Review Paper: Review of Instrumentation for Irradiation Testing of Nuclear Fuels and Materials

Kim, Bong Goo; Rempe, Joy L.; Villard, Jean‐François; Solstad, S.

doi:10.13182/nt11-a13294

Cited by 27 publications

(13 citation statements)

References 48 publications

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“…In addition, there are other additions which can increase specific Table 2: Boundary conditions of reactor testing types of corrosion phenomena, such as niobium, which lowers the susceptibility to intergranular corrosion. 2 Although less extreme conditions than experienced in a typical PWR, the corrosion rate of 316 SS at 100 psi and 200 °C in tap water was less than 0.1 mpy (mils penetration per year), similar to 304 SS. A similar corrosion rate was observed when 316 SS was held at nearly 300 °C and higher pressures.…”

Section: Materials Assessment Of Lvdtmentioning

confidence: 83%

In-Pile Fuel Rod Deformation Measurements Using Miniaturized LVDT Technology

Skifton

Schoensee

Jaques

et al. 2017

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Different types of materials are being considered for fuel, cladding, and structures in existing and advanced nuclear reactors. These materials can undergo significant dimensional changes during irradiation. Currently in the US, such changes are measured with the 'cook and look' method (i.e. repeatedly irradiating a specimen for a specified period of time, and then removing it from the reactor for evaluation)-which leads to costly and time consuming experiments. In addition, such techniques provide limited data, and handling may disturb the phenomena of interest. Therefore, in-pile detection of geometric changes is needed to understand real-time behavior during irradiation testing of fuels and materials in high flux US Material and Test Reactors (MTRs). The developmental results of an advanced Linear Variable Differential Transformer (LVDT)-based test rig capable of detecting real-time changes in diameter or length of fuel rods or other material samples during irradiation in US MTRs are presented. The LVDT is being developed at the Idaho National Laboratory (INL), and will provide experimenters with the capability to measure dimensional changes associated with fuel and clad swelling, pellet-clad interaction, and crud buildup. The LVDT design utilizes the MTR's loop pressure to drive the test specimen at a constant rate. This leads to a simplified construction which only requires three pressure boundary penetrations. Further, the LVDT pressure boundary is a leak tight hydraulic ram capable of actuating under low differential pressure (e.g. 1 psid), and is able to survive the high irradiation tests at Pressurized Water Reactor (PWR) conditions. v vi

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Section: Materials Assessment Of Lvdtmentioning

confidence: 83%

In-Pile Fuel Rod Deformation Measurements Using Miniaturized LVDT Technology

Skifton

Schoensee

Jaques

et al. 2017

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“…Characterization needs include dimensional changes in fuel pellets, microstructural changes (such as porosity and cracking), as well as characterization of fission gasses. Several recent reviews have focused on in-pile instrumentation for reactor monitoring (Kim et al 2011;Solstad and Van Nieuwenhove 2011;Villard and Schyns 2011;Rempe et al 2010). On-line continuous monitoring of in-pile materials requires radiation-hardened sensor materials.…”

Section: In-pile Measurementsmentioning

confidence: 99%

Materials Degradation and Detection (MD2): Deep Dive Final Report

McCloy¹,

Montgomery²,

Ramuhalli³

et al. 2013

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“…In the past rates such as 1 degree per minute have been used. As such, the time necessary for each experiment will depend on the Curie temperature; on the order of 500-1000 minutes or [8][9][10][11][12][13][14][15][16] hours.…”

Section: Test Materials Descriptionmentioning

confidence: 99%

2012 Status Report on Efforts to Enhance Instrume

Rempe¹,

Knudson²,

Daw³

et al. 2012

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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 at the Idaho National Laboratory (INL) is to design, develop, and deploy 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 initial 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. Since 2009, annual reports have been issued to provide updates on the program strategy and the progress made on implementing the strategy. This report provides the 2012 update.As reported in this document, significant accomplishments occurred in several instrumentation development and deployment areas during 2012. Specialized INL-developed sensors for real-time detection of temperature and thermal conductivity are not only being provided to NSUF reactors at INL and at the Massachusetts Institute of Technology, but are also being provided to the Commissariat à l'Énergie Atomique et aux Energies Alternatives (CEA) in France and to the Institute for Energy Technology/Halden Reactor Project (IFE/HRP) in Norway for evaluation. High Temperature Test Laboratory (HTTL) staff are also involved in expanding options for peak temperature sensors, such as melt wires and silicon carbide temperature monitors, and integral fluence sensors, such as activation foils and flux wires available to our users. On-going tasks to deploy real-time length and flux detection sensors are continuing. A test rig for evaluating creep specimens is now ready for use in the newly reactivated ATR pressurized water loop and efforts have been initiated to develop a crack growth test rig. In addition, several tasks evaluating 'advanced' technologies, such as fiber-optics based length detection and ultrasonic thermometers, were initiated.

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Review Paper: Review of Instrumentation for Irradiation Testing of Nuclear Fuels and Materials

Cited by 27 publications

References 48 publications

In-Pile Fuel Rod Deformation Measurements Using Miniaturized LVDT Technology

In-Pile Fuel Rod Deformation Measurements Using Miniaturized LVDT Technology

Materials Degradation and Detection (MD2): Deep Dive Final Report

2012 Status Report on Efforts to Enhance Instrume

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