Fuel assembly geometrical changes assessment during pool-side inspections

Kód výsledku v IS VaVaI

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Výsledek na webu

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DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

Fuel assembly geometrical changes assessment during pool-side inspections

Popis výsledku v původním jazyce

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.

Název v anglickém jazyce

Fuel assembly geometrical changes assessment during pool-side inspections

Popis výsledku anglicky

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.

Druh

D - Stať ve sborníku

CEP obor

JF - Jaderná energetika

OECD FORD obor

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Projekt

Výsledek vznikl pri realizaci vícero projektů. Více informací v záložce Projekty.

Návaznosti

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

Rok uplatnění

2016

Kód důvěrnosti údajů

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

Název statě ve sborníku

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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Počet stran výsledku

11

Strana od-do

64-74

Název nakladatele

Centrum výzkumu Řež, s.r.o.

Místo vydání

Řež

Místo konání akce

Řež

Datum konání akce

24. 11. 2016

Typ akce podle státní příslušnosti

CST - Celostátní akce

Kód UT WoS článku

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