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Neutral-beam injection

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96: 1325: 592: 792: 605: 864:). Caesium, deposited at the source walls, is an efficient electron donor; atoms and positive ions scattered at caesiated surface have a relatively high probability of being scattered as negatively charged ions. Operation of caesiated sources is complex and not so reliable. The development of alternative concepts for negative-ion beam sources is mandatory for the use of neutral beam systems in future fusion reactors. 856:. The precursor beam could either be a positive-ion beam or a negative-ion beam: in order to obtain a sufficiently high current, it is produced extracting charges from a plasma discharge. However, few negative hydrogen ions are created in a hydrogen plasma discharge. In order to generate a sufficiently high negative-ion density and obtain a decent negative-ion beam current, 774:
1 MeV. With increasing energy, it is increasingly difficult to obtain fast hydrogen atoms starting from precursor beams composed of positive ions. For that reason, recent and future heating neutral beams will be based on negative-ion beams. In the interaction with background gas, it is much easier to detach the extra electron from a
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field. When these neutral particles are ionized by collision with the plasma particles, they are kept in the plasma by the confining magnetic field and can transfer most of their energy by further collisions with the plasma. By tangential injection in the torus, neutral beams also provide momentum to
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Typically, the background gas density shall be minimised all along the beam path (i.e. within the accelerating electrodes, along the duct connecting to the fusion plasma) to minimise losses except in the neutraliser cell. Therefore, the required target thickness for neutralisation is obtained by
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in keV. Depending on the plasma minor diameter and density, a minimum particle energy can be defined for the neutral beam, in order to deposit a sufficient power on the plasma core rather than to the plasma edge. For a fusion-relevant plasma, the required fast neutral energy gets in the range of
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First, plasma is formed by microwaving gas. Next, the plasma is accelerated across a voltage drop. This heats the ions to fusion conditions. After this the ions are re-neutralizing. Lastly, the neutrals are injected into the
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Because the magnetic field inside the torus is circular, these fast ions are confined to the background plasma. The confined fast ions mentioned above are slowed down by the background plasma, in a similar way to how
181:. To allow power deposition in the center of the burning plasma in larger devices, a higher neutral-beam energy is required. High-energy (>100 keV) systems require the use of negative ion technology (N-NBI). 559:
It is very important that the fast ions are confined within the plasma long enough for them to deposit their energy. Magnetic fluctuations are a big problem for plasma confinement in this type of device (see
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L. R. Grisham, P. Agostinetti, G. Barrera, P. Blatchford, D. Boilson, J. Chareyre, et al., Recent improvements to the ITER neutral beam system design, Fusion Engineering and Design 87 (11), 1805–1815.
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Neutralisation of the precursor ion beam is commonly performed by passing the beam through a gas cell. For a precursor negative-ion beam at fusion-relevant energies, the key collisional processes are:
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Cross-sections at 1 MeV are such that, once created, a fast positive ion cannot be converted into a fast neutral, and this is the cause of the limited achievable efficiency of gas neutralisers.
736: 47:. Neutral-beam injection is a flexible and reliable technique, which has been the main heating system on a large variety of fusion devices. To date, all NBI systems were based on positive precursor 1435: 861: 1695:
is adopted, but this solution is unlikely in future devices due to the limited volume inside the bioshield protecting from energetic neutron flux (for instance, in the case of
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collisions of fast ions with plasma ions and electrons by Coulomb collisions (slow-down and scattering, thermalisation) or charge exchange collisions with background neutrals.
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The fractions of negatively charged, positively charged, and neutral particles exiting the neutraliser gas cells depend on the integrated gas density or target thickness
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injecting gas in a cell with two open ends. A peaked density profile is realised along the cell, when injection occurs at mid-length. For a given gas throughput
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among the largest ever built, with pumping speeds in the range of million liters per second. If there are no space constraints, a large gas cell length
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It is critical to inject neutral material into plasma, because if it is charged, it can start harmful plasma instabilities. Most fusion devices inject
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is being constructed to optimize its performance in view of the ITER future operations. Other ways to heat plasma for nuclear fusion include
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Ikeda, K.; Tsumori, K.; Kisaki, M.; Nakano, H.; Nagaoka, K.; Osakabe, M.; Kamio, S.; Fujiwara, Y.; Haba, Y.; Takeiri, Y. (2018).
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At present, all main fusion experiments use NBIs. Traditional positive-ion-based injectors (P-NBI) are installed for instance in
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slows down a baseball. The energy transfer from the fast ions to the plasma increases the overall plasma temperature.
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This is done dropping the positively charged ions towards negative plates. As the ions fall, the electric field does
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Existing and future negative-ion-based neutral beam systems (N-NBI) are listed in the following table:
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Maximum neutralisation efficiency of a fast D ion beam in a gas cell, as a function of the ion energy
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A neutral beam is obtained by neutralisation of a precursor ion beam, commonly accelerated in large
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sources and accelerators with the construction of multi-megawatt negative-ion-based NBI systems at
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the hot plasma by adding in the opposite charge. This gives the fast-moving beam with no charge.
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Very high gas throughput is commonly adopted, and neutral-beam systems have custom
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V. Toigo; D. Boilson; T. Bonicelli; R. Piovan; M. Hanada; et al. (2015).
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indicate the charge state of fast particle before and after collision.
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the plasma and current drive, one essential feature for long pulses of
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charge when it enters, as it passes through the plasma, the atoms are
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Thermonuclear Fusion Test Reactor with neutral beam injector at PPPL
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Simplified scheme of gas-cell neutraliser for neutral-beam injectors
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the N-NBI neutraliser cell is about 15 m long, while in the
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Proceedings of the 17th International Conference on Ion Sources
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The interaction of fast neutrals with the plasma consist of
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Schiesko, L; McNeely, P; Fantz, U; Franzen, P (2011-07-07).
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is a substantial challenge (D, 1 MeV, 40 A) and a
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Underline indicates the fast particles, while subscripts
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drift of newly created fast ions in the magnetic field,
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ionisation by collision with plasma electrons and ions,
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Neutral-beam injectors installed in fusion experiments
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This can be done by microwaving a low-pressure gas.
