Post-irradiation examination of overheated canflex bundles


Book Description

Five canflex fuel bundles were irradiated in the u2 loop in nru during 1990. the 43-element bundles contained two element sizes: 11.5 mm diameter elements with 0.33 mm thin-wall zr-4 cladding in the outer and intermediate rings, and 13.5 mm diameter elements with 0.35 mm thin-wall cladding in the inner ring. three bundles contained uo2 enriched to 2.59% u-235 in u, and two contained natural uo2 in the intermediate and outer ring of elements, with 2.59% enriched uo2 in the inner ring. the bundles overheated when, due to loss of class iv electrical power to the main loop pumps, the coolant flow stagnated briefly in the down leg of the u loop, then reversed direction as convective cooling was established. although the bundle power decayed rapidly after the reactor tripped due to the loss of electrical power, the stored energy and decay heat were sufficient to cause overheating of the bundles during the brief stagnation period, and this in turn led to steam generation which resulted in high coolant pressure (sheath temperature in excess of 600 degrees c and coolant pressure above 11.2 mpa). post-irradiation examinations revealed that the sheath in some elements had collapsed into the gaps between the pellet stack and end caps, and between adjacent pellets; however, no defects were attributed to sheath collapse. two of the elements had defects due to hydride blisters, but the source of the hydrogen was not from a breach in the cladding or end caps. the defects were attributed to primary hydriding. the results show that even though the bundles were subjected to abnormally high temperatures and pressures, and were damaged as a result, none of the collapsed elements leaked. this indicates that thin-wall cladding provides a significant margin of safety during transient high temperature and pressure excursions.







Information Digest


Book Description




Reverse Osmosis and Nanofiltration


Book Description

This book explains the processes of membrane technologies applications, used in the treatment of water sources and by medical professionals for kidney dialysis, and is a helpful research tool for engineers, scientists, administrators, and educators seeking an introduction to these processes. Covers history and theory, design and equipment, regulations, and more.




IAEA Safety Glossary


Book Description

The IAEA Safety Glossary defines and explains technical terms used in the IAEA Safety Standards and other safety related IAEA publications, and provides information on their usage. The 2018 Edition of the IAEA Safety Glossary is a new edition of the IAEA Safety Glossary, originally issued in 2007. It has been revised and updated to take into account new terminology and usage in safety standards issued between 2007 and 2018. The revisions and updates reflect developments in the technical areas of application of the safety standards and changes in regulatory approaches in Member States.




Modelling of Fuel Behaviour in Design Basis Accidents and Design Extension Conditions


Book Description

This publication is the result of an IAEA technical meeting and reports on Member States' capabilities in modelling, predicting and improving their understanding of the behaviour of nuclear fuel under accident conditions. The main results and outcomes of a coordinated research project (CRP) on this topic are also presented.