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Water reactor fuel element modelling at high burnup and its experimental support. Proceedings of a technical committee meeting

Abstract

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.
Publication Date:
Aug 01, 1997
Product Type:
Technical Report
Report Number:
IAEA-TECDOC-957; CONF-9409411-
Reference Number:
SCA: 220300; PA: AIX-28:068338; EDB-98:023990; NTS-98:006454; SN: 97001862992
Resource Relation:
Conference: IAEA technical committee meeting on water reactor fuel element modelling at high burnup and its experimental support, Windermere (United Kingdom), 19-23 Sep 1994; Other Information: PBD: Aug 1997
Subject:
22 NUCLEAR REACTOR TECHNOLOGY; FUEL ELEMENTS; SIMULATION; BURNUP; ECONOMICS; EXPERIMENTAL DATA; FUEL ELEMENT CLUSTERS; HEAVY WATER COOLED REACTORS; IAEA; INTERNATIONAL COOPERATION; LEADING ABSTRACT; MEMBER STATES; SAFETY; TECHNOLOGY TRANSFER; THEORETICAL DATA; MEETINGS
OSTI ID:
575591
Research Organizations:
International Atomic Energy Agency, Vienna (Austria)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
Journal ID: ISSN 1011-4289; Other: ON: DE98602336; TRN: XA9744786068338
Availability:
INIS; OSTI as DE98602336
Submitting Site:
INIS
Size:
559 p.
Announcement Date:
Mar 25, 1998

Citation Formats

None. Water reactor fuel element modelling at high burnup and its experimental support. Proceedings of a technical committee meeting. IAEA: N. p., 1997. Web.
None. Water reactor fuel element modelling at high burnup and its experimental support. Proceedings of a technical committee meeting. IAEA.
None. 1997. "Water reactor fuel element modelling at high burnup and its experimental support. Proceedings of a technical committee meeting." IAEA.
@misc{etde_575591,
title = {Water reactor fuel element modelling at high burnup and its experimental support. Proceedings of a technical committee meeting}
author = {None}
abstractNote = {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.}
place = {IAEA}
year = {1997}
month = {Aug}
}