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Fuel operational limits based on Studsvik international projects data

N. Kjær-Pedersen

Open publisher page 2 citations

Abstract

Over the past 10 yr, several experimental projects have been performed at the Swedish R2 test reactor in Studsvik, under joint international sponsorship, to investigate the failure propensity of light water reactor fuel due to pellet/cladding interaction. Experimental data have been obtained by subjecting preirradiated fuel rod segments to overpower tests (ramp tests). This paper evaluates major findings from the projects Inter-Ramp (IR), Over-Ramp (OR) and Super-Ramp (SR). IR addressed boiling water reactor (BWR) fuel performance at low medium burnup; OR, pressurized water reactor (PWR) fuel performance at medium burnup; SR, the high-burnup performance of both fuel types. An integrated analysis of all the failure data from one-step fast ramp tests from the three programs has been performed to identify any overall trends within the total data base relative to design and operational variables as well as burnup.

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What this paper is about

Over the past 10 yr, several experimental projects have been performed at the Swedish R2 test reactor in Studsvik, under joint international sponsorship, to investigate the failure propensity of light water reactor fuel due to pellet/cladding interaction. Experimental data have been obtained by subjecting preirradiated fuel rod segments to overpower tests (ramp tests). This paper evaluates major findings from the projects Inter-Ramp (IR), Over-Ramp (OR) and Super-Ramp (SR). IR addressed boiling water reactor (BWR) fuel performance at low medium burnup; OR, pressurized water reactor (PWR) fuel performance at medium burnup; SR, the high-burnup performance of both fuel types. An integrated analysis of all the failure data from one-step fast ramp tests from the three programs has been performed to identify any overall trends within the total data base relative to design and operational variables as well as burnup.

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Available abstract

Over the past 10 yr, several experimental projects have been performed at the Swedish R2 test reactor in Studsvik, under joint international sponsorship, to investigate the failure propensity of light water reactor fuel due to pellet/cladding interaction. Experimental data have been obtained by subjecting preirradiated fuel rod segments to overpower tests (ramp tests). This paper evaluates major findings from the projects Inter-Ramp (IR), Over-Ramp (OR) and Super-Ramp (SR). IR addressed boiling water reactor (BWR) fuel performance at low medium burnup; OR, pressurized water reactor (PWR) fuel performance at medium burnup; SR, the high-burnup performance of both fuel types. An integrated analysis of all the failure data from one-step fast ramp tests from the three programs has been performed to identify any overall trends within the total data base relative to design and operational variables as well as burnup.

Key concepts: Burnup, Boiling water reactor, Nuclear engineering, Cladding (metalworking), Pressurized water reactor, Environmental science, Light-water reactor, Spent nuclear fuel

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