22:
2034:
2024:
2004:
2014:
214:
or uranium oxycarbide are also possibilities. Uranium oxycarbide combines uranium carbide with the uranium dioxide to reduce the oxygen stoichiometry. Less oxygen may lower the internal pressure in the TRISO particles caused by the formation of carbon monoxide, due to the oxidization of the porous
142:
was one example of this design that operated as an HTGR from 1979 to 1989. Though the reactor was beset by some problems which led to its decommissioning due to economic factors, it served as proof of the HTGR concept in the United States (though no new commercial HTGRs have been developed there
267:
and the helium coolant is single phase, inert, and has no reactivity effects. The core is composed of graphite, has a high heat capacity and structural stability even at high temperatures. The fuel is coated uranium-oxycarbide which permits high burn-up (approaching 200 GWd/t) and retains
776:
Alrwashdeh, Mohammad, and Saeed A. Alameri. "Two-Dimensional Full Core
Analysis of IFBA-Coated TRISO Fuel Particles in Very High Temperature Reactors." In International Conference on Nuclear Engineering, vol. 83761, p. V001T05A014. American Society of Mechanical Engineers,
786:
Alrwashdeh, Mohammad, Saeed A. Alameri, and Ahmed K. Alkaabi. "Preliminary Study of a
Prismatic-Core Advanced High-Temperature Reactor Fuel Using Homogenization Double-Heterogeneous Method." Nuclear Science and Engineering 194, no. 2 (2020):
992:
Three of these plants, AVR, Peach Bottom, and Fort St. Vrain, are actual electrical generating plants, and two, Dragon and UHTREX, are experimental plants being used primarily to develop the technology of high – temperature, gas-cooled
215:
carbon layer in the particle. The TRISO particles are either dispersed in a pebble for the pebble bed design or molded into compacts/rods that are then inserted into the hexagonal graphite blocks. The QUADRISO fuel concept conceived at
766:
Alameri, Saeed A., and
Mohammad Alrwashdeh. "Preliminary three-dimensional neutronic analysis of IFBA coated TRISO fuel particles in prismatic-core advanced high temperature reactor." Annals of Nuclear Energy 163 (2021):
796:
Alrwashdeh, Mohammad, Saeed A. Alamaeri, Ahmed K. Alkaabi, and
Mohamed Ali. "Homogenization of TRISO Fuel using Reactivity Equivalent Physical Transformation Method." Transactions 121, no. 1 (2019): 1521-1522.
578:
to develop the technology of high-temperature gas-cooled reactors. In UHTREX, unlike HTGR reactors, helium coolant contacted nuclear fuel directly, reaching temperatures in excess of 1300 °C.
645:
The high-temperature gas-cooled reactor (HTGR) is a uranium-fueled, graphite-moderated, gas-cooled nuclear reactor design concept capable of producing very high core outlet temperatures
2037:
231:, so it will generally not chemically react with any material. Additionally, exposing helium to neutron radiation does not make it radioactive, unlike most other possible coolants.
138:
unit 1 reactor in the United States was the first HTGR to produce electricity, and did so very successfully, with operation from 1966 through 1974 as a technology demonstrator.
1128:
1168:
926:
263:
The design takes advantage of the inherent safety characteristics of a helium-cooled, graphite-moderated core with specific design optimizations. The graphite has large
1832:
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The neutron moderator is graphite, although whether the reactor core is configured in graphite prismatic blocks or in graphite pebbles depends on the HTGR design.
1014:
21:
1227:
479:
159:
359:
135:
107:
moderator. Development of this high temperature design proposal continued at the Power Pile
Division of the Clinton Laboratories (known now as
1161:
2063:
2058:
1473:
1108:
1046:
419:
26:
1390:
1113:
285:
As of 2011, a total of seven HTGR reactors had been constructed and operated. A further two HTGR reactors were brought on-line at China's
1142:
1466:
1672:
927:
http://www.uxc.com/smr/Library/Design%20Specific/HTR-PM/Papers/2006%20-%20Design%20aspects%20of%20the%20Chinese%20modular%20HTR-PM.pdf
597:
901:
268:
fission products. The high average core-exit temperature of the VHTR (1,000 °C) permits emissions-free production of high grade
1154:
1126:
139:
127:, was leader of the team responsible for the initial development of the High temperature gas-cooled reactor (HTGR), as well as the
2007:
1982:
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1239:
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1222:
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1207:
216:
1875:
1554:
587:
42:
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are inserted in holes cut in the graphite blocks that make up the core. The VHTR will be controlled like current
2017:
1942:
1842:
1754:
1138:
264:
100:
53:
coolant. The reactor core can be either a "prismatic block" (reminiscent of a conventional reactor core) or a "
1021:
749:
77:
1721:
1972:
1947:
1561:
1338:
902:"Thermal performance and flow instabilities in a multi-channel, helium-cooled, porous metal divertor module"
128:
1837:
181:
reactors, each with 100 MW of electrical production capacity, have gone operational in China as of 2021.
