Oak Ridge National Laboratory's Low Activation Materials Development and Analysis (LAMDA) laboratory is a dedicated facility containing specialized instruments for the study of irradiation-induced effects on materials properties. Located in the Materials Science and Technology Division, LAMDA consists of several interconnected contamination-zone and clean area suites. Originally created as a facility for plutonium studies and then thermophysical properties of graphite for high temperature gas cooled reactors in the 1960's, the role of LAMDA has changed with the emphasis placed on "low activation" materials. Currently, LAMDA is involved in both fundamental and applied research on radiation-induced changes in structural materials, reactor internals, diagnostic materials and sensor components for both current and advanced reactor designs for both fission and fusion systems. LAMDA allows for the examination of low activity radiological samples (< 100 mR/hr at 30 cm) without the need for remote manipulation. LAMDA typically utilizes small, compact samples to allow researchers to leverage cutting-edge characterization and test equipment to study materials phenomenon not possible at a hot cell facility. The LAMDA facility is maintained as a low alpha contamination facility, but certain equipment is available for fuel-related studies. LAMDA contains a strong electron microscopy subprogram, which we describe here.A full complement of equipment and instruments are available for metallographic and microstructural analysis of materials. This includes X-ray tomography and three irradiated-materials-dedicated FEI DualBeam FIB-SEM instruments for 3D materials studies and the preparation of specimens for TEM. LAMDA contains a new 200kV Schottky JEOL JEM-2100F S/TEM with EDS and Gatan Quantum Image Filter, and leverages ORNL's other TEM tools as well as SEMs and atom probe.The LAMDA lab works in conjunction with the Irradiated Materials Examination and Testing (IMET) and Irradiated Fuels Examination Laboratory (IFEL) hot-cell facilities at the laboratory to study materials irradiated at either the High Flux Isotope Reactor (HFIR) or other experimental and commercial reactors. The LAMDA, IMET, IFEL and HFIR facilities are all part of the National Science User Facility. LAMDA performs work supported by various Department of Energy (DOE) programs including the Fusion Materials, Light Water Reactor Sustainability, DOE-Naval prime contractors, as well as collaborations with other international research facilities, universities and companies. Figure 1 shows the IMET facility, where irradiated capsules are opened and the specimens sorted and subjected to first-stage preparation (e.g., inspection, cutting, grinding). Figure 2 shows one of the FEI DualBeam instruments, which is located in a lead-shielded room and equipped for remote operation, and can be used to prepare TEM specimens of irradiated fuels. Figure 3 shows the newly installed JEOL 2100F TEM/STEM instrument. Figure 4 shows Re-rich precipitates in HFIR-irradiated tungsten that ...
Yttrium hydride is an optimal choice for a high-temperature moderator material in advanced thermal neutron spectrum reactors that require small core volumes. A complete database of the thermomechanical properties of yttrium hydride is not yet available, although it is much needed to understand and predict the moderator performance during service in reactors. This milestone report presents the properties of unirradiated bulk yttrium hydride as a function of hydrogen concentration-including density, crystal structure, specific heat capacity, thermal diffusivity, thermal conductivity, hardness, elastic/shear moduli, Poisson's ratio, fracture strength, microstructure, and thermal stability. This information provides a baseline measurement for the subsequent neutron irradiation response study of yttrium hydride. The recommended empirical treatment of the data is suggested. In addition, other properties (i.e., hydrogen retention, thermal hydrogen migration, and irradiation response) requiring investigation are discussed. Also included are the Preliminary post-irradiation examination (PIE) data of yttrium hydride irradiated at 600 and 900°C to 0.1 dpa in the High Flux Isotope Reactor (HFIR). The thermophysical properties have insignificant change following this low dpa irradiation for both irradiation temperatures.
A Severe Accident Test Station (SATS) capable of examining the oxidation kinetics and accident response of irradiated fuel and cladding materials for design basis accident (DBA) and beyond design basis accident (BDBA) scenarios has been successfully installed and demonstrated in the Irradiated Fuels Examination Laboratory, a hot cell facility at Oak Ridge National Laboratory. Two test station modules provide various temperature profiles, steam, and the thermal shock conditions necessary for integral lossof-coolant accident (LOCA) testing, defueled oxidation quench testing, and high-temperature BDBA testing. Installation of the SATS system restores the domestic capability to examine postulated and extended LOCA conditions on spent fuel and cladding and provides a platform for evaluating advanced fuel and accident-tolerant fuel cladding concepts.This document reports on the successful in-cell demonstration testing of unirradiated Zircaloy-4. It also describes the integral test facility's capabilities, installation activities, and out-of-cell verification testing to calibrate and optimize the system.
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