Published August 1997 | Version v1
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Water reactor fuel element modelling at high burnup and its experimental support. Proceedings of a technical committee meeting

Description

The Technical Committee Meeting on Fuel Element Modelling at High Burnup and its Experimental Support was recommended by the International Working Group on Fuel Performance and Technology (IWGFPT). Its subject had been touched on in many of the IAEA's activities; however for the first time modellers and experimentalists were brought together to have an exchange of views on the research under way and to identify areas where new knowledge is necessary to improve the safety, reliability and/or economics of nuclear fuel. The timely organization of this meeting in conjunction with the second meeting of the Co-ordinated Research Programme on Fuel Modelling at Extended Burnup, in short ''FUMEX'', allowed fruitful participation of representatives of developing countries which are only rarely exposed to such a scientific event. The thirty-nine papers presented covered the status of codes and experimental facilities and the main phenomena affecting the fuel during irradiation, namely: thermal fuel performance, clad corrosion and pellet-cladding interaction (PCI) and fission gas release (FGR). Refs, figs, tabs

Availability note (English)

MF available from INIS under the Report Number.

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Additional details

Publishing Information

Imprint Pagination
559 p.
ISSN
1011-4289
Report number
IAEA-TECDOC--957

Conference

Title
Technical committee meeting on water reactor fuel element modelling at high burnup and its experimental support.
Dates
19-23 Sep 1994.
Place
Windermere (United Kingdom).

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
28068338
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Numerical Data
Is Lead record
Yes
Descriptors DEI
BURNUP; ECONOMICS; EXPERIMENTAL DATA; FUEL ELEMENT CLUSTERS; FUEL ELEMENTS; HEAVY WATER COOLED REACTORS; IAEA; INTERNATIONAL COOPERATION; LEADING ABSTRACT; MEMBER STATES; SAFETY; SIMULATION; TECHNOLOGY TRANSFER; THEORETICAL DATA; WATER COOLED REACTORS
Descriptors DEC
ABSTRACTS; COOPERATION; DATA; FUEL ASSEMBLIES; INFORMATION; INTERNATIONAL ORGANIZATIONS; NUMERICAL DATA; REACTOR COMPONENTS; REACTORS