72:
The high operating temperatures of HTGR reactors potentially enable applications such as process heat or
1867:
1822:
1284:
1212:
694:
247:
designs if it utilizes a pebble bed core, the control rods will be inserted in the surrounding graphite
81:
956:"High Temperature Gas-Cooled Reactors Lessons Learned Applicable to the Next Generation Nuclear Plant"
1817:
1802:
819:
662:
120:
46:
1977:
1952:
1737:
1331:
1199:
58:
95:
The use of a high-temperature, gas-cooled reactor for power production was proposed by in 1944 by
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637:
96:
54:
38:
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955:
682:
248:
66:
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1008:
858:
827:
674:
658:
252:
1677:
1517:
1456:
847:"A novel concept of QUADRISO particles. Part II: Utilization for excess reactivity control"
750:"Demonstration HTR PM prepares for grid connection : New Nuclear – World Nuclear News"
1935:
1895:
1422:
1349:
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707:
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112:
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329:
147:
16:
Type of nuclear reactor that operates at high temperatures as part of normal operation
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1366:
424:
364:
862:
659:"Summary Report on Design and Development of High Temperature Gas-Cooled Power Pile"
1641:
1146:
986:
Lipper, H. W. (1969), "High-Temperature Gas-Cooled
Reactors Using Helium Coolant",
269:
99:, then associate director of the chemistry division at the University of Chicago's
831:
1699:
1289:
721:
389:
240:
151:
807:
638:"A White Paper: Disposition Options for a High-Temperature Gas-Cooled Reactor"
1040:
1410:
1400:
1103:
1076:
737:
666:
615:
228:
104:
1905:
87:(VHTR) which would initially work with temperatures of 750 to 950 °C.
618:(2020) – a micro–small modular reactor design effort, discontinued in 2023
1930:
1779:
1774:
1714:
1383:
1311:
1294:
1279:
1254:
609:
449:
206:
fuel particles. Coated fuel particles have fuel kernels, usually made of
155:
73:
657:
McCullough, C. Rodgers; Staff, Power Pile
Division (15 September 1947).
1920:
1900:
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62:
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678:
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Helium has been the coolant used in all HTGRs to date. Helium is an
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929:
Page 489, Table 2. Quote: Designed operational life time (year) 60
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1602:
1405:
1395:
1118:
612:(2016) – developers of a proposed Generation IV pebble-bed reactor
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514:
484:
203:
1073:"The European VHTR research & development programme: RAPHAEL"
1607:
1496:
1306:
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734:
244:
163:
146:
Experimental HTGRs have also existed in the United
Kingdom (the
1150:
606:(2005) – a proposed Generation IV very-high-temperature reactor
1580:
1444:
988:
Helium symposia proceedings in 1968: a hundred years of helium
251:. Control can also be attained by adding pebbles containing
600:(1997) – proposed reactor with gas turbine power conversion
877:"High temperature gas cool reactor technology development"
219:
has been used to better manage the excess of reactivity.
202:
The fuel used in HTGRs is coated fuel particles, such as
963:
To date, seven HTGR plants have been built and operated
1092:
Pebble Bed
Advanced High Temperature Reactor (PB-AHTR)
177:
of generation). Two full-scale pebble-bed HTGRs, the
119:
also played a role in development during the 1950s.
49:
output temperatures. All existing HTGR reactors use
1965:
1866:
1796:
1745:
1736:
1663:
1629:
1620:
1579:
1572:
1552:
1505:
1487:
1443:
1348:
1330:
1198:
272:. Reactors are designed for 60 years of service.
103:. Initially, Daniels envisaged a reactor using
1041:Generation IV International Forum VHTR website
1833:Small sealed transportable autonomous (SSTAR)
1162:
1114:INL Thermal-Hydraulic Analyses of the LS-VHTR
80:. A proposed development of the HGTR is the
8:
2013:
1810:
1742:
1626:
1576:
1569:
1345:
1169:
1155:
1147:
570:Additionally, from 1969 to 1971, the 3 MW
291:
35:high-temperature gas-cooled reactor (HTGR)
572:Ultra-High Temperature Reactor Experiment
160:High-temperature engineering test reactor
954:J. M. Beck, L. F. Pincock (April 2011).
