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A Survey of the Fuel Cycles Operated in the United Kingdom; Etude d'ensemble sur les cycles de combustible au Royaume-Uni; Obzor toplivnykh tsiklov, ispol'zuemykh v soedinennom korolevstve; Estudio de los ciclos de combustible utilizados en el Reino Unido

Conference:

Abstract

(a) The natural uranium/ magnox fuel cycle. The United Kingdom have chosen the natural uranium graphite-moderated gas-cooled reactor as the basis of their nuclear power programme. They have operated the reactors at Calder Hall and Chapelcross for seven years; the Berkeley and Bradwell reactors of the CEGB are now operating, and reactors at seven other sites are under construction or planned. The fuel for these reactors is designed and manufactured at the U.K.A.E.A. Springfields factory and then transported to the reactor site for loading. After irradiation and discharge the fuel is transported to the U.K.A.E.A. site at Windscale for separation of uranium and plutonium from fission products. The paper outlines the UK experience of design and manufacture of fuel, re actor operation, transport of irradiated fuel and subsequent processing of the fuel. Mention is made of the behaviour of fuel in a reactor and alternative charging and discharging programmes, the subject is further elaborated in another paper. (b) Reactors using enriched fuels. The UK are developing an advanced gas-cooled reactor (AGR), the prototype reactor of which came on power in 1963. The fuel is manufactured from enriched uranium oxide canned in stainless steel and it will be reprocessed through a  More>>
Authors:
Allday, C. [1] 
  1. United Kingdom Atomic Energy Authority, Risley, Warrington, Lancs (United Kingdom)
Publication Date:
Oct 15, 1963
Product Type:
Conference
Resource Relation:
Conference: Conference on Operating Experience with Power Reactors, Vienna (Austria), 4-8 Jun 1963; Other Information: 12 figs., 1 tab., 14 refs.; Related Information: In: Operating Experience with Power Reactors. Proceedings of the Conference on Operating Experience with Power Reactors. Vol. II| 428 p.
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; AGR TYPE REACTORS; BRADWELL REACTOR; CALDER HALL A-1 REACTOR; CALDER HALL A-2 REACTOR; CHAPELCROSS-1 REACTOR; CHAPELCROSS-2 REACTOR; ENRICHED URANIUM; FAST REACTORS; FISSION PRODUCTS; FUEL CYCLE; FUEL FABRICATION PLANTS; FUEL REPROCESSING PLANTS; NATURAL URANIUM; PLUTONIUM; REACTOR FUELING; REACTOR SITES; STAINLESS STEELS; TRANSPORT; UNITED KINGDOM
OSTI ID:
22108197
Research Organizations:
International Atomic Energy Agency, Vienna (Austria)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
Other: ISSN 0074-1884; TRN: XA13R0419066008
Submitting Site:
INIS
Size:
page(s) 269-293
Announcement Date:
Jun 27, 2013

Conference:

Citation Formats

Allday, C. A Survey of the Fuel Cycles Operated in the United Kingdom; Etude d'ensemble sur les cycles de combustible au Royaume-Uni; Obzor toplivnykh tsiklov, ispol'zuemykh v soedinennom korolevstve; Estudio de los ciclos de combustible utilizados en el Reino Unido. IAEA: N. p., 1963. Web.
Allday, C. A Survey of the Fuel Cycles Operated in the United Kingdom; Etude d'ensemble sur les cycles de combustible au Royaume-Uni; Obzor toplivnykh tsiklov, ispol'zuemykh v soedinennom korolevstve; Estudio de los ciclos de combustible utilizados en el Reino Unido. IAEA.
Allday, C. 1963. "A Survey of the Fuel Cycles Operated in the United Kingdom; Etude d'ensemble sur les cycles de combustible au Royaume-Uni; Obzor toplivnykh tsiklov, ispol'zuemykh v soedinennom korolevstve; Estudio de los ciclos de combustible utilizados en el Reino Unido." IAEA.
@misc{etde_22108197,
title = {A Survey of the Fuel Cycles Operated in the United Kingdom; Etude d'ensemble sur les cycles de combustible au Royaume-Uni; Obzor toplivnykh tsiklov, ispol'zuemykh v soedinennom korolevstve; Estudio de los ciclos de combustible utilizados en el Reino Unido}
author = {Allday, C.}
abstractNote = {(a) The natural uranium/ magnox fuel cycle. The United Kingdom have chosen the natural uranium graphite-moderated gas-cooled reactor as the basis of their nuclear power programme. They have operated the reactors at Calder Hall and Chapelcross for seven years; the Berkeley and Bradwell reactors of the CEGB are now operating, and reactors at seven other sites are under construction or planned. The fuel for these reactors is designed and manufactured at the U.K.A.E.A. Springfields factory and then transported to the reactor site for loading. After irradiation and discharge the fuel is transported to the U.K.A.E.A. site at Windscale for separation of uranium and plutonium from fission products. The paper outlines the UK experience of design and manufacture of fuel, re actor operation, transport of irradiated fuel and subsequent processing of the fuel. Mention is made of the behaviour of fuel in a reactor and alternative charging and discharging programmes, the subject is further elaborated in another paper. (b) Reactors using enriched fuels. The UK are developing an advanced gas-cooled reactor (AGR), the prototype reactor of which came on power in 1963. The fuel is manufactured from enriched uranium oxide canned in stainless steel and it will be reprocessed through a ''head-end'' which will be added to the Windscale Magnox separation plant. The enriched uranium for the AGR is produced in the UK Diffusion Plant at Capenhurst. An alternative to enriched uranium oxide as a fuel is plutonium-enriched natural-uranium oxide. The paper outlines the experience in production of oxide fuel for AGR, the operating experience with the reactor so far and the plans for reprocessing the fuel. The alternative use of a plutonium fuel is considered and the effects of this on costs and the fuel cycle. Finally the paper outlines the place of Magnox and AGR reactors in the UK power programme. (author) [French] a) Cycle de l'uranlum naturel gaine de magnox. Le Royaume-Uni a choisi de fonder son programme d'energie d'origine nucleaire sur la filie re des reacteurs a l'uranium naturel et au graphite, refroidis par un gaz. Les reacteurs de Calder Hall et de Chapelcross fonctionnent depuis sept ans; ceux de Berkeley et de Bradwell, qui dependent du Central Electricity Generating Board (CEGB), sont maintenant en service et sept autres reacteurs sont en construction ou en projet. Le combustible destine a ces reacteurs est etudie et fabrique dans l'usine de l'Atomic Energy Authority (AEA) a Springfields, puis transporte jusqu'au reacteur. Apres irradiation et dechargement, le combustible est transporte a l'usine de l'AEA, situee a Windscale, ou l'uranium et le plutonium sont separes des produits de fission. L'auteur decrit l'experience britannique en matiere d'etude et de fabrication du combustible, d'exploitation du reacteur, de transport et de traitement chimique du combustible irradie. Il examine brievement le comportement du combustible dans le reacteur et les differents programmes possibles de chargement et de dechargement, ce sujet etant developpe dans un autre memoire. b) Reacteurs utilisant les combustibles enrichis. Le Royaume-Uni met au point un reacteur perfectionne refroidi par un gaz (Advanced Gas Cooled Reactor = AGR), dont le prototype a ete mis en service en 1963. Le combustible est fabrique a partir d'oxyde d'uranium enrichi gaine d' acier inoxydable; apres irradiation, il sera traite dans une novelle installation qui sera ajoutee a l'usine de separation de Windscale ou est actu ellement traite le combustible gaine de magnox. L'uranium enrichi destine a AGR est produit par l'usine de diffusion situee a Capenhurst. L'oxyde d'uranium naturel enrichi au plutonium peut remplacer, comme combustible, l'oxyde d'uranium enrichi. L'auteur decrit l'experience acquise dans la transformation de l'oxyde destine a AGR et dans le fonctionnement