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Dragon reactor

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29: 173:. This suffered from a number of problems due to corrosion and the customer soured on the design. Contracts for similar models in the US that were being signed were cancelled, and although Dragon suffered none of these issues, no orders were forthcoming in Europe either. By this time the market had largely standardized on the 250:
The TRISO design was never widely commercialized. The German designs suffered from a number of problems, and while Dragon operated successfully for many years, declining interest in alternative designs led to its closure without a larger commercial variant being built. As of 2019, these concepts have
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remain, and they are in the process of being decommissioned. During decommissioning, the reactor vessels will be placed in reactor safestores, other structures will be dismantled and stored, any remaining waste will be sent to allocated storage sites, and the soil will be removed as necessary to a
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By the mid-1960s the concerns about helium availability had largely faded, and in 1967 considered a non-issue. By this time the major concern was building a cooling system that was leak-proof enough to contain the gas while still being inexpensive enough to build. The UKAEA, in particular, had
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is encapsulated in a ceramic material that is capable of sustaining extremely high temperatures. This ensures the fuel remains encapsulated even if the reactor itself is compromised. This also allows the reactor to operate at higher temperatures, which results in higher efficiency.
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and meant the gas would not become highly radioactive over time. At the time, helium was available in the required quantities only from the USA, who classified it as a strategic material and carefully controlled its international sales. Risley Nuclear Laboratories, developing the
243:(AGR), argued that the supply would be a serious issue, while CO2, in spite of any technical downsides, was trivially available. The OEEC team overseeing the project admitted that the helium issue "throw(s) doubt on the feasibility of employing it in an extensive power program." 348:), though later more lower enrichment (about 20%) fuel was used. The reactor resembled an enormous bottle, with the larger area at the bottom containing the active fuel within the reflector, and the smaller area on top holding additional fuel elements for reloading. 208:
to remove the heat and extract its energy. It is here that TRISO reactor designs may differ significantly. In the case of Dragon, the fuel was produced in small spherical pellets and then pressed into larger blocks containing the
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of the helium provided emergency cooling. The fuel used in the reactor was coated particles, consisting of micro-pellets of a fissile material (such as U235) surrounded by a ceramic outer layer. Initially most of the fuel was
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The choice of cooling gas for the design was highly controversial within the UK establishment. C.A. Rennie favoured the use of helium as it would reduce corrosion issues and had the added advantage of having a very low
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moderator formed into long hexagonal rods. The resulting blocks were then placed in fixed locations in the reactor. This is known as the "prismatic" design. While the Dragon reactor explored the prismatic design, the
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Originally conceived as a small research reactor, during the design phase it grew larger. The choice of helium coolant was made after a long debate within the UKAEA between proponents of helium and
653: 311:. Fuel was formed into tiny spherical pellets and then coated with ceramics. These were then mixed with the graphite and pressed together to form blocks of various shapes and sizes. 152: 327:, as well as its chemical inertness allowing it to operate at higher temperatures without fear of eroding the reactor materials. Higher temperatures also allow for more efficient 247:
already gone ahead with the AGR program and were noting the issues with corrosion due to the CO2, and raised concerns that helium might not be as inert as proponents suggested.
554: 368:. Finally, the site will be declassified as a nuclear licensed site, landscaped and returned to normal use. The contract for decommissioning the site has been awarded to 663: 579: 648: 356:
The Winfrith site extended to 129.4 hectares (320 acres) of heathland in rural south Dorset, and nine different experimental reactors were located there.
678: 668: 260: 166:, with helium ultimately selected. Groundbreaking occurred in 1960. It operated from 1965 to 1976, and is generally considered extremely successful. 673: 252: 144: 42: 360: 170: 147:(UKAEA). Its purpose was to test fuel and materials for the European High Temperature Reactor programme, which was exploring the use of 658: 610: 643: 268: 504: 69: 284: 583: 104: 240: 437: 159:
international project. In total, 13 countries were involved in its design and operation during the project lifetime.
624: 177:(PWR) for the large buildout that occurred during the 1970s and 80s, and the decision was made to shut down Dragon. 365: 529: 389:
M S Barents (2000). "Decommissioning the Winfrith technology centre – Environmental Restoration with a Purpose".
174: 510:. 18th International Conference on Structural Mechanics in Reactor Technology. SMiRT18-S05-2. Archived from 341: 319:, allowing additional fuel to be held in a ready area and loaded on-the-fly. Helium was used due to its low 151:
fuel and gas cooling for future high-efficiency reactor designs. The project was built and managed as an
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was built for the construction and operation of experimental and research nuclear reactors. Dragon used
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Dragon's construction was followed by similar work in the US, leading ultimately to the much larger
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is only possible when the blocks are placed together in certain configurations within a
618:. 18th International Conference on Structural Mechanics in Reactor Technology. Beijing. 236: 163: 637: 511: 369: 328: 205: 332: 215: 193: 438:"Demonstration HTR-PM connected to grid : New Nuclear - World Nuclear News" 345: 256: 336: 84: 71: 372:, and the final decommissioning phase has been deferred for twenty years. 192:
fuel concept became an area of significant interest. In this concept, the
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Operating experience with the DRAGON High Temperature Reactor experiment
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While the TRISO assembly provides the fuel, a reactor also requires a
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Europe's Nuclear Power Experiment: History of the OECD Dragon Project
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The Primary Circuit Of The Dragon High Temperature Reactor Experiment
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been used in several further research reactors, including
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WM'00 Conference, February 27 – March 2, 2000, Tucson, AZ
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Of the nine reactors, only the Dragon Reactor and the
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operation and make it more suitable for direct use as
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Organisation for Economic Co-operation and Development
557:. Nuclear Decommissioning Authority. 25 October 2013 118: 110: 100: 63: 48: 38: 21: 459: 457: 654:Nuclear research institutes in the United Kingdom 267:as well as for small-scale commercial reactors, 16:UK experimental HTR, operated from 1965 to 1976 218:developed an alternative concept known as the 8: 180:As of 2023, Dragon is being decommissioned. 287:connected to the grid as of December 2021. 335:. In the case of a power failure, natural 664:Nuclear technology in the United Kingdom 476: 474: 472: 283:is under construction, with one unit at 574: 572: 381: 145:United Kingdom Atomic Energy Authority 43:United Kingdom Atomic Energy Authority 18: 131:was an experimental high temperature 7: 463: 403: 361:Steam Generating Heavy Water Reactor 171:Fort Saint Vrain Nuclear Power Plant 295:The Atomic Energy Establishment at 33:Cutaway model of the Dragon reactor 649:Former nuclear research institutes 580:"Winfrith's DRAGON loses its fire" 14: 679:1976 disestablishments in England 669:Science and technology in Dorset 528:Simon, R.A.; Capp, P.D. (2002). 27: 503:Simon, Rainer (7 August 2005). 190:tristructural-isotropic (TRISO) 149:tristructural-isotropic (TRISO) 674:1965 establishments in England 1: 609:Simon, Rainer (August 2005). 535:(Report). IAEA. INIS-XA--524 105:High-temperature gas reactor 241:Advanced Gas-cooled Reactor 143:, England, operated by the 695: 442:www.world-nuclear-news.org 366:Low Level Waste Repository 659:Nuclear research reactors 175:pressurized water reactor 26: 644:Defunct nuclear reactors 342:highly enriched uranium 303:gas as the coolant and 188:During the 1950s, the 417:"Triso Particle Fuel" 321:nuclear cross section 228:nuclear cross section 157:Nuclear Energy Agency 39:Operating Institution 623:Shaw, E. N. (1983). 323:which led to higher 230:which improved the 81: /  421:Ultra Safe Nuclear 220:pebble-bed reactor 133:gas-cooled reactor 85:50.6840°N 2.2694°W 317:neutron reflector 309:neutron moderator 202:neutron moderator 126: 125: 111:First Criticality 686: 630: 619: 617: 596: 595: 593: 591: 582:. 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Retrieved 584:the original 559:. Retrieved 549: 537:. Retrieved 523: 512:the original 498: 486:. Retrieved 445:. Retrieved 441: 420: 411: 406:, p. 2. 399: 390: 384: 358: 355: 333:process heat 294: 253:Peach Bottom 249: 245: 224: 216:West Germany 199: 194:nuclear fuel 187: 179: 168: 161: 128: 127: 629:. Pergamon. 346:uranium-235 344:(about 93% 313:Criticality 291:The reactor 88: / 64:Coordinates 638:Categories 482:"Winfrith" 447:2022-07-25 376:References 337:convection 285:Shidao Bay 73:50°41′02″N 590:24 August 488:24 August 464:Shaw 1983 404:Shaw 1983 364:suitable 76:2°16′10″W 59:, England 484:. Magnox 305:graphite 297:Winfrith 273:THTR-300 211:graphite 137:Winfrith 53:Winfrith 49:Location 307:as the 184:Concept 561:7 June 539:7 June 301:helium 277:HTR-PM 275:. The 265:HTR-10 263:, and 204:and a 141:Dorset 129:Dragon 57:Dorset 616:(PDF) 533:(PDF) 515:(PDF) 508:(PDF) 281:China 592:2016 563:2021 541:2021 490:2016 271:and 261:HTTR 122:1976 114:1965 101:Type 279:in 257:AVR 139:in 135:at 640:: 571:^ 471:^ 456:^ 440:. 429:^ 419:. 259:, 255:, 55:, 594:. 565:. 543:. 492:. 466:. 450:. 423:. 393:. 155:/

Index


United Kingdom Atomic Energy Authority
Winfrith
Dorset
50°41′02″N 2°16′10″W / 50.6840°N 2.2694°W / 50.6840; -2.2694
High-temperature gas reactor
gas-cooled reactor
Winfrith
Dorset
United Kingdom Atomic Energy Authority
tristructural-isotropic (TRISO)
Organisation for Economic Co-operation and Development
Nuclear Energy Agency
carbon dioxide
Fort Saint Vrain Nuclear Power Plant
pressurized water reactor
tristructural-isotropic (TRISO)
nuclear fuel
neutron moderator
cooling fluid
graphite
West Germany
pebble-bed reactor
nuclear cross section
neutron economy
carbon dioxide
Advanced Gas-cooled Reactor
Peach Bottom
AVR
HTTR

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