Modelling design basis accidents LOCA and RIA from the perspective of single fuel rods

Dissertation

Research output: ThesisDissertationCollection of Articles

Abstract

When designing a nuclear power plant and its fuel, certain accidents are postulated to occur with a predetermined low frequency. The consequences of these accidents are mitigated by various passive and active safety features, and an adequate safety level is implemented by the regulatory authority in the safety requirements.
The dissertation considers computational modelling of two main design basis accidents in current light water reactors: loss-of-coolant accident (abbreviated LOCA) and reactivity initiated accident (RIA). The applied computer programmes are designed for modelling the behaviour of a single fuel rod in transient and accident conditions.
LOCA modelling is focused on developing a statistical analysis methodology for the evaluation of fuel failures in LOCA. The statistical system is applied to a large break LOCA in an EPR type reactor, and fulfilment of the regulations included in the Regulatory Guides on nuclear safety set by the Finnish nuclear safety authority STUK is studied. In order to determine the underlyingfactors affecting the fuel rod failures, a sensitivity analysis is performed. A systematic multistage procedure is developed for the sensitivity analysis.
RIA modelling focuses on adaptation of the single rod RIA modelling code SCANAIR for boiling water reactor (BWR) conditions. The SCANAIR code, developed by the French research organisation Institut de Radioprotection et de Sûreté Nucléaire (IRSN), is specifically designed for modelling RIAs in pressurized water reactors (PWRs). In this dissertation, the code is adapted totake into account BWR specific properties and conditions.
Original languageEnglish
QualificationDoctor Degree
Awarding Institution
  • Aalto University
Supervisors/Advisors
  • Tuomisto, Filip, Supervisor, External person
  • Hämäläinen, Anitta, Advisor
Award date8 Mar 2018
Place of PublicationHelsinki
Publisher
Print ISBNs978-952-60-7846-5, 978-951-38-8617-2
Electronic ISBNs978-952-60-7847-2, 978-951-38-8616-5
Publication statusPublished - 2018
MoE publication typeG5 Doctoral dissertation (article)

Fingerprint

Loss of coolant accidents
Accidents
Boiling water reactors
Sensitivity analysis
Light water reactors
Pressurized water reactors
Nuclear power plants
Paramagnetic resonance
Computer program listings
Statistical methods

Keywords

  • loss-of-coolant accident
  • reactivity initiated accident
  • fuel rod modelling

Cite this

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title = "Modelling design basis accidents LOCA and RIA from the perspective of single fuel rods: Dissertation",
abstract = "When designing a nuclear power plant and its fuel, certain accidents are postulated to occur with a predetermined low frequency. The consequences of these accidents are mitigated by various passive and active safety features, and an adequate safety level is implemented by the regulatory authority in the safety requirements.The dissertation considers computational modelling of two main design basis accidents in current light water reactors: loss-of-coolant accident (abbreviated LOCA) and reactivity initiated accident (RIA). The applied computer programmes are designed for modelling the behaviour of a single fuel rod in transient and accident conditions.LOCA modelling is focused on developing a statistical analysis methodology for the evaluation of fuel failures in LOCA. The statistical system is applied to a large break LOCA in an EPR type reactor, and fulfilment of the regulations included in the Regulatory Guides on nuclear safety set by the Finnish nuclear safety authority STUK is studied. In order to determine the underlyingfactors affecting the fuel rod failures, a sensitivity analysis is performed. A systematic multistage procedure is developed for the sensitivity analysis.RIA modelling focuses on adaptation of the single rod RIA modelling code SCANAIR for boiling water reactor (BWR) conditions. The SCANAIR code, developed by the French research organisation Institut de Radioprotection et de S{\^u}ret{\'e} Nucl{\'e}aire (IRSN), is specifically designed for modelling RIAs in pressurized water reactors (PWRs). In this dissertation, the code is adapted totake into account BWR specific properties and conditions.",
keywords = "loss-of-coolant accident, reactivity initiated accident, fuel rod modelling",
author = "Asko Arkoma",
year = "2018",
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}

Modelling design basis accidents LOCA and RIA from the perspective of single fuel rods : Dissertation. / Arkoma, Asko.

Helsinki : Aalto University, 2018. 148 p.

Research output: ThesisDissertationCollection of Articles

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T1 - Modelling design basis accidents LOCA and RIA from the perspective of single fuel rods

T2 - Dissertation

AU - Arkoma, Asko

PY - 2018

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N2 - When designing a nuclear power plant and its fuel, certain accidents are postulated to occur with a predetermined low frequency. The consequences of these accidents are mitigated by various passive and active safety features, and an adequate safety level is implemented by the regulatory authority in the safety requirements.The dissertation considers computational modelling of two main design basis accidents in current light water reactors: loss-of-coolant accident (abbreviated LOCA) and reactivity initiated accident (RIA). The applied computer programmes are designed for modelling the behaviour of a single fuel rod in transient and accident conditions.LOCA modelling is focused on developing a statistical analysis methodology for the evaluation of fuel failures in LOCA. The statistical system is applied to a large break LOCA in an EPR type reactor, and fulfilment of the regulations included in the Regulatory Guides on nuclear safety set by the Finnish nuclear safety authority STUK is studied. In order to determine the underlyingfactors affecting the fuel rod failures, a sensitivity analysis is performed. A systematic multistage procedure is developed for the sensitivity analysis.RIA modelling focuses on adaptation of the single rod RIA modelling code SCANAIR for boiling water reactor (BWR) conditions. The SCANAIR code, developed by the French research organisation Institut de Radioprotection et de Sûreté Nucléaire (IRSN), is specifically designed for modelling RIAs in pressurized water reactors (PWRs). In this dissertation, the code is adapted totake into account BWR specific properties and conditions.

AB - When designing a nuclear power plant and its fuel, certain accidents are postulated to occur with a predetermined low frequency. The consequences of these accidents are mitigated by various passive and active safety features, and an adequate safety level is implemented by the regulatory authority in the safety requirements.The dissertation considers computational modelling of two main design basis accidents in current light water reactors: loss-of-coolant accident (abbreviated LOCA) and reactivity initiated accident (RIA). The applied computer programmes are designed for modelling the behaviour of a single fuel rod in transient and accident conditions.LOCA modelling is focused on developing a statistical analysis methodology for the evaluation of fuel failures in LOCA. The statistical system is applied to a large break LOCA in an EPR type reactor, and fulfilment of the regulations included in the Regulatory Guides on nuclear safety set by the Finnish nuclear safety authority STUK is studied. In order to determine the underlyingfactors affecting the fuel rod failures, a sensitivity analysis is performed. A systematic multistage procedure is developed for the sensitivity analysis.RIA modelling focuses on adaptation of the single rod RIA modelling code SCANAIR for boiling water reactor (BWR) conditions. The SCANAIR code, developed by the French research organisation Institut de Radioprotection et de Sûreté Nucléaire (IRSN), is specifically designed for modelling RIAs in pressurized water reactors (PWRs). In this dissertation, the code is adapted totake into account BWR specific properties and conditions.

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