20:
628:
1760:Liquid-fluoride thorium reactor (LFTR)
949:
947:
945:
943:
941:
939:
937:
935:
703:
692:
1765:Molten-Salt Reactor Experiment (MSRE)
158:), and currently exist in Japan (the
7:
975:https://aris.iaea.org/PDF/HTR-PM.pdf
882:. IAEA. 15 November 1996. p. 61
808:"Nuclear fuels – Present and future"
1770:Integral Molten Salt Reactor (IMSR)
1141:reports to the IAEA in April 2014:
636:Evans D. Kitcher (26 August 2020).
1009:Idaho National Lab VHTR Fact Sheet
598:Gas turbine modular helium reactor
259:Safety features and other benefits
76:production via the thermochemical
14:
669:, USA: Clinton Laboratories (now
140:Fort St. Vrain Generating Station
2033:
2032:
2023:
2022:
2012:
2003:
2002:
1853:Fast Breeder Test Reactor (FBTR)
173:, a pebble-bed design with 10 MW
1121:slides from 2014 about Areva's
863:10.1016/j.nucengdes.2010.03.025
65:, a 250 MW HTGR power plant in
1843:Energy Multiplier Module (EM2)
990:, United States, p. 117,
851:Nuclear Engineering and Design
590:(1994) – reactor proposed for
576:Los Alamos National Laboratory
1:
961:. Idaho National Laboratory.
904:. Inist. 2000. Archived from
832:10.1016/j.jnucmat.2009.01.297
722:"Peter Fortescue Dies at 102"
671:Oak Ridge National Laboratory
643:. Idaho National Laboratory.
604:Next Generation Nuclear Plant
592:Koeberg Nuclear Power Station
162:using prismatic fuel with 30
109:Oak Ridge National Laboratory
85:very-high-temperature reactor
1643:Uranium Naturel Graphite Gaz
812:Journal of Nuclear Materials
169:of capacity) and China (the
2064:Graphite moderated reactors
2059:Nuclear power reactor types
1990:Aircraft Reactor Experiment
1047:"INL VHTR workshop summary"
217:Argonne National Laboratory
41:which use uranium fuel and
2080:
1828:Liquid-metal-cooled (LMFR)
588:Pebble bed modular reactor
239:In the prismatic designs,
39:gas-cooled nuclear reactor
1998:
1953:Stable Salt Reactor (SSR)
1848:Reduced-moderation (RMWR)
1813:
1655:Advanced gas-cooled (AGR)
1185:
574:(UHTREX) was operated by
111:) until 1947. Professor
2018:List of nuclear reactors
1858:Dual fluid reactor (DFR)
1474:Steam-generating (SGHWR)
1139:Office of Nuclear Energy
1104:IAEA HTGR Knowledge Base
845:Talamo, Alberto (2010).
101:Metallurgical Laboratory
2008:Nuclear fusion reactors
1973:Organic nuclear reactor
1179:nuclear fission reactor
129:Gas-cooled fast reactor
1097:6 October 2010 at the
754:world-nuclear-news.org
702:Cite journal requires
30:
276:List of HTGR reactors
45:to produce very high
27:Fort Saint Vrain HTGR
24:
1838:Traveling-wave (TWR)
1322:Supercritical (SCWR)
1131:4 March 2016 at the
1037:(from the year 2002)
806:Olander, D. (2009).
281:Constructed reactors
1208:Aqueous homogeneous
1059:on 29 November 2007
1027:on 25 February 2009
1015:"VHTR presentation"
824:2009JNuM..389....1O
738:HTGR Knowledge Base
78:sulfur–iodine cycle
61:currently operates
59:China Huaneng Group
43:graphite moderation
25:Refueling floor at
2028:Nuclear technology
908:on 30 January 2012
289:site, in 2021/22.
97:Farrington Daniels
31:
2046:
2045:
2038:Nuclear accidents
1961:
1960:
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253:neutron absorbers
190:Neutron moderator
67:Shandong province
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1948:Helium gas (GFR)
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1075:. Archived from
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857:(7): 1919–1927.
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150:) and Germany (
131:(GCFR) system.
