In-core corrosion monitoring in the Halden test reactor

Bennett, Peter; Karlsen, T. M.

doi:10.1179/174892408x394182

Cited by 10 publications

(5 citation statements)

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“…As listed in Table 3-2, a wide range of in-core instrumentation has been developed, fabricated, and used by the IFE/HRP for measuring key fuel and material performance parameters such as fuel temperature, fuel swelling / densification, fission gas release, cladding creep, corrosion/crud buildup, and crack-growth rates. [28][29][30][31][32][33][34][35] Instruments are also available for monitoring the irradiation environment (e.g. SPNDs and miniaturized gamma thermometers) and thermalhydraulic and water chemistry conditions (e.g.…”

Section: Ife/hrpmentioning

confidence: 99%

Status Report on Efforts to Enhance Instrumentation to Support Advanced Test Reactor Irradiations

Rempe¹,

Knudson²,

Daw³

et al. 2014

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The Department of Energy (DOE) designated the Advanced Test Reactor (ATR) as a National Scientific User Facility (NSUF) in April 2007 to support U.S. leadership in nuclear science and technology. By attracting new research users-universities, laboratories, and industry-the ATR NSUF facilitates basic and applied nuclear research and development, further advancing the nation's energy security needs. A key component of the ATR NSUF effort is to prove new in-pile instrumentation techniques that are capable of providing real-time measurements of key parameters during irradiation. To address this need, an assessment of instrumentation available and under-development at other test reactors was completed. Based on this review, recommendations were made with respect to what instrumentation is needed at the ATR; and a strategy was developed for obtaining these sensors. In 2009, a report was issued documenting this program's strategy and initial progress toward accomplishing program objectives. In 2009, a report was issued documenting this instrumentation development strategy and initial progress toward accomplishing instrumentation development program objectives. This document reports progress toward implementing this strategy in 2010.

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Section: Ife/hrpmentioning

confidence: 99%

Status Report on Efforts to Enhance Instrumentation to Support Advanced Test Reactor Irradiations

Rempe¹,

Knudson²,

Daw³

et al. 2014

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show abstract

“…An overview of most in-core corrosion monitoring techniques, including instruments for measuring crack growth, crack initiation, irradiation creep, irradiation creep, in-core water conductivity, fuel cladding thickness and electrochemical impedance spectroscopy has been presented elsewhere [2]. Here we will focus on the latest developments in in-core reference electrodes.…”

Section: In-pile Materials Characterizationmentioning

confidence: 99%

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

Nieuwenhove

Solstad

2009

2009 1st International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and Their Applications

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Reliable in-core instrumentation has been developed for measuring all key parameters for fuel studies such as fission gas release, fuel temperature, fuel swelling, cladding creep, etc. For material corrosion studies, new electrochemical sensors have been developed, allowing performing in-pile electrochemical impedance spectroscopy. A prototype in-core eddy current based probe has been developed for measuring the oxide thickness on fuel cladding.

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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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In-core corrosion monitoring in the Halden test reactor

Cited by 10 publications

References 0 publications

Status Report on Efforts to Enhance Instrumentation to Support Advanced Test Reactor Irradiations

Status Report on Efforts to Enhance Instrumentation to Support Advanced Test Reactor Irradiations

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

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

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