontrib>Turnbull, A.D.</creatorcontrib><creatorcontrib>West, W.P.</creatorcontrib><title>Physics basis for the advanced tokamak fusion power plant, ARIES-AT</title><title>Fusion engineering and design</title><description>The advanced tokamak is considered as the basis for a fusion power plant. The ARIES-AT design has an aspect ratio of
A
≡
R
/
a
=
4.0
, an elongation and triangularity of
κ
=
2.20
,
δ
=
0.90
(evaluated at the separatrix surface), a toroidal beta of
β
=
9.1
%
(normalized to the vacuum toroidal field at the plasma center), which corresponds to a normalized beta of
β
N
≡
100
×
β
/
(
I
P
(
M
A
)
/
a
(
m
)
B
(
T
)
)
=
5.4
. These beta values are chosen to be 10% below the ideal MHD stability limit. The bootstrap-current fraction is
f
BS
≡
I
BS
/
I
P
=
0.91
. This leads to a design with total plasma current
I
P
=
12.8
MA, and toroidal field of 11.1 T (at the coil edge) and 5.8 T (at the plasma center). The major and minor radii are 5.2 and 1.3 m. The effects of H-mode edge gradients and the stability of this configuration to non-ideal modes is analyzed. The current drive system consists of ICRF/FW for on-axis current drive and a Lower Hybrid system for off-axis. Transport projections are presented using the drift-wave based GLF23 model. The approach to power and particle exhaust using both plasma core and scrape-off-layer radiation is presented.</description><subject>Advanced tokamak</subject><subject>Fusion power plant</subject><subject>Physics basis</subject><subject>Reactor studies</subject><issn>0920-3796</issn><issn>1873-7196</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2006</creationdate><recordtype>article</recordtype><recordid>eNqFkF9LwzAUxYMoOKefwTz5ZGvSNEn7WMbUwUDR-RzS9sZlf5qadJN9ezMmvgoXLlzOuffcH0K3lKSUUPGwSs0uQPfZQkgzQnhKRMp4doZGtJAskbQU52hEyowkTJbiEl2FsCKEylgjNHldHoJtAq51sAEb5_GwBKzbve4aaPHg1nqr1zjesK7DvfsGj_uN7oZ7XL3Npu9JtbhGF0ZvAtz89jH6eJwuJs_J_OVpNqnmScNKPiSc8VyzTJha1lBILZiQPAeaA9OmNXFoak0zoQsASWJuiNFFyaO5EHlL2Rjdnfb23n3tIAxqa0MDm5gG3C6orMzzQtAiCuVJ2HgXggejem-32h8UJeoITa3UHzR1hKaIUBFadFYnJ8Q_9ha8Co2FIwnroRlU6-y_O34AXjF48Q</recordid><startdate>2006</startdate><enddate>2006</enddate><creator>Jardin, S.C.</creator><creator>Kessel, C.E.</creator><creator>Mau, T.K.</creator><creator>Miller, R.L.</creator><creator>Najmabadi, F.</creator><creator>Chan, V.S.</creator><creator>Chu, M.S.</creator><creator>LaHaye, R.</creator><creator>Lao, L.L.</creator><creator>Petrie, T.W.</creator><creator>Politzer, P.</creator><creator>St.John, H.E.</creator><creator>Snyder, P.</creator><creator>Staebler, G.M.</creator><creator>Turnbull, A.D.</creator><creator>West, W.P.</creator><general>Elsevier B.V</general><scope>AAYXX</scope><scope>CITATION</scope><scope>7SP</scope><scope>7TB</scope><scope>7U5</scope><scope>8FD</scope><scope>FR3</scope><scope>KR7</scope><scope>L7M</scope></search><sort><creationdate>2006</creationdate><title>Physics basis for the advanced tokamak fusion power plant, ARIES-AT</title><author>Jardin, S.C. ; Kessel, C.E. ; Mau, T.K. ; Miller, R.L. ; Najmabadi, F. ; Chan, V.S. ; Chu, M.S. ; LaHaye, R. ; Lao, L.L. ; Petrie, T.W. ; Politzer, P. ; St.John, H.E. ; Snyder, P. ; Staebler, G.M. ; Turnbull, A.D. ; West, W.P.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c395t-5354a326fb7be87a636754e14e3afdf7befba126a8ee70719e196695395864d13</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2006</creationdate><topic>Advanced tokamak</topic><topic>Fusion power plant</topic><topic>Physics basis</topic><topic>Reactor studies</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Jardin, S.C.</creatorcontrib><creatorcontrib>Kessel, C.E.