du reacteur et indique comment on envisage de traiter le combustible irradie. Il examine le cas de l'utilisation d'un combustible au plutonium et ses incidences sur le prix de revient et le cycle du combustible. Enfin, il precise la place qu'occupent les reacteurs a l'uranium naturel gaine de magnox et les reacteurs AGR dans le programme britannique d'energie d'origine nucleaire. (author) [Spanish] a) El ciclo uranio natural/Magnox. En el Reino Unido se ha adoptado el reactor de uranio natural moderado con grafito y refrigerado con gas como base del respectivo programa de energia nucleoelectrica. Se explotan desde hace siete afios los reactores de Calder Hall y Chapelcross; ahora han comenzado a funcionar los reactores de Berkeley y Bradwell, de la Central Electricity Generating Board, y hay reactores en construccion o en proyecto en otros siete emplazamientos. El combustible destinado a esos reactores se prepara y elabora en el establecimiento de Springfields de la Atomic Energy Authority y de alli se transporta al reactor para efectuar la carga. Una vez irradiado y descargado, el combustible se lleva al establecimiento de la AEA en Windscale, para separar el uranio y el plutonio de los productos de fision. El autor resena la experiencia en el Reino Unido en materia de calculo y elaboracion de elementos combustibles, explotacion de reactores, transporte de combustible irradiado y regeneracion del mismo. Alude al comportamiento del combustible en un reactor y a los programas de carga y descarga alternada, tema que se desarrolla mas' extensamente en otra memoria. b) Reactores de combustible enriquecido. En el Reino Unido se viene probando un reactor avanzado refrigerado con gas, cuyo prototipo comenzo a desarrollar potencia en 1963. El combustible se elabora con oxido de uranio enriquecido revestido de acero inoxidable y sera regenerado en una seccion especial que se agregara al establecimiento de separacion de combustible Magnox en Windscale. El uranio enriquecido para el reactor avanzado (AGR) se produce en la planta de difusion gaseosa en Capenhurst. En lugar del oxido de uranio enriquecido tambien se puede utilizar como combustible oxido de uranio natural enriquecido con plutonio. En la memoria se resume la experiencia adquirida en la produccion de combustible de oxido para el AGR y en la explotacion del reactor y los planes para la regeneracion del combustible. Se examina la posibilidad de utilizar combustible de plutonio y se analizan las consecuencias que tendria su adopcion sobre los costos y el ciclo del combustible. Por ultimo, se destaca la importancia de los reactores Magnox y AGR en el programa energetico del Reino Unido. (author) [Russian] a ) Prirodnyj uran/topdivnyj tsikl ''Magnoks''. Soedinennoe Kor olevstvo izb ralo reaktor na prirodnom urane s grafitovym zam edli tel em i gazovy m okhlazhdeniem v kachestve osnovy programmy po yadernoj ehnergii. Ono ehkspluatirovalo ehti reaktory v Kolder-Kholle i Chepelkrosse v techenie semi det; reaktory v Berkli i Braduehlle v nastoyashchee vremya nakhodyatsya v stadii ehkspluatatsii, a reaktory v semi drugikh mestakh v stadii stroitel'stva ili planirovaniya. Toplivo dlya ehtikh reaktorov proizvoditsya na zavode v Springfilde i zatem perevozitsya dlya zagruzki k mestopolozheniyu reaktora. Posle oblucheniya i razgruzki toplivo transportiruetsya na zavod v Uindskejl dlya otdeleniya urana i plutoniya ot produktov deleniya. Daetsya opisanie opyta CK v oblasti konstruktsii i proizvodstva toplivnykh ehlementov, ehkspluatatsii reaktora, transportirovki obluchennogo topliva i posleduyushchej obrabotki topliva. Upominaetsya o povedenii topliva v reaktore i ob al'ternativnykh programmakh zagruzki l razgruzki toplivnykh ehlementov; ehta tema razrabatyvaetsya v drugikh trudakh. b) Reaktory, ispol'zuyushchie obogashchennoe toplivo. Soedinennoe Korolevstvo razrabatyvaet usovershenstvovannyj reaktors gazovym okhlazhdeniem AGE, prototip kotorogo voshel v stroj v 1963 godu. Toplivo proizvoditsya iz obogashchennoj okisi urana, zaklyuchennoj v obolochku iz nerzhaveyushchej stali, i Sudet pererabatyvat'sya posredstvom protsessa head-end, kotoryj budet vveden na zavode po otdeleniyu okisi magniya v Uindskejle . Obogashchennyj uran dlya ehtogo reaktora proizvoditsya v Soedinennom Korolevstve. Diffuzionnyj zavod nakhoditsya v Kapenkherste. Al'ternativoj dlya obogashchennoj okisi urana v kachestve topliva yavlyaetsya plutonij, obogashchennyj okis'yu prirodnogo urana. V doklade soderzhitsya opisanie opyta po proizvodstvu okisi, yavlyayushchejsya toplivom dlya usovershenstvovannogo reaktora s gazovym okhlazhdeniem, ehkspluatatsionnogo opyta raboty na reaktore, poluchennogo do oikh por, i planov po pererabotke topliva. Rassmatrivaetsya vopros ob al'ternativnom ispol'zovanii plutonievogo topliva i ego vliyanii na stoimost' i toplivnyj tsikl. Nakonets, v doklade ukazyvaetsya mesto reaktora ''Magnoks'' i usovershenstvovannykh reaktorov AGR v ehnergeticheskoj programme Soedinennogo Korolevstva. (author)}
place = {IAEA}
year = {1963}
month = {Oct}
}