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Search indexed NASA NTRS and DOE OSTI research on propulsion, heat transfer, battery materials and energy systems. Follow report and document links to the original sources.
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This plan describes post-irradiation examination (PIE) activities (safety testing and post-safety test analyses) to be performed by Oak Ridge National Laboratory (ORNL) on irradiated Compact 3-1-1 taken from the Advanced Gas Reactor (AGR) experiment, AGR 2. This work will be performed in accordance with general objectives outlined in the AGR-2 PIE plan and guidance in the ORNL PIE statement of work.
High efficiency and compactness, offered by the Printed Circuit Heat Exchanger (PCHE) makes it a strong candidate for use as an Intermediate Heat Exchanger (IHX) and/or Secondary Heat Exchanger (SHX) for Advanced High Temperature Reactor (AHTR) systems and also the Very High Temperature Reactor (VHTR). Idaho National Laboratory (INL) has been developing a computer code for the PCHE design and analysis [1], and will construct an experimental loop to evaluate the thermal hydraulic performance of PCHEs [2]. In order to correctly compare experimental results with the simulations, the extraneous heat losses from the PCHEs must be determined and incorporated. These heat exchangers operate at high temperature and consequently, despite the use of external thermal insulation, experience non-negligible heat losses to the surroundings. The objective of this work is to develop an analytical methodology for quantification of these heat losses based on experimental data to evaluate and predict the performance of the heat exchanger accurately.
A low-power, compact piezoelectric particle emitter for emitting particles such as X-rays and neutrons. A piezoelectric transformer crystal receives an input voltage at an input end and generates a higher output voltage at an output electrode disposed at an output end. The emitter is in a vacuum and the output voltage creates an electric field. A charged particle source is positioned relative a target such that charged particles from the charged particle source are accelerated by the electric field toward the target. Interaction between the accelerated charged particles and the target causes one of X-rays and neutrons to be emitted.
This plan describes post-irradiation examination (PIE) activities (safety testing and post-safety test analyses) to be performed by Oak Ridge National Laboratory (ORNL) on irradiated Compact 4-1-2 taken from the Advanced Gas Reactor (AGR) experiment, AGR 2. This work will be performed in accordance with the Statement of Work for PIE and Safety Testing of Pebble Bed Modular Reactor Limited (PBMR) Fuel at ORNL.
This plan describes post-irradiation examination (PIE) activities (safety testing and post-safety test analyses) to be performed by Oak Ridge National Laboratory (ORNL) on irradiated Compact 2-1-2 that was taken from the Advanced Gas Reactor (AGR) experiment, AGR-2. This work will be performed in accordance with general objectives outlined in the AGR-2 PIE plan0F0F and guidance in the ORNL PIE statement of work.
This plan describes the post irradiation examination (PIE) activities to be performed by Oak Ridge National Laboratory (ORNL) on irradiated Compact 6-2-3 taken from the Advanced Gas Reactor (AGR) experiment, AGR 2. This work will be performed in accordance with the general objectives outlined in the AGR 2 PIE Plan and guidance in the ORNL PIE Statement of Work.
This plan describes the post irradiation examination (PIE) activities to be performed by Oak Ridge National Laboratory (ORNL) on irradiated Compact 2-2-1 taken from the Advanced Gas Reactor (AGR) experiment, AGR 2. This work will be performed in accordance with the general objectives outlined in the AGR 2 PIE Plan and guidance in the ORNL PIE Statement of Work.
A compact cooling system based on thermoelastic effect is provided. In one embodiment, the system comprises a pair of rollers serving as a heat sink, stress applicator and belt drive, a cold reservoir and a solid refrigerant belt coupled to the cold reservoir and to the heat sinks to pump heat from the cold reservoir to the heat sink. The refrigerant belt comprises solid thermoelastic materials capable of thermoelastic effect. The refrigerant material is mechanically compressed when entering the gap of the roller and subsequently released after passing through. When compressed the refrigerant material transforms to martensite phase and releases heat to the roller and neighboring materials. After released by the rollers, the refrigerant material transforms back to austenite and absorbs heat from the ambient atmosphere.
This plan describes post-irradiation examination (PIE) activities to be performed by Oak Ridge National Laboratory (ORNL) on irradiated Compact 3-4-1 that was taken from the Advanced Gas Reactor (AGR) experiment, AGR-2. This work will be performed in accordance with general objectives outlined in the AGR-2 PIE plan and guidance in the ORNL PIE statement of work.
This plan describes post-irradiation examination (PIE) activities (safety testing and post-safety test analyses) to be performed by Oak Ridge National Laboratory (ORNL) on irradiated Compact 6-2-2 taken from the Advanced Gas Reactor (AGR) experiment, AGR 2. This work will be performed in accordance with general objectives outlined in the AGR-2 PIE plan and guidance in the ORNL PIE statement of work.
One of the key challenges to licensing new reactor designs is validating the integral transient response models of a novel system. This work used a frequency response approach for model validation of the Compact Integral Effects Test (CIET) facility at the University of California, Berkeley. This facility was built as a scaled integral effects test for verifying transient modeling tools for fluoride-salt-cooled hightemperature reactors using Dowtherm A as a simulant fluid for molten salt. The dynamic system model of CIET was created using the Modelica-based TRANSFORM tool developed by Oak Ridge National Laboratory (ORNL). Analysis of the model’s performance as compared with experimental results indicates good agreement under both steady-state and transient conditions. This paper describes the Modelica model creation process using TRANSFORM and the modeling assumptions and methods for matching dynamic behavior with frequency response data. Results, analysis, and a discussion of future work are also presented.
The supercritical CO2 (sCO2) power cycles rely heavily on heat recuperation to increase efficiency. Compact heat exchangers are proposed to reduce equipment size and enhance heat transfer between heat source and sCO2. Microchannel architectures in these heat exchangers are typically formed by a lamination process wherein channels are formed in layers of sheet material, which are then stacked and joined together using diffusion bonding, brazing, or transient-liquid-phase bonding (TLPB). TLPB of Ni-based superalloy (Alloy 230) sheets into stacks was investigated. Electron microscopy identified solidification shrinkage porosity on the bond line as the most common defect in the TLP bonded stacks. Tensile yield strengths of 76-86 % of the base alloy strength were obtained on bonded stacks. Scanning electron microscopy on the fracture surfaces indicated ductile failure mode in the bonded zone. Environmental stability of joined regions in Alloy 230 stacks was investigated by exposing to CO2 at 700°C for 1500 hours. Mass change and post-exposure microscopic analysis showed a corrosion behavior similar to the base material.
This plan describes post-irradiation examination (PIE) activities (safety testing and post-safety test analyses) to be performed by Oak Ridge National Laboratory (ORNL) on irradiated Compact 6-4-3 taken from the Advanced Gas Reactor (AGR) experiment, AGR 2. This work will be performed in accordance with general objectives outlined in the AGR-2 PIE plan0F and guidance in the ORNL PIE statement of work.
This plan describes post-irradiation examination (PIE) activities (safety testing and post-safety test analyses) to be performed by Oak Ridge National Laboratory (ORNL) on irradiated Compact 5-2-1 taken from the Advanced Gas Reactor (AGR) experiment, AGR 2. This work will be performed in accordance with general objectives outlined in the AGR-2 PIE plan0F and guidance in the ORNL PIE statement of work.
This plan describes the post irradiation examination (PIE) activities to be performed by Oak Ridge National Laboratory (ORNL) on irradiated Compact 1-4 taken from the Advanced Gas Reactor (AGR) experiment, AGR-3/4. This work will be performed in accordance with the general objectives outlined in the AGR 3/4 PIE Plan and guidance in the ORNL PIE Statement of Work.
A compact particle accelerator can include two or more cavities disposed along an axis of the particle accelerator, each of which is coupled to two or more drivers. The accelerator can also include a power supply coupled to the two or more drivers such that a particle beam traveling along the axis is accelerated. The power supply can be an interface with a commercial power outlet, battery power, or a combination thereof depending upon the use case. Example configurations of the accelerator include hand held or mobile devices that are capable of delivering up to and greater than a 1 MeV electron beam.
Atomic clocks are precision timekeeping devices that form the basis for modern communication and navigation. While many atomic clocks are room-sized systems requiring bulky free space optics and detectors, the Trapped-lon Clock using Technology-On-Chip (TICTOC) project integrates these components into Sandia's existing surface trap technology via waveguides for beam delivery and avalanche photodiodes for light detection. Taking advantage of a multi-ensemble clock interrogation approach, we expect to achieve record time stability (< 1 ns error per year) in a compact (< /1 2 L) clock. Here, we present progress on the development of the integrated devices and recent trapped ion demonstrations.
New designs for compact SRF linacs can produce micron-size electron beams. These can can be used for inverse Compton scattering light sources of exceptional flux and brilliance.