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(April 2017). 2035: 782:Charge state of the precursor ion beam 1863:Plasma Physics and Controlled Fusion 1703:its length is limited to 3 m). 1235:the gas density along the beam path 818:adding citations to reliable sources 785: 631:adding citations to reliable sources 598: 34:consisting in a beam of high-energy 862:surface-plasma negative-ion sources 13: 924:Max power per installed beam (MW) 94: 14: 2054: 2011: 1208:{\displaystyle \tau =\int n\,dl,} 2028:IPP website about NBI technology 790: 603: 1713:ITER Neutral Beam Test Facility 115:Electrostatic ion acceleration. 81:ion cyclotron resonance heating 1968: 1956: 1905: 1850: 1824:. AIP Conference Proceedings. 1809: 1791: 1734: 1725: 1568:with the geometric parameters 910:Max acceleration voltage (kV) 586: 582:Design of neutral beam systems 189:experiments (* design target) 85:lower hybrid resonance heating 1: 1883:10.1088/0741-3335/53/8/085029 1767:10.1088/0029-5515/55/8/083025 1718: 26:) is one method used to heat 2001:10.1016/0042-207X(87)90015-7 194:Magnetic confinement device 90: 77:electron cyclotron resonance 7: 1706: 1071: (reionization, with 547:Coupling with fusion plasma 104:This is typically done by: 10: 2059: 854:electrostatic accelerators 2023:Auxiliary heating in ITER 1135:negligible at 1 MeV) 1112: (charge exchange, 1094:=3.79×10 m at 1 MeV) 1049:=7.22×10 m at 1 MeV) 1004:=1.13×10 m at 1 MeV) 1939:10.1088/1367-2630/aa64bd 871:N-NBI (* design target) 769:in amu, particle energy 754:{\displaystyle \lambda } 678:{\displaystyle \lambda } 1648:gas molecule mass, and 1160:{\displaystyle \sigma } 1125:{\displaystyle \sigma } 1084:{\displaystyle \sigma } 1039:{\displaystyle \sigma } 994:{\displaystyle \sigma } 954:Ion beam neutralisation 761:in m, particle density 1918:New Journal of Physics 1689: 1662: 1642: 1622: 1602: 1582: 1559: 1464:can be calculated as 1454: 1431: 1367: 1347: 1329: 1315: 1249: 1229: 1209: 1161: 1126: 1085: 1040: 995: 755: 732: 679: 665:The adsorption length 596: 101: 59:(H, 180 keV) and 20:Neutral-beam injection 1963:IAEA Aladdin database 1690: 1663: 1643: 1628:indicated in figure, 1623: 1603: 1583: 1560: 1462:molecular-flow regime 1455: 1432: 1368: 1348: 1327: 1316: 1250: 1230: 1210: 1162: 1147:of the cross-section 1127: 1086: 1041: 996: 765:in 10 m, atomic mass 756: 733: 680: 594: 98: 1679: 1652: 1632: 1612: 1592: 1572: 1471: 1444: 1380: 1357: 1337: 1259: 1239: 1219: 1180: 1151: 1116: 1075: 1030: 985: 814:improve this section 745: 692: 669: 627:improve this section 528: In development 40:magnetic confinement 1993:1987Vacuu..37..309D 1975:G. Duesing (1987). 1930:2017NJPh...19d5003S 1875:2011PPCF...53h5029S 1834:2018AIPC.2011f0002I 1759:2015NucFu..55h3025T 938:Pulse duration (s) 896:Precursor ion beam 872: 190: 38:that can enter the 1685: 1658: 1638: 1618: 1598: 1578: 1555: 1450: 1427: 1363: 1343: 1330: 1311: 1245: 1225: 1205: 1157: 1122: 1081: 1036: 991: 870: 751: 728: 675: 597: 184: 102: 1843:10.1063/1.5053331 1688:{\displaystyle L} 1668:gas temperature. 1661:{\displaystyle T} 1641:{\displaystyle m} 1621:{\displaystyle b} 1601:{\displaystyle a} 1581:{\displaystyle L} 1550: 1510: 1509: 1498: 1453:{\displaystyle C} 1422: 1403: 1366:{\displaystyle C} 1346:{\displaystyle Q} 1285: 1271: 1248:{\displaystyle l} 1228:{\displaystyle n} 951: 950: 947:3600 (at 16.7MW) 850: 849: 842: 723: 663: 662: 655: 511: 510: 36:neutral particles 2050: 2005: 2004: 1987:(3–4): 309–315. 1972: 1966: 1960: 1954: 1953: 1951: 1941: 1909: 1903: 1902: 1854: 1848: 1847: 1845: 1813: 1807: 1806: 1801:. 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519: 485:Wendelstein 7-X 463: 458: 171: 145:, such as pure 93: 45:burning plasmas 17: 12: 11: 5: 2056: 2046: 2045: 2031: 2030: 2025: 2020: 2013: 2012:External links 2010: 2007: 2006: 1967: 1955: 1904: 1849: 1808: 1805:on 2017-03-24. 1790: 1733: 1723: 1722: 1720: 1717: 1716: 1715: 1708: 1705: 1684: 1657: 1637: 1617: 1597: 1577: 1566: 1565: 1554: 1548: 1545: 1542: 1535: 1531: 1527: 1522: 1518: 1508: 1505: 1496: 1492: 1488: 1484: 1479: 1476: 1449: 1438: 1437: 1426: 1420: 1417: 1413: 1408: 1399: 1395: 1390: 1386: 1362: 1342: 1308: 1305: 1301: 1297: 1294: 1291: 1281: 1276: 1265: 1244: 1224: 1204: 1201: 1198: 1194: 1191: 1188: 1185: 1167: 1156: 1137: 1136: 1132: 1121: 1109: 1101: 1095: 1091: 1080: 1068: 1056: 1050: 1046: 1035: 1023: 1011: 1005: 1001: 990: 978: 966: 955: 952: 949: 948: 945: 942: 939: 935: 934: 931: 928: 925: 921: 920: 917: 914: 911: 907: 906: 903: 900: 897: 893: 892: 886: 881: 876: 848: 847: 798: 796: 789: 783: 780: 750: 739: 738: 727: 721: 718: 715: 712: 709: 705: 700: 697: 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819: 815: 809: 808: 804: 799:This section 797: 793: 788: 787: 779: 777: 772: 768: 764: 748: 725: 719: 716: 713: 710: 707: 703: 698: 695: 688: 687: 686: 672: 657: 654: 646: 643:December 2020 636: 632: 628: 622: 621: 617: 612:This section 610: 606: 601: 600: 593: 576: 573: 570: 569: 568: 565: 563: 557: 555: 536: Retired 513: 512: 506: 503: 500: 497: 494: 491: 488: 486: 483: 482: 478: 475: 472: 469: 466: 461: 456: 454: 451: 450: 446: 443: 440: 437: 434: 431: 428: 425: 422: 421: 417: 414: 411: 408: 405: 402: 399: 396: 393: 392: 388: 385: 382: 379: 376: 373: 370: 368: 365: 364: 360: 357: 354: 351: 348: 345: 342: 340: 337: 336: 332: 329: 326: 323: 320: 317: 314: 312: 309: 308: 304: 301: 298: 295: 292: 289: 286: 284: 281: 280: 276: 273: 270: 267: 264: 261: 258: 256: 253: 252: 248: 245: 242: 239: 236: 233: 230: 228: 225: 224: 220: 217: 215: 212: 210: 207: 205: 202: 199: 196: 193: 192: 188: 182: 180: 176: 166: 164: 160: 159:electrostatic 156: 152: 148: 144: 140: 132: 129: 126: 123: 120: 116: 113: 110: 107: 106: 105: 97: 88: 86: 82: 78: 74: 70: 66: 62: 58: 54: 50: 46: 41: 37: 33: 32:fusion device 29: 25: 21: 2043:Fusion power 1984: 1980: 1970: 1958: 1921: 1917: 1907: 1866: 1862: 1852: 1825: 1821: 1811: 1803:the original 1793: 1750: 1747:Nucl. Fusion 1746: 1736: 1727: 1673:vacuum pumps 1670: 1567: 1439: 1331: 1175: 1172: 1144: 1140: 1138: 1105: 1097: 1064: 1060: 1052: 1019: 1015: 1007: 974: 970: 962: 957: 866: 851: 836: 827: 812:Please help 800: 776:negative ion 770: 766: 762: 740: 664: 649: 640: 625:Please help 613: 566: 558: 550: 522: Active 504:Stellarator 476:Stellarator 187:fusion power 172: 149:or a mix of 136: 130: 124: 114: 108: 103: 83:(ICRH), and 53:negative ion 23: 19: 18: 1776:10281/96413 587:Beam energy 1719:References 1891:0741-3335 1785:124477971 1526:⋅ 1304:− 1296:⋅ 1290:≈ 1275:− 1264:τ 1190:∫ 1184:τ 1155:σ 1120:σ 1079:σ 1034:σ 989:σ 801:does not 749:λ 717:⋅ 711:⋅ 696:λ 673:λ 614:does not 151:deuterium 147:deuterium 131:Injecting 91:Mechanism 75:heating, 69:prototype 49:ion beams 30:inside a 2037:Category 1899:33934446 1707:See also 1701:ITER HNB 1104:→ 1059:→ 1014:→ 969:→ 444:Tokamak 415:Tokamak 386:Tokamak 358:Tokamak 330:Tokamak 302:Tokamak 274:Tokamak 246:Tokamak 143:hydrogen 139:isotopes 100:machine. 1989:Bibcode 1926:Bibcode 1871:Bibcode 1830:Bibcode 1755:Bibcode 858:caesium 822:removed 807:sources 635:removed 620:sources 462:15 (H) 459:20 (D) 395:JT60-SA 367:ASDEX-U 179:ASDEX-U 177:and in 163:ionized 155:tritium 1981:Vacuum 1897:  1889:  1783:  1697:JT-60U 905:H / D 902:H / D 879:JT-60U 540:  534:  526:  520:  514:Legend 464:6 (D) 457:9 (H) 339:DIII-D 255:JT-60U 200:N-NBI 197:P-NBI 87:(LH). 61:JT-60U 28:plasma 1895:S2CID 1781:S2CID 1284:1 MeV 1215:with 933:16.7 919:1000 741:with 507:2015 479:1998 447:2026 418:2020 389:1991 361:1986 333:2006 305:1982 277:1985 249:1983 218:Type 1887:ISSN 1826:2011 1440:and 1402:tank 930:6.4 927:5.8 916:190 913:400 889:ITER 805:any 803:cite 618:any 616:cite 424:ITER 321:0.5 311:EAST 283:TFTR 209:ICRH 204:ECRH 153:and 119:work 65:ITER 1997:doi 1944:hdl 1934:doi 1879:doi 1838:doi 1771:hdl 1763:doi 1483:9.7 1460:in 1321:m. 1293:1.4 1108:+ D 1100:+ D 1067:+ D 1055:+ D 1047:−11 1022:+ D 1010:+ D 1002:−10 977:+ D 965:+ D 891:** 884:LHD 816:by 629:by 495:10 453:LHD 438:20 435:20 432:33 403:10 400:24 371:20 343:20 296:11 287:40 259:40 240:10 231:34 227:JET 175:JET 141:of 57:LHD 24:NBI 2039:: 1995:. 1985:37 1983:. 1979:. 1942:. 1932:. 1922:19 1920:. 1916:. 1893:. 1885:. 1877:. 1867:53 1865:. 1861:. 1836:. 1820:. 1779:. 1769:. 1761:. 1751:55 1749:. 1745:. 1608:, 1588:, 1373:: 1307:16 1300:10 1168:ij 1143:, 1133:10 1092:01 1063:+ 1018:+ 973:+ 899:D 708:18 501:— 498:? 492:— 489:8 473:? 470:? 467:? 441:— 429:— 426:* 412:— 409:— 406:7 397:* 383:— 380:8 377:6 374:— 355:— 352:4 349:5 346:— 327:4 324:3 318:— 315:8 299:— 293:— 290:— 271:8 268:7 265:4 262:3 243:7 237:— 234:— 214:LH 73:RF 2003:. 1999:: 1991:: 1965:. 1952:. 1946:: 1936:: 1928:: 1901:. 1881:: 1873:: 1846:. 1840:: 1832:: 1787:. 1773:: 1765:: 1757:: 1683:L 1656:T 1636:m 1616:b 1596:a 1576:L 1553:, 1547:b 1544:+ 1541:a 1534:2 1530:b 1521:2 1517:a 1507:m 1504:T 1495:2 1491:/ 1487:L 1478:= 1475:C 1448:C 1425:, 1419:C 1416:2 1412:Q 1407:+ 1398:P 1394:= 1389:0 1385:P 1361:C 1341:Q 1280:, 1270:D 1243:l 1223:n 1203:, 1200:l 1197:d 1193:n 1187:= 1145:j 1141:i 1110:2 1106:D 1102:2 1098:D 1069:2 1065:e 1061:D 1057:2 1053:D 1024:2 1020:e 1016:D 1012:2 1008:D 979:2 975:e 971:D 967:2 963:D 843:) 837:( 832:) 828:( 824:. 810:. 771:E 767:M 763:n 726:, 720:M 714:n 704:E 699:= 656:) 650:( 645:) 641:( 637:. 623:. 22:(

Index

plasma
fusion device
neutral particles
magnetic confinement
burning plasmas
ion beams
negative ion
LHD
JT-60U
ITER
prototype
RF
electron cyclotron resonance
ion cyclotron resonance heating
lower hybrid resonance heating
First, plasma is formed by microwaving gas. Next, the plasma is accelerated across a voltage drop. This heats the ions to fusion conditions. After this the ions are re-neutralizing. Lastly, the neutrals are injected into the machine.
work
isotopes
hydrogen
deuterium
deuterium
tritium
electrostatic
ionized
JET
ASDEX-U
fusion power
ECRH
ICRH
LH

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