</creatorcontrib><creatorcontrib>Mau, T.K.</creatorcontrib><creatorcontrib>Miller, R.L.</creatorcontrib><creatorcontrib>Najmabadi, F.</creatorcontrib><creatorcontrib>Chan, V.S.</creatorcontrib><creatorcontrib>Chu, M.S.</creatorcontrib><creatorcontrib>LaHaye, R.</creatorcontrib><creatorcontrib>Lao, L.L.</creatorcontrib><creatorcontrib>Petrie, T.W.</creatorcontrib><creatorcontrib>Politzer, P.</creatorcontrib><creatorcontrib>St.John, H.E.</creatorcontrib><creatorcontrib>Snyder, P.</creatorcontrib><creatorcontrib>Staebler, G.M.</creatorcontrib><creatorcontrib>Turnbull, A.D.</creatorcontrib><creatorcontrib>West, W.P.</creatorcontrib><collection>CrossRef</collection><collection>Electronics & Communications Abstracts</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Solid State and Superconductivity Abstracts</collection><collection>Technology Research Database</collection><collection>Engineering Research Database</collection><collection>Civil Engineering Abstracts</collection><collection>Advanced Technologies Database with Aerospace</collection><jtitle>Fusion engineering and design</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Jardin, S.C.</au><au>Kessel, C.E.</au><au>Mau, T.K.</au><au>Miller, R.L.</au><au>Najmabadi, F.</au><au>Chan, V.S.</au><au>Chu, M.S.</au><au>LaHaye, R.</au><au>Lao, L.L.</au><au>Petrie, T.W.</au><au>Politzer, P.</au><au>St.John, H.E.</au><au>Snyder, P.</au><au>Staebler, G.M.</au><au>Turnbull, A.D.</au><au>West, W.P.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Physics basis for the advanced tokamak fusion power plant, ARIES-AT</atitle><jtitle>Fusion engineering and design</jtitle><date>2006</date><risdate>2006</risdate><volume>80</volume><issue>1</issue><spage>25</spage><epage>62</epage><pages>25-62</pages><issn>0920-3796</issn><eissn>1873-7196</eissn><abstract>The advanced tokamak is considered as the basis for a fusion power plant. The ARIES-AT design has an aspect ratio of
A
≡
R
/
a
=
4.0
, an elongation and triangularity of
κ
=
2.20
,
δ
=
0.90
(evaluated at the separatrix surface), a toroidal beta of
β
=
9.1
%
(normalized to the vacuum toroidal field at the plasma center), which corresponds to a normalized beta of
β
N
≡
100
×
β
/
(
I
P
(
M
A
)
/
a
(
m
)
B
(
T
)
)
=
5.4
. These beta values are chosen to be 10% below the ideal MHD stability limit. The bootstrap-current fraction is
f
BS
≡
I
BS
/
I
P
=
0.91
. This leads to a design with total plasma current
I
P
=
12.8
MA, and toroidal field of 11.1 T (at the coil edge) and 5.8 T (at the plasma center). The major and minor radii are 5.2 and 1.3 m. The effects of H-mode edge gradients and the stability of this configuration to non-ideal modes is analyzed. The current drive system consists of ICRF/FW for on-axis current drive and a Lower Hybrid system for off-axis. Transport projections are presented using the drift-wave based GLF23 model. The approach to power and particle exhaust using both plasma core and scrape-off-layer radiation is presented.</abstract><pub>Elsevier B.V</pub><doi>10.1016/j.fusengdes.2005.06.352</doi><tpages>38</tpages><oa>free_for_read</oa></addata></record> |
| fulltext | fulltext |
| identifier | ISSN: 0920-3796 |
| ispartof | Fusion engineering and design, 2006, Vol.80 (1), p.25-62 |
| issn | 0920-3796 1873-7196 |
| language | eng |
| recordid | cdi_proquest_miscellaneous_29448618 |
| source | Elsevier ScienceDirect Journals |
| subjects | Advanced tokamak Fusion power plant Physics basis Reactor studies |
| title | Physics basis for the advanced tokamak fusion power plant, ARIES-AT |
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