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37:is a type of
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1876:Sodium (SFR)
1803:fast-neutron
1642:
1188:
1081:. Retrieved
1077:the original
1061:. Retrieved
1054:the original
1029:. Retrieved
1022:the original
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695:cite journal
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631:
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360:Peach Bottom
284:
270:process heat
262:
241:control rods
238:
226:
201:
198:Nuclear fuel
193:
145:
136:Peach Bottom
133:
123:, whilst at
94:
84:
71:
47:reactor core
34:
32:
18:
1911:Superphénix
1738:Molten-salt
1690:VHTR (HTGR)
1467:HW BLWR 250
1433:R4 Marviken
1362:Pressurized
1332:Heavy water
1316:many others
1245:Pressurized
1200:Light water
1063:21 December
1031:24 November
818:(1): 1–22.
552:Operational
522:Operational
492:Operational
324:power (MW)
210:, however,
152:AVR reactor
2053:Categories
1695:PBR (PBMR)
623:References
558:Pebble bed
528:Pebble bed
468:Pebble bed
408:Pebble bed
314:Fuel type
55:pebble-bed
1747:Fluorides
1411:IPHWR-700
1406:IPHWR-540
1401:IPHWR-220
1190:Moderator
1177:Types of
993:reactors.
663:Oak Ridge
616:U-Battery
498:Prismatic
438:Prismatic
378:Prismatic
348:Prismatic
311:reactors
306:Shutdown
249:reflector
229:inert gas
105:beryllium
69:, China.
57:" core.
1780:TMSR-LF1
1775:TMSR-500
1755:Fuji MSR
1715:THTR-300
1555:Graphite
1418:PHWR KWU
1384:ACR-1000
1312:IPWR-900
1295:ACPR1000
1290:HPR-1000
1280:CPR-1000
1255:APR-1400
1129:Archived
1095:Archived
787:163-167.
610:X-energy
450:THTR-300
300:Country
295:Facility
156:THTR-300
143:since).
74:hydrogen
1921:FBR-600
1901:CFR-600
1896:BN-1200
1562:coolant
1489:Organic
1374:CANDU 9
1371:CANDU 6
1339:coolant
1300:ACP1000
1275:CAP1400
1213:Boiling
1123:SC-HTGR
820:Bibcode
767:108551.
687:4359623
501:850–950
455:Germany
395:Germany
381:700–726
322:Thermal
235:Control
223:Coolant
117:Germany
91:History
1966:Others
1906:Phénix
1891:BN-800
1886:BN-600
1881:BN-350
1710:HTR-PM
1705:HTR-10
1685:UHTREX
1650:Magnox
1645:(UNGG)
1538:Lucens
1533:KS 150
1270:ATMEA1
1250:AP1000
1233:Kerena
1083:1 July
685:
540:HTR-PM
510:HTR-10
317:Outlet
309:No. of
287:HTR-PM
179:HTR-PM
171:HTR-10
63:HTR-PM
51:helium
29:, 1972
1983:Piqua
1978:Arbus
1936:PRISM
1678:MHR-T
1673:GTMHR
1603:EGP-6
1598:AMB-X
1573:Water
1518:HWGCR
1457:HWLWR
1396:IPHWR
1367:CANDU
1228:ESBWR
1119:IFNEC
1057:(PDF)
1050:(PDF)
1025:(PDF)
1018:(PDF)
959:(PDF)
912:8 May
886:8 May
880:(PDF)
641:(PDF)
545:China
515:China
485:Japan
354:21.5
297:name
204:TRISO
1943:Lead
1926:CEFR
1916:PFBR
1798:None
1608:RBMK
1593:AM-1
1523:EL-4
1497:WR-1
1479:AHWR
1423:MZFR
1391:CVTR
1380:AFCR
1307:VVER
1265:APWR
1260:APR+
1223:ABWR
1137:The
1085:2015
1065:2005
1033:2005
914:2009
888:2009
777:2020
735:IAEA
708:help
683:OSTI
564:250
549:2021
519:2000
489:1999
480:HTTR
474:750
462:1988
459:1985
444:842
432:1989
429:1979
402:1988
399:1967
384:115
372:1974
369:1967
342:1967
339:1965
245:PBMR
154:and
134:The
1931:PFR
1722:PMR
1700:AVR
1622:Gas
1560:by
1528:KKN
1462:ATR
1377:EC6
1337:by
1285:EPR
1218:BWR
859:doi
855:240
828:doi
816:389
675:doi
673:).
561:750
534:10
531:700
504:30
471:750
441:777
414:46
411:950
390:AVR
351:750
115:in
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1631:CO
1507:CO
1428:R3
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697:}}
693:{{
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667:TN
665:,
661:.
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166:th
164:MW
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