Full-core uncertainty analysis of nuclear fuel behavior

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

Abstract

Fuel performance analysis can be usedto show compliance with regulatory criteria, such as criteria related to fuel melting, rod internal pressure and cladding stresses and strains. A nuclear reactor core contains typically tens of thousands fuel rods in hundreds of fuel assemblies, and each rod experiences different generated power and coolant conditions during its irradiation. Therefore fuel performance analysis must be performed on each rod separately, resulting in tens of thousands of simulation runs.Additionally, the manufacturing parameters of the fuel rods, fuel performance code model parameters and even the determined power are fundamentally uncertain: they are not single, exact values but rather their true nature can be approximated with statistical distributions. Therefore also the results are distributions of values and not exact. Parameters of these distributions must be compared to regulatory criteria, and as a conservative approach some limiting values can be established which can be used to show whether a regulatory criteria is exceeded or not. A method widely in use in the nuclear industryis based on order statistics, and can be used to show that the 0.95-content tolerance interval with 95 % probability does not exceed the examined criterion.In this work a method applicable forfull-core fuel performance analysis is demonstrated with a calculation of a PWR 17x17 assembly. Fuel performance parameters such as maximum temperature, pressure and cladding stress are investigated.
Original languageEnglish
Title of host publicationSYP2019 Proceedings
PublisherFinnish Nuclear Society
Number of pages4
Publication statusPublished - 31 Oct 2019
MoE publication typeNot Eligible
EventNuclear Science and Technology Symposium, NST 2019 - Helsinki, Finland
Duration: 20 Oct 201931 Oct 2019

Conference

ConferenceNuclear Science and Technology Symposium, NST 2019
Abbreviated titleNST 2019
CountryFinland
CityHelsinki
Period20/10/1931/10/19

Fingerprint

Uncertainty analysis
Nuclear fuels
Reactor cores
Coolants
Melting
Statistics
Irradiation

Cite this

Loukusa, H. (2019). Full-core uncertainty analysis of nuclear fuel behavior. In SYP2019 Proceedings Finnish Nuclear Society.
Loukusa, Henri. / Full-core uncertainty analysis of nuclear fuel behavior. SYP2019 Proceedings. Finnish Nuclear Society, 2019.
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Loukusa, H 2019, Full-core uncertainty analysis of nuclear fuel behavior. in SYP2019 Proceedings. Finnish Nuclear Society, Nuclear Science and Technology Symposium, NST 2019, Helsinki, Finland, 20/10/19.

Full-core uncertainty analysis of nuclear fuel behavior. / Loukusa, Henri.

SYP2019 Proceedings. Finnish Nuclear Society, 2019.

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

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Loukusa H. Full-core uncertainty analysis of nuclear fuel behavior. In SYP2019 Proceedings. Finnish Nuclear Society. 2019