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Behaviour and Chemical State of Irradiated Ceramic Fuels BEHAVIOUR AND CHEMICAL STATE OF IRRADIATED CERAMIC FUELS INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA, 1974 BEHAVIOUR AND CHEMICAL STATE OF IRRADIATED CERAMIC FUELS The following States are Members of the International Atomic Energy Agency: AFGHANISTAN HAITI PAKISTAN ALBANIA HOLY SEE PANAMA ALGERIA HUNGARY PARAGUAY ARGENTINA ICELAND PERU AUSTRALIA INDIA PHILIPPINES AUSTRIA INDONESIA POLAND BANGLADESH IRAN PORTUGAL -BELGIUM IRAQ ROMANIA BOLIVIA IRELAND SAUDI ARABIA BRAZIL ISRAEL SENEGAL BULGARIA ITALY SIERRA LEONE BURMA IVORY COAST SINGAPORE BYELORUSSIAN SOVIET JAMAICA SOUTH AFRICA SOCIALIST REPUBLIC JAPAN SPAIN CAMEROON JORDAN SRI LANKA CANADA KENYA SUDAN CHILE KHMER REPUBLIC . SWEDEN COLOMBIA KOREA, REPUBLIC OF SWITZERLAND COSTA RICA KUWAIT SYRIAN ARAB REPUBLIC CUBA LEBANON THAILAND CYPRUS LIBERIA TUNISIA CZECHOSLOVAK SOCIALIST LIBYAN ARAB REPUBLIC TURKEY REPUBLIC LIECHTENSTEIN UGANDA DENMARK LUXEMBOURG UKRAINIAN SOVIET SOCIALIST DOMINICAN REPUBLIC MADAGASCAR REPUBLIC ECUADOR MALAYSIA UNION OF SOVIET SOCIALIST EGYPT, ARAB REPUBLIC OF MALI REPUBLICS EL SALVADOR MEXICO UNITED KINGDOM OF GREAT ETHIOPIA MONACO BRITAIN AND NORTHERN FINLAND MONGOLIA IRELAND FRANCE MOROCCO UNITED STATES OF AMERICA GABON NETHERLANDS URUGUAY GERMAN DEMOCRATIC REPUBLIC NEW ZEALAND VENEZUELA GERMANY, FEDERAL REPUBLIC OF NIGER VIET-NAM GHANA NIGERIA YUGOSLAVIA GREECE NORWAY ZAIRE, REPUBLIC OF GUATEMALA ZAMBIA The Agency's Statute was approved on 23 October 1956 by the Conference on die Statute of the IAEA held at United Nations Headquarters, Mew York; it entered into force on 29 Iuly 1957, The Headquarters of the Agency are situated in Vienna. Its principal objective is "to accelerate and enlarge the contribution of atom ic energy to peace, health and prosperity throughout the world". © IAEA, 1974 Permission to reproduce or translate the information contained in this publication may be obtained by writing to the International Atomic Energy Agency, Kärntner Ring 11, P.O. Box 590, A-1011 Vienna, Austria. Printed by the IAEA in Austria January 1974 PANEL PROCEEDINGS SERIES BEHAVIOUR AND CHEMICAL STATE OF IRRADIATED CERAMIC FUELS PROCEEDINGS OF A PANEL ON THE BEHAVIOUR AND CHEMICAL STATE OF IRRADIATED CERAMIC FUELS ORGANIZED BY THE INTERNATIONAL ATOMIC ENERGY AGENCY AND HELD IN VIENNA, 7-11.AUGUST 1972 INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA, 1974 BEHAVIOUR AND CHEMICAL STATE OF IRRADIATED CERAMIC FUELS IAEA, VIENNA, 1974 STI/PUB/303 FOREWORD The economic attractiveness of large nuclear power reactors is criti­ cally dependent on overall fuel performance and fuel life. The successful design of high performance, long-lived fuel elements is itself dependent on a thorough understanding of the special chemical and physical behaviour of irradiated fuel. The transformation of some of the original actinide elements into new species, the effects of fission products, the progressive alteration in the stoichiometry within the fuel, and the effects of oxygen on fuel and cladding are among the many important problems that must be in­ vestigated when developing a successful fuel. Extensive studies are under­ way on mixed urania-plutonia fuel systems, developed for fast breeder reactors, and on other advanced fuels. To review the progress and problems in this field, the International Atomic Energy Agency convened a panel of experts at its Headquarters in Vienna on 7 - 11 August 1972. The deliberations of the Panel, which was composed of 19 experts from seven countries and EURATOM, covered many aspects of transport properties, fuel/fission product-clad interaction, and the thermodynamics and phase equilibria of nuclear fuel m aterials. These Proceedings contain the texts of the 30 working papers con­ sidered by the Panel and the Panel's Summary and Recommendations. CONTENTS Stoichiometric effects in irradiated uranium-plutonium oxide fuel (IA E A -PL -463/1) ................................................................................... 1 C. E. Johnson, I. Johnson,. P. Blackburn, J .E . Battles, C .E . Crouthamel The composition and chemical state of irradiated oxide reactor fuel material (IAEA-PL-463/2) ............. ................................................. 31 J. R. Findlay Redistribution of uranium and plutonium in mixed-oxide fuels during irradiation (IA E A -PL -463/3) ...................................................... 41 D .R . O'Boyle, R .O . Meyer Determination du taux de combustion et de la composition en isotopes lourds et en produits de fission des combustibles des réacteurs thermiques et rapides (IA EA -PL-463/4a) ................ 