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The Application of Non-Metallic Core Materials in a High-Temperature Reactor Experiment; Utilisation de materes non metalliques dans le coeur d'un reacteur experimental a haute temperature; Ispol'zovanie nemetallicheskikh materialov dlya aktivnoj zony vysokotemperaturnogo opytnogo reaktora; Empleo de materiales no metalicos en el nucleo de un reactor experimental de alta temperatura

Conference:

Abstract

The OECD High-Temperature Reactor Project (DRAGON) was set up to develop the technology of high-temperature gas-cooled reactors and, as part of this development, to construct and operate a 20-MW(t) reactor experiment. The reactor, which is now nearing completion, is a helium-cooled system with a coreoutlet temperature of 750{sup o}C; it employs U{sup 235} fuel with thorium as a fertile material. A particular feature of this system is the absence of any metals in the core. Because of the high temperatures involved, namely, up to 1050{sup o}C at fuel element surfaces and above, 1500{sup o}C in-the hottest regions of the fuel, refractory nonmetallic materials are employed. All the core material is incorporated within the fuel element which leads to a high ratio of heat transfer surface area to core volume and hence permits a high average power density leading to a relatively compact system. Each fuel element consists of a cluster of graphite tubes, containing the fissile and fertile materials as carbides incorporated in graphite pellets. A purge flow of the helium coolant passing through the centre of each fuel rod is extracted from the base whence it passes into a helium processing plant to remove fission products and other impurities  More>>
Authors:
Huddle, R. A.U.; Shepherd, L. R. [1] 
  1. Organization for Economic Co-Operation and Development, Dragon Project, Atomic Energy Establishment, Winfrith, Dorset (United Kingdom)
Publication Date:
Nov 15, 1963
Product Type:
Conference
Resource Relation:
Conference: Conference on New Nuclear Materials Technology, Including Non Metallic Fuel Elements, Prague (Czech Republic), 1-5 Jul 1963; Other Information: 14 figs., 6 refs.; Related Information: In: New Nuclear Materials Including Non Metallic Fuel Elements. Vol. II. Proceedings of the Conference on New Nuclear Materials Technology, Including Non Metallic Fuel Elements| 586 p.
Subject:
36 MATERIALS SCIENCE; CARBIDES; CERAMICS; FERTILE MATERIALS; FISSION PRODUCTS; FUEL RODS; FUELS; GRAPHITE; HEAT TRANSFER; HELIUM; HTGR TYPE REACTORS; IMPURITIES; IN PILE LOOPS; IRRADIATION; POWER DENSITY; REFRACTORIES; STREAMS; SURFACE AREA; SURFACES; THORIUM; URANIUM 235
OSTI ID:
22109697
Research Organizations:
International Atomic Energy Agency, Vienna (Austria)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
Other: ISSN 0074-1884; TRN: XA13R0487067342
Submitting Site:
INIS
Size:
page(s) 467-495
Announcement Date:
Jul 08, 2013

Conference:

