Assessment of Scrape-Off Layer and divertor plasma conditions in JT-60SA with tungsten wall and nitrogen injection

The possibility to safely operate tokamaks strongly depends on the capability to protect the divertor targets from excessive power load and erosion. Here, we will present a study of the JT-60SA Scenario 3 with a W wall to identify possible criticality in the transition from C to W wall. The assessme...
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Autor*in:	G. Rubino [verfasserIn] G. Calabrò [verfasserIn] M. Wischmeier [verfasserIn]

Format:	E-Artikel
Sprache:	Englisch

Erschienen:	2021

Schlagwörter:	SOLPS-ITER JT-60SA Scenario 3 High radiating scenario W wall Nitrogen

Übergeordnetes Werk:	In: Nuclear Materials and Energy - Elsevier, 2016, 26(2021), Seite 100895-
Übergeordnetes Werk:	volume:26 ; year:2021 ; pages:100895-

Links:	Link aufrufen Link aufrufen Link aufrufen Journal toc

DOI / URN:	10.1016/j.nme.2020.100895

Katalog-ID:	DOAJ01985613X

Internformat


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520			\|a The possibility to safely operate tokamaks strongly depends on the capability to protect the divertor targets from excessive power load and erosion. Here, we will present a study of the JT-60SA Scenario 3 with a W wall to identify possible criticality in the transition from C to W wall. The assessment of the SOL and divertor plasma conditions is made with the SOLPS-ITER code suite. The simulations results show that safe operations are mainly limited by Te. In addition, the analysis of the balance equations highlights the importance of the impurity injection. It represents the main mechanism to drive the decrease in power load onto the outer target (POT) by impurity radiation and to achieve detachment via the collisions between D+ions and D2molecules.
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publishDate	2021
allfields	10.1016/j.nme.2020.100895 doi (DE-627)DOAJ01985613X (DE-599)DOAJ6de01a80e7f54303853392c750218386 DE-627 ger DE-627 rakwb eng TK9001-9401 G. Rubino verfasserin aut Assessment of Scrape-Off Layer and divertor plasma conditions in JT-60SA with tungsten wall and nitrogen injection 2021 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier The possibility to safely operate tokamaks strongly depends on the capability to protect the divertor targets from excessive power load and erosion. Here, we will present a study of the JT-60SA Scenario 3 with a W wall to identify possible criticality in the transition from C to W wall. The assessment of the SOL and divertor plasma conditions is made with the SOLPS-ITER code suite. The simulations results show that safe operations are mainly limited by Te. In addition, the analysis of the balance equations highlights the importance of the impurity injection. It represents the main mechanism to drive the decrease in power load onto the outer target (POT) by impurity radiation and to achieve detachment via the collisions between D+ions and D2molecules. SOLPS-ITER JT-60SA Scenario 3 High radiating scenario W wall Nitrogen Nuclear engineering. Atomic power G. Calabrò verfasserin aut M. Wischmeier verfasserin aut In Nuclear Materials and Energy Elsevier, 2016 26(2021), Seite 100895- (DE-627)817363181 (DE-600)2808888-8 23521791 nnns volume:26 year:2021 pages:100895- https://doi.org/10.1016/j.nme.2020.100895 kostenfrei https://doaj.org/article/6de01a80e7f54303853392c750218386 kostenfrei http://www.sciencedirect.com/science/article/pii/S2352179120301563 kostenfrei https://doaj.org/toc/2352-1791 Journal toc kostenfrei GBV_USEFLAG_A SYSFLAG_A GBV_DOAJ GBV_ILN_11 GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_39 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_95 GBV_ILN_105 GBV_ILN_110 GBV_ILN_151 GBV_ILN_161 GBV_ILN_170 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2007 GBV_ILN_2008 GBV_ILN_2009 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2026 GBV_ILN_2027 GBV_ILN_2034 GBV_ILN_2038 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2088 GBV_ILN_2106 GBV_ILN_2110 GBV_ILN_2112 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2470 GBV_ILN_2507 GBV_ILN_4012 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4242 GBV_ILN_4249 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4338 GBV_ILN_4367 GBV_ILN_4393 GBV_ILN_4700 AR 26 2021 100895-
spelling	10.1016/j.nme.2020.100895 doi (DE-627)DOAJ01985613X (DE-599)DOAJ6de01a80e7f54303853392c750218386 DE-627 ger DE-627 rakwb eng TK9001-9401 G. Rubino verfasserin aut Assessment of Scrape-Off Layer and divertor plasma conditions in JT-60SA with tungsten wall and nitrogen injection 2021 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier The possibility to safely operate tokamaks strongly depends on the capability to protect the divertor targets from excessive power load and erosion. Here, we will present a study of the JT-60SA Scenario 3 with a W wall to identify possible criticality in the transition from C to W wall. The assessment of the SOL and divertor plasma conditions is made with the SOLPS-ITER code suite. The simulations results show that safe operations are mainly limited by Te. In addition, the analysis of the balance equations highlights the importance of the impurity injection. It represents the main mechanism to drive the decrease in power load onto the outer target (POT) by impurity radiation and to achieve detachment via the collisions between D+ions and D2molecules. SOLPS-ITER JT-60SA Scenario 3 High radiating scenario W wall Nitrogen Nuclear engineering. Atomic power G. Calabrò verfasserin aut M. Wischmeier verfasserin aut In Nuclear Materials and Energy Elsevier, 2016 26(2021), Seite 100895- (DE-627)817363181 (DE-600)2808888-8 23521791 nnns volume:26 year:2021 pages:100895- https://doi.org/10.1016/j.nme.2020.100895 kostenfrei https://doaj.org/article/6de01a80e7f54303853392c750218386 kostenfrei http://www.sciencedirect.com/science/article/pii/S2352179120301563 kostenfrei https://doaj.org/toc/2352-1791 Journal toc kostenfrei GBV_USEFLAG_A SYSFLAG_A GBV_DOAJ GBV_ILN_11 GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_39 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_95 GBV_ILN_105 GBV_ILN_110 GBV_ILN_151 GBV_ILN_161 GBV_ILN_170 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2007 GBV_ILN_2008 GBV_ILN_2009 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2026 GBV_ILN_2027 GBV_ILN_2034 GBV_ILN_2038 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2088 GBV_ILN_2106 GBV_ILN_2110 GBV_ILN_2112 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2470 GBV_ILN_2507 GBV_ILN_4012 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4242 GBV_ILN_4249 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4338 GBV_ILN_4367 GBV_ILN_4393 GBV_ILN_4700 AR 26 2021 100895-
allfields_unstemmed	10.1016/j.nme.2020.100895 doi (DE-627)DOAJ01985613X (DE-599)DOAJ6de01a80e7f54303853392c750218386 DE-627 ger DE-627 rakwb eng TK9001-9401 G. Rubino verfasserin aut Assessment of Scrape-Off Layer and divertor plasma conditions in JT-60SA with tungsten wall and nitrogen injection 2021 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier The possibility to safely operate tokamaks strongly depends on the capability to protect the divertor targets from excessive power load and erosion. Here, we will present a study of the JT-60SA Scenario 3 with a W wall to identify possible criticality in the transition from C to W wall. The assessment of the SOL and divertor plasma conditions is made with the SOLPS-ITER code suite. The simulations results show that safe operations are mainly limited by Te. In addition, the analysis of the balance equations highlights the importance of the impurity injection. It represents the main mechanism to drive the decrease in power load onto the outer target (POT) by impurity radiation and to achieve detachment via the collisions between D+ions and D2molecules. SOLPS-ITER JT-60SA Scenario 3 High radiating scenario W wall Nitrogen Nuclear engineering. Atomic power G. Calabrò verfasserin aut M. Wischmeier verfasserin aut In Nuclear Materials and Energy Elsevier, 2016 26(2021), Seite 100895- (DE-627)817363181 (DE-600)2808888-8 23521791 nnns volume:26 year:2021 pages:100895- https://doi.org/10.1016/j.nme.2020.100895 kostenfrei https://doaj.org/article/6de01a80e7f54303853392c750218386 kostenfrei http://www.sciencedirect.com/science/article/pii/S2352179120301563 kostenfrei https://doaj.org/toc/2352-1791 Journal toc kostenfrei GBV_USEFLAG_A SYSFLAG_A GBV_DOAJ GBV_ILN_11 GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_39 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_95 GBV_ILN_105 GBV_ILN_110 GBV_ILN_151 GBV_ILN_161 GBV_ILN_170 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2007 GBV_ILN_2008 GBV_ILN_2009 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2026 GBV_ILN_2027 GBV_ILN_2034 GBV_ILN_2038 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2088 GBV_ILN_2106 GBV_ILN_2110 GBV_ILN_2112 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2470 GBV_ILN_2507 GBV_ILN_4012 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4242 GBV_ILN_4249 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4338 GBV_ILN_4367 GBV_ILN_4393 GBV_ILN_4700 AR 26 2021 100895-
allfieldsGer	10.1016/j.nme.2020.100895 doi (DE-627)DOAJ01985613X (DE-599)DOAJ6de01a80e7f54303853392c750218386 DE-627 ger DE-627 rakwb eng TK9001-9401 G. Rubino verfasserin aut Assessment of Scrape-Off Layer and divertor plasma conditions in JT-60SA with tungsten wall and nitrogen injection 2021 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier The possibility to safely operate tokamaks strongly depends on the capability to protect the divertor targets from excessive power load and erosion. Here, we will present a study of the JT-60SA Scenario 3 with a W wall to identify possible criticality in the transition from C to W wall. The assessment of the SOL and divertor plasma conditions is made with the SOLPS-ITER code suite. The simulations results show that safe operations are mainly limited by Te. In addition, the analysis of the balance equations highlights the importance of the impurity injection. It represents the main mechanism to drive the decrease in power load onto the outer target (POT) by impurity radiation and to achieve detachment via the collisions between D+ions and D2molecules. SOLPS-ITER JT-60SA Scenario 3 High radiating scenario W wall Nitrogen Nuclear engineering. Atomic power G. Calabrò verfasserin aut M. Wischmeier verfasserin aut In Nuclear Materials and Energy Elsevier, 2016 26(2021), Seite 100895- (DE-627)817363181 (DE-600)2808888-8 23521791 nnns volume:26 year:2021 pages:100895- https://doi.org/10.1016/j.nme.2020.100895 kostenfrei https://doaj.org/article/6de01a80e7f54303853392c750218386 kostenfrei http://www.sciencedirect.com/science/article/pii/S2352179120301563 kostenfrei https://doaj.org/toc/2352-1791 Journal toc kostenfrei GBV_USEFLAG_A SYSFLAG_A GBV_DOAJ GBV_ILN_11 GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_39 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_95 GBV_ILN_105 GBV_ILN_110 GBV_ILN_151 GBV_ILN_161 GBV_ILN_170 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2007 GBV_ILN_2008 GBV_ILN_2009 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2026 GBV_ILN_2027 GBV_ILN_2034 GBV_ILN_2038 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2088 GBV_ILN_2106 GBV_ILN_2110 GBV_ILN_2112 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2470 GBV_ILN_2507 GBV_ILN_4012 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4242 GBV_ILN_4249 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4338 GBV_ILN_4367 GBV_ILN_4393 GBV_ILN_4700 AR 26 2021 100895-
allfieldsSound	10.1016/j.nme.2020.100895 doi (DE-627)DOAJ01985613X (DE-599)DOAJ6de01a80e7f54303853392c750218386 DE-627 ger DE-627 rakwb eng TK9001-9401 G. Rubino verfasserin aut Assessment of Scrape-Off Layer and divertor plasma conditions in JT-60SA with tungsten wall and nitrogen injection 2021 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier The possibility to safely operate tokamaks strongly depends on the capability to protect the divertor targets from excessive power load and erosion. Here, we will present a study of the JT-60SA Scenario 3 with a W wall to identify possible criticality in the transition from C to W wall. The assessment of the SOL and divertor plasma conditions is made with the SOLPS-ITER code suite. The simulations results show that safe operations are mainly limited by Te. In addition, the analysis of the balance equations highlights the importance of the impurity injection. It represents the main mechanism to drive the decrease in power load onto the outer target (POT) by impurity radiation and to achieve detachment via the collisions between D+ions and D2molecules. SOLPS-ITER JT-60SA Scenario 3 High radiating scenario W wall Nitrogen Nuclear engineering. Atomic power G. Calabrò verfasserin aut M. Wischmeier verfasserin aut In Nuclear Materials and Energy Elsevier, 2016 26(2021), Seite 100895- (DE-627)817363181 (DE-600)2808888-8 23521791 nnns volume:26 year:2021 pages:100895- https://doi.org/10.1016/j.nme.2020.100895 kostenfrei https://doaj.org/article/6de01a80e7f54303853392c750218386 kostenfrei http://www.sciencedirect.com/science/article/pii/S2352179120301563 kostenfrei https://doaj.org/toc/2352-1791 Journal toc kostenfrei GBV_USEFLAG_A SYSFLAG_A GBV_DOAJ GBV_ILN_11 GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_39 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_95 GBV_ILN_105 GBV_ILN_110 GBV_ILN_151 GBV_ILN_161 GBV_ILN_170 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2007 GBV_ILN_2008 GBV_ILN_2009 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2026 GBV_ILN_2027 GBV_ILN_2034 GBV_ILN_2038 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2088 GBV_ILN_2106 GBV_ILN_2110 GBV_ILN_2112 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2470 GBV_ILN_2507 GBV_ILN_4012 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4242 GBV_ILN_4249 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4338 GBV_ILN_4367 GBV_ILN_4393 GBV_ILN_4700 AR 26 2021 100895-
language	English
source	In Nuclear Materials and Energy 26(2021), Seite 100895- volume:26 year:2021 pages:100895-
sourceStr	In Nuclear Materials and Energy 26(2021), Seite 100895- volume:26 year:2021 pages:100895-
format_phy_str_mv	Article
institution	findex.gbv.de
topic_facet	SOLPS-ITER JT-60SA Scenario 3 High radiating scenario W wall Nitrogen Nuclear engineering. Atomic power
isfreeaccess_bool	true
container_title	Nuclear Materials and Energy
authorswithroles_txt_mv	G. Rubino @@aut@@ G. Calabrò @@aut@@ M. Wischmeier @@aut@@
publishDateDaySort_date	2021-01-01T00:00:00Z
hierarchy_top_id	817363181
id	DOAJ01985613X
language_de	englisch
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callnumber-first	T - Technology
author	G. Rubino
spellingShingle	G. Rubino misc TK9001-9401 misc SOLPS-ITER misc JT-60SA Scenario 3 misc High radiating scenario misc W wall misc Nitrogen misc Nuclear engineering. Atomic power Assessment of Scrape-Off Layer and divertor plasma conditions in JT-60SA with tungsten wall and nitrogen injection
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topic_title	TK9001-9401 Assessment of Scrape-Off Layer and divertor plasma conditions in JT-60SA with tungsten wall and nitrogen injection SOLPS-ITER JT-60SA Scenario 3 High radiating scenario W wall Nitrogen
topic	misc TK9001-9401 misc SOLPS-ITER misc JT-60SA Scenario 3 misc High radiating scenario misc W wall misc Nitrogen misc Nuclear engineering. Atomic power
topic_unstemmed	misc TK9001-9401 misc SOLPS-ITER misc JT-60SA Scenario 3 misc High radiating scenario misc W wall misc Nitrogen misc Nuclear engineering. Atomic power
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title	Assessment of Scrape-Off Layer and divertor plasma conditions in JT-60SA with tungsten wall and nitrogen injection
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title_full	Assessment of Scrape-Off Layer and divertor plasma conditions in JT-60SA with tungsten wall and nitrogen injection
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author_browse	G. Rubino G. Calabrò M. Wischmeier
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title_sort	assessment of scrape-off layer and divertor plasma conditions in jt-60sa with tungsten wall and nitrogen injection
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title_auth	Assessment of Scrape-Off Layer and divertor plasma conditions in JT-60SA with tungsten wall and nitrogen injection
abstract	The possibility to safely operate tokamaks strongly depends on the capability to protect the divertor targets from excessive power load and erosion. Here, we will present a study of the JT-60SA Scenario 3 with a W wall to identify possible criticality in the transition from C to W wall. The assessment of the SOL and divertor plasma conditions is made with the SOLPS-ITER code suite. The simulations results show that safe operations are mainly limited by Te. In addition, the analysis of the balance equations highlights the importance of the impurity injection. It represents the main mechanism to drive the decrease in power load onto the outer target (POT) by impurity radiation and to achieve detachment via the collisions between D+ions and D2molecules.
abstractGer	The possibility to safely operate tokamaks strongly depends on the capability to protect the divertor targets from excessive power load and erosion. Here, we will present a study of the JT-60SA Scenario 3 with a W wall to identify possible criticality in the transition from C to W wall. The assessment of the SOL and divertor plasma conditions is made with the SOLPS-ITER code suite. The simulations results show that safe operations are mainly limited by Te. In addition, the analysis of the balance equations highlights the importance of the impurity injection. It represents the main mechanism to drive the decrease in power load onto the outer target (POT) by impurity radiation and to achieve detachment via the collisions between D+ions and D2molecules.
abstract_unstemmed	The possibility to safely operate tokamaks strongly depends on the capability to protect the divertor targets from excessive power load and erosion. Here, we will present a study of the JT-60SA Scenario 3 with a W wall to identify possible criticality in the transition from C to W wall. The assessment of the SOL and divertor plasma conditions is made with the SOLPS-ITER code suite. The simulations results show that safe operations are mainly limited by Te. In addition, the analysis of the balance equations highlights the importance of the impurity injection. It represents the main mechanism to drive the decrease in power load onto the outer target (POT) by impurity radiation and to achieve detachment via the collisions between D+ions and D2molecules.
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title_short	Assessment of Scrape-Off Layer and divertor plasma conditions in JT-60SA with tungsten wall and nitrogen injection
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Assessment of Scrape-Off Layer and divertor plasma conditions in JT-60SA with tungsten wall and nitrogen injection

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