Fuel assembly geometrical changes assessment during pool-side inspections

Result code in IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F16%3AN0000105" target="_blank" >RIV/26722445:_____/16:N0000105 - isvavai.cz</a>

Result on the web

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DOI - Digital Object Identifier

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Result language

angličtina

Original language name

Fuel assembly geometrical changes assessment during pool-side inspections

Original language description

Basic requirements on fuel system at nuclear power plants are to ensure the proper coolant flow, enable to control the reactivity and maintain the subcritical state of the core, and keep fission products within the fuel rods. These requirements are valid not only for currently used Gen II and III reactors, but also for Gen IV systems. And from these, requirements on post-irradiation inspections generally result. In case of whole fuel assembly, evaluation of its geometry changes is needed as well as the information about fuel assembly components´ and fuel rods´ state. The inspections of the irradiated fuel are intended to confirm that the fuel performs according to expectations and, if not, to determine the nature of fuel anomaly and possible remedy actions. In the rare event of fuel failure, the inspections are to provide information required for the analysis of the failure, i.e. the determination of the type of failure and root causes. Regular monitoring and systematic data collection help assessing merits and weaknesses of the fuel design and the available operational margins. Inspections also enable to detect any anomaly at an early stage, hence preventing major operational consequences. The main factors influencing fuel performance in a reactor core are the fuel assembly design, the fuel manufacturing process, the materials, the water chemistry conditions and the operating strategy. These factors and their interactions make each reactor unique. The most effective approach to assess fuel performance is to perform fuel inspections directly at the plant, regularly and systematically, and thereby building extensive fuel databases and valuable fuel performance expertise.

Czech name

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Czech description

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Type

D - Article in proceedings

CEP classification

JF - Nuclear energy

OECD FORD branch

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Project

Result was created during the realization of more than one project. More information in the Projects tab.

Continuities

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Publication year

2016

Confidentiality

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Article name in the collection

Utilization of SUSEN Technologies for the Gen IV Development

ISBN

978-80-270-0925-1

ISSN

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e-ISSN

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Number of pages

11

Pages from-to

64-74

Publisher name

Centrum výzkumu Řež, s.r.o.

Place of publication

Řež

Event location

Řež

Event date

Nov 24, 2016

Type of event by nationality

CST - Celostátní akce

UT code for WoS article

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