Citation Formats

Huddle, R. A.U., and Shepherd, L. R. The Application of Non-Metallic Core Materials in a High-Temperature Reactor Experiment; Utilisation de materes non metalliques dans le coeur d'un reacteur experimental a haute temperature; Ispol'zovanie nemetallicheskikh materialov dlya aktivnoj zony vysokotemperaturnogo opytnogo reaktora; Empleo de materiales no metalicos en el nucleo de un reactor experimental de alta temperatura. IAEA: N. p., 1963. Web.
Huddle, R. A.U., & Shepherd, L. R. The Application of Non-Metallic Core Materials in a High-Temperature Reactor Experiment; Utilisation de materes non metalliques dans le coeur d'un reacteur experimental a haute temperature; Ispol'zovanie nemetallicheskikh materialov dlya aktivnoj zony vysokotemperaturnogo opytnogo reaktora; Empleo de materiales no metalicos en el nucleo de un reactor experimental de alta temperatura. IAEA.
Huddle, R. A.U., and Shepherd, L. R. 1963. "The Application of Non-Metallic Core Materials in a High-Temperature Reactor Experiment; Utilisation de materes non metalliques dans le coeur d'un reacteur experimental a haute temperature; Ispol'zovanie nemetallicheskikh materialov dlya aktivnoj zony vysokotemperaturnogo opytnogo reaktora; Empleo de materiales no metalicos en el nucleo de un reactor experimental de alta temperatura." IAEA.
@misc{etde_22109697,
title = {The Application of Non-Metallic Core Materials in a High-Temperature Reactor Experiment; Utilisation de materes non metalliques dans le coeur d'un reacteur experimental a haute temperature; Ispol'zovanie nemetallicheskikh materialov dlya aktivnoj zony vysokotemperaturnogo opytnogo reaktora; Empleo de materiales no metalicos en el nucleo de un reactor experimental de alta temperatura}
author = {Huddle, R. A.U., and Shepherd, L. R.}
abstractNote = {The OECD High-Temperature Reactor Project (DRAGON) was set up to develop the technology of high-temperature gas-cooled reactors and, as part of this development, to construct and operate a 20-MW(t) reactor experiment. The reactor, which is now nearing completion, is a helium-cooled system with a coreoutlet temperature of 750{sup o}C; it employs U{sup 235} fuel with thorium as a fertile material. A particular feature of this system is the absence of any metals in the core. Because of the high temperatures involved, namely, up to 1050{sup o}C at fuel element surfaces and above, 1500{sup o}C in-the hottest regions of the fuel, refractory nonmetallic materials are employed. All the core material is incorporated within the fuel element which leads to a high ratio of heat transfer surface area to core volume and hence permits a high average power density leading to a relatively compact system. Each fuel element consists of a cluster of graphite tubes, containing the fissile and fertile materials as carbides incorporated in graphite pellets. A purge flow of the helium coolant passing through the centre of each fuel rod is extracted from the base whence it passes into a helium processing plant to remove fission products and other impurities before being returned to the reactor. This procedure reduces the escape of fission products from the very hot ceramic fuel into the primary coolant stream. Problems associated with the development and production of ceramic fuel bodies and graphite for this reactor, and the behaviour of these materials under operating conditions are outlined. Some experience from irradiation and in-pile loop investigations are reported. The main emphasis in this programme is on the development of the high-temperature gas-cooled reactor for application as an economic power producing system. (author) [French] Les objectifs du Projet DRAGON de l'OCDE (reacteur a haute temperature) sont les suivants: ameliorer la technologie des reacteurs a haute temperature refroidis par un gaz, construire et exploiter, dans le cadre de ce projet, un reacteur experimental de 20 MWth. Le reacteur - dont la construction touche a sa fin - est refroidi a l'helium; la temperature de sortie du coeur est de 750{sup o}C; il emploie de l'uranium-235 comme combustible et du thorium comme matiere fertile. Il est caracterise par l'absence de tout metal dans le coeur du reacteur. En raison'des hautes temperatures, qui peuvent atteindre 1050{sup o}C a la surface des elements combustibles et s'elever au dessus de 1500{sup o}C dans les regions les plus chaudes du combustible, on emploie des materiaux refractaires non metalliques. Le fait que tous les constituants du coeur sont reunis dans l'element combustible permet d'obtenir un rapport eleve entre la surface de transfert de la chaleur et le volume du coeur, d'ou une puissance specifique moyenne elevee pour un ensemble de dimension relativement faible. Chaque element combustible est constitue par un faisceau de tubes de graphite contenant les matieres fissiles et fertiles sous forme de carbure incorpore a des pastilles de graphite. Un courant refroidisseur d'helium traverse le centre de chaque barreau de combustible d'ou il ressort par la base pour etre conduit dans