Engineering Papers⌕ Search

SEARCH · Engineering Papers

Results for “Radiation protection”

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.

Quote a phrase for an exact phrase match. Source license links do not imply unrestricted reuse.

At least 1,297 records · Page 72

A Computationally Efficient Algorithm for Computing Convex Hull Prices

Electricity markets worldwide allow participants to bid non-convex production offers. While non-convex offers can more accurately reflect a resource's capabilities, they create challenges for market clearing processes. For example, system operators may execute side payments when a participant’s cost is not covered through energy sale settlements from locational marginal pricing schemes, or when a participant incurs lost opportunity costs to follow the dispatch signal. Convex hull pricing minimizes these and other types of side payments while providing uniform (i.e., locationally and temporally consistent) prices. However, computing convex hull prices involves solving either a large-scale linear program - which in turn requires explicit descriptions of market participants’ convex hulls -or the Lagrangian dual of the corresponding non-convex scheduling problem. Here, we propose a computationally feasible and industrially scalable Benders decomposition approach to computing convex hull prices at least an order of magnitude faster than the current state-of-the-art while leveraging recent advances in convex hull formulations for thermal generating units.

61 RADIATION PROTECTION AND DOSIMETRY↗

Restoring Distribution System Under Renewable Uncertainty Using Reinforcement Learning

Distributed energy resources (DER) in distribution systems, including renewable generation, micro-turbine, and energy storage, can be used to restore critical loads following extreme events to increase grid resiliency. However, properly coordinating multiple DERs in the system for multi-step restoration process under renewable uncertainty and fuel availability is a complicated sequential optimal control problem. Due to its capability to handle system non-linearity and uncertainty, reinforcement learning (RL) stands out as a potentially powerful candidate in solving complex sequential control problems. Moreover, the offline training of RL provides excellent action readiness during online operation, making it suitable to problems such as load restoration, where in-time, