In-core fuel performance and material characterization in the Halden reactor

Nieuwenhove, R. Van; Solstad, S.

doi:10.1109/animma.2009.5503800

Cited by 4 publications

(2 citation statements)

References 3 publications

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“…Tungsten-rhenium thermocouples have demonstrated survivability at up to 2100 • C while experiencing transmutation decalibration [5]. LVDT affords indirect temperature measurement by tracking the thermal expansion of a rod connected to the LVDT core [6]. Because the LVDT must be positioned close to the point of measurement, its measurement range is constrained by coil oxidation, coil insulation degradation, and the Curie temperature of the LVDT core [7].…”

Section: Introductionmentioning

confidence: 99%

Magnetostrictive Ultrasonic Waveguide Transducer for In-Pile Thermometry

Keller

Robinson

Draper

et al. 2022

IEEE/ASME Trans. Mechatron.

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Section: Introductionmentioning

confidence: 99%

Magnetostrictive Ultrasonic Waveguide Transducer for In-Pile Thermometry

Keller

Robinson

Draper

et al. 2022

IEEE/ASME Trans. Mechatron.

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“…As discussed in [1][2][3][4][5][6][7][8][9][10][11][12][13][14][15][16][17] have deployed creep test rigs to detect the growth of tensile and creep specimens using a bellows to apply a variable load to a specimen and LVDTs to detect the growth of the specimen. In table 1, we compare aspects of these various creep test setups.…”

Section: Introductionmentioning

confidence: 99%

Linear variable differential transformer (LVDT)-based elongation measurements in Advanced Test Reactor high temperature irradiation testing

Knudson¹,

Rempe

2012

Meas. Sci. Technol.

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New materials are being considered for fuel, cladding and structures in next generation and existing nuclear reactors. These materials can undergo significant dimensional and physical changes during high temperature irradiations. Currently, such changes are determined by repeatedly irradiating a specimen for a specified period of time in the Advanced Test Reactor (ATR) and then removing it from the reactor for evaluation. The labor and time to remove, examine and return irradiated samples for each measurement make this approach very expensive. In addition, such techniques provide limited data and may disturb the phenomena of interest. To resolve these issues, an instrumented creep testing capability is being developed for specimens irradiated under pressurized water reactor coolant conditions in the ATR at the Idaho National Laboratory (INL). This paper reports the status of INL efforts to develop this testing capability. In addition to providing an overview of in-pile creep test capabilities available at other test reactors, this paper focuses on efforts to design and evaluate a prototype test rig in an autoclave at

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Reactivity Initiated Accident transient testing on irradiated fuel rods in PWR conditions: The CABRI International Program

Biard

Chevalier

Gaillard

et al. 2020

Annals of Nuclear Energy

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The CABRI International Program (CIP) tests irradiated UO2 or MOX fuels submitted to Reactivity Initiated Accidents (RIA) representative power pulses in prototypical PWR thermal-hydraulic conditions. CIP is managed by The Institut de Radioprotection et de Sûreté Nucléaire (IRSN) within a OECD/NEA framework. Experiments are conducted in the CABRI reactor operated by CEA. For CIP, CABRI benefits from a new pressurized water loop. An important refurbishment program enhanced the facility safety and upgraded the experimental equipment such as the nondestructive examination bench IRIS and the Hodoscope on-line fuel motion monitoring system. Specific test devices with appropriate innovative instrumentation follow the test rod behavior during the transient.The successful first test in the pressurized water loop demonstrated the CABRI capability to perform fully instrumented RIA tests in PWR conditions and to provide highly valuable results for RIA phenomena modelling (boiling crisis, post-failure events), for code validation, and for assessing PWR safety criteria. Highlights• The CABRI international Program (CIP) tests industrial irradiated fuel rods in a circulating test loop ensuring prototypical PWR conditions.• The CABRI reactor provides experimental conditions and power pulses representative of PWR RIA transients.• A complete instrumentation is available: online fuel motion monitoring system (Hodoscope), instrumented test device, pre-test and post-test non-destructive examination (IRIS).• Results will help modelling, code qualification and validation, and provide a new technical basis for PWR fuel safety criteria assessment for RIA conditions.

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In-core fuel performance and material characterization in the Halden reactor

Cited by 4 publications

References 3 publications

Magnetostrictive Ultrasonic Waveguide Transducer for In-Pile Thermometry

Magnetostrictive Ultrasonic Waveguide Transducer for In-Pile Thermometry

Linear variable differential transformer (LVDT)-based elongation measurements in Advanced Test Reactor high temperature irradiation testing

Reactivity Initiated Accident transient testing on irradiated fuel rods in PWR conditions: The CABRI International Program

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