une installation de purification dans laquelle il est debarrasse des produits de fission et autres impuretes avant d'etre achemine de nouveau vers le reacteur. Cette methode permet de reduire la fuite des produits de fission qui, s'echappant du combustible ceramique porte a tres haute temperature, entrent dans le circuit de refroidissement primaire. Les auteurs exposent les problemes lies a la mise au point et a la fabrication du graphite et des elements combustibles ceramiques destines a ce reacteur ainsi que le comportement de ces materiaux dans les conditions de fonctionnement. Ils indiquent les resultats de recherches en pile et dans des boucles d'irradiation. Dans ce programme, tout l'effort se concentre sur la mise au point de reacteurs a haute temperature refroidis par un gaz, qui soient rentables pour la production d'electricite. (author) [Spanish] El proyecto DRAGON de la O.C.F.E., relativo a un reactor de alta temperatura, se emprendio con el fin de perfeccionar la tecnologia de esa categoria de reactores refrigerados por gas y, como parte de esta labor, con objeto de construir y explotar un reactor experimental de 20 MW (t). El reactor, cuya construccion esta por terminarse, es del tipo refrigerado por helio, con una temperatura de salida del nucleo de 750{sup o}C; como combustible se utiliza {sup 235}U y torio como materiaj fertil. Una particularidad de este reactor es la ausencia de materiales metalicos en su nucleo. En razon de la elevada temperatura de funcionamiento, a saber, hasta 1050{sup o}C en la superficie de los elementos combustibles y superior a 1500{sup o}C en las regiones mas calientes de los mismos se utilizan meteriales refractarios no metalicos. Todos los materiales del nucleo se hallan incorporados en los elementos combustibles, lo que permite alcanzar una amplia superficie de transmision de calor en relacion con el volumen del nucleo y, por tanto, una potencia especifica media elevada que hace posible reducir las dimensiones del sistema. Cada elemento combustible esta formado-por un haz-de tubos de grafito que contienen los materiales fisionables y fertiles en forma de carburos incorporados en pastillas de grafito. Una corriente purgadora de helio refrigerante que atraviesa la zona-central de cada barra de combustible es extraida por la base, desde donde pasa a una instalacion de tratamiento para eliminar los productos de fision y otras impurezas antes de retornar el helio al reactor. Por este procedimiento se reduce el escape de productos de fision del combustible ceramico, cuya temperatura es muy elevada, al circuito primario de refrigeracion. Se exponen los problemas inherentes al estudio y produccion de combustibles ceramicos y de grafito para este reactor, asi como al comportamiento de estos materiales en condiciones de funcionamiento normales. Se comunican los resultados de las investigaciones sobre irradiacion, asi como de los trabajos efectuados en los circuitos del reactor. El objetivo principal de este programa es el perfeccionamiento de los reactores de elevada temperatura refrigerados por gas para aplicarlos a la generacion de electricidad en condiciones rentables. (author) [Russian] Proekt vysokotemperaturnogo reaktora (DRAGON)sozdan dlya razrabotki tekhnologii vysokotemperaturnykh reaktorov s gazovym okhladitelem; v nem predusmatrivalos' sooruzhenie i ehkspluatatsiya opytnogo reaktora na 20 mgvt (tepl.). Reaktor, sooruzhenie kotorogo budet vskore zakoncheno, predstavlyaet soboj sistemu, okhlazhdaemuyu geliem; temperatura na vykhode iz aktivnoj zony budet dostigat' 750{sup o}C. V nem budet ispol'zovat'sya U-235 v kachestve goryuchego i torij v kachestve vosproizvodyashchego materiala. Kharakternoj osobennost'yu sistemy yavlyaetsya otsutstvie kakogo-libo metalla v aktivnoj zone. Vvidu togo, chto v reaktore dolzhny razvivat'sya ves'ma vysokie temperatury,' a imenno, 1050{sup o}C na poverkhnosti teplovydelyayushchego ehlementa i do 1500{sup o}C v naibolee sil'no nagrevaemykh tochkakh topliva, dlya ego sooruzheniya ispol'zovany ogneupornye nemetallicheskie materialy. Vse veshchestvo aktivnoj zony sosredotocheno v teplovydelyayushchem ehlemente, blagodarya chemu sootnoshenie mezhdu poverkhnost'yu teploperedachi i ob{sup e}mom aktivnoj zony dostigaet bol'shogo znacheniya, i, sledovatel'no, pozvolyaet dostigat' vysokoj srednej plotnosti ehnergii v sravnitel'no kompaktnoj sisteme. Kazhdyj teplovydelyayushchij ehlement sostoit ieh gruppy grafitovykh trubok, zapolnennykh grafitovymi tabletkami, soderzhashchimi rasshcheplyayushcheesya i vosproizvodyashchee veshchestva v vide karbidov. Gelievyj okhladitel' prokhodit po osi. kazhdogo teplovydelyayushchego sterzhnya i vyvoditsya u ego osnovaniya, okhladitel' zatem napravlyaetsya v ochistitel'nuyu ustanovku, gde iz nego udalyayutsya produkty deleniya i drugie primesi, posle chego tsikl povtoryaetsya. Takaya protsedura pozvolyaet snizit' popadanie produktov deleniya ieh sil'no nagretogo keramicheskogo topliva v pervichnyj potok okhladitelya. (author)}
place = {IAEA}
year = {1963}
month = {Nov}
}