67 R. Vidal, M. Robin, C. Devillers Désaccord entre les rendements de fission théorique et experimental des gaz nobles en neutrons rapides — Mise en évidence sur le combustible du réacteur RAPSODIE (IAEA- PL-463 / 4b) .................................V..................................................... 77 B. K r y g e r Oxygen redistribution in LMFBR fuels (IA E A -P L -463/5) .................... 83 S. K. Evans, E .A . Aitken Modification du potentiel d'oxydation des oxydes mixtes (U, Pu)02, en fonction du taux de combustion (IA E A -PL-463/6a) .................... 87 F. Schmitz, J. Marticorena, G. Dean Evolution de l'activité du carbone en fonction du taux de combustion dans un combustible carbure (IAEA-PL-463/6b) ......... 99 Nicole L o r e n z e 11 i , J .P . Marcon Some phase equilibria and thermodynamic considerations for irradiated oxide nuclear fuels (IAEA-PL-463/7)................................ 115 P. E. Potter Formation of phases and distribution of fission products in an oxide fuel (IA E A -P L -463/8) ................................................................. 157 H. Kleykamp Microanalyse X d'oxyde (U, Pu)02+x simulant différents taux d'irradiation (IA E A -PL-463/9a) ............................................................... 167 F. de Keroulas, D. Calais, F. Schmitz Migration des produits de fission radioactifs dans des combustibles (U, Pu)02 (IAEA-PL-463/9b) ......................................... 179 M. Mouchnino Distribution des produits de fission et localisation par spectrométrie gamma en cours d'irradiation et après irradiation (IAEA- PL-463 /9c) ......................................................................................... 191 G. de Contenson, J. Monier, Nicole V i gn e s ou 11 Analyse à la microsonde de produits de fission métalliques dans les combustibles en géométrie eau ordinaire fonctionnant avec une zone fondue (IA E A -PL-463/9d) .............................................. 201 J. Bazin, M. Perrot, Nicole V i gn.e s о u lt The migration of fission products through reactor fuel materials (IA E A -PL-463/10) .................................................................... 211 J .R . Findlay Contribution to the studies of the fission gases released from irradiated uranium oxide pellets (IAEA-PL-463/11 ) ................. 221 J. Klima, M. Podest, V. Vins Pu, U redistribution in (U, Pu)02 fuels by temperature gradients (IAEA-PL-463/12) ..................................................................... 225 M. G. Adamson, E. A. Ait ken Chemical interactions of fission products with stainless steel claddings (IAEA-PL-463/14) ..................................................................... 237 P. Hofmann, O. Gôtzmann Fuel/cladding compatibility of stainless steels with gas and sodium-bonded uranium plutonium carbide fuels (IAEA- PL -463/15) ......................................................................................... 255 O. Götzmann, R. W. Ohse Out-of-pile investigations of fission product-cladding reactions in fast reactor fuel pins (IAEA-PL-463/16) ......................................... 269 E. A. Aitken, S. K. Evans, B. F. Rubin Réaction à l'interface gaine (acier inoxydable )/combustible (oxyde mixte (U,Pu)02±x) dans les éléments combustibles irradiés en neutrons rapides (1AEA-PL-463/17) .................... ' ......... 287 D. Calais, M. Conte, F. de Keroulas, R. Le Beuze The role of caesium in chemical interaction of austenitic stainless steels with uranium plutonium oxide fuels (IA E A -PL -463/18) ......................................................................................... 299 R. W. Ohse, M. Schlechter Mise en évidence de la migration de l'oxygène sous irradiation: Irradiation L-l (IAEA-PL-463/l9a) ....................................... .............. 315 M. Trotabas, F. de Keroulas, J. P. Gatesoupe Thermodiffusion et vaporisation dans les oxydes mixtes irradiés: Evolution du rapport Pu/U + Pu (IAEA-PL-463/19b) .... 325 M. Mouchnino Emission des gaz de fission par l'oxyde d'uranium dans les éléments combustibles (IAEA-PL-463/19c) ......................................... 337 P. Chènebault, R. Delmas Réactions entre le sodium et les oxydes mixtes (IAEA- P L -4 6 3 /l9 d )......................................................................................... 349 M. Housseau, G. Dean, F. Perret Reaction behaviour of fission products in carbides (IA E A -PL-463/20) ......................................................................................... 361 H. Holleck, E. Smailos Fission product distribution in fast reactor oxide fuels (IA EA -PL-463/21) ......................................................................................... 379 H .J. Powell Reaction of sodium with uranium-plutonium oxide and uranium oxide fuels (IAEA-PL-463/22) ................................................................. 393 P. E. Blackburn Thermodynamic studies of the sodium fuel reaction at General Electric (IAEA-PL-463/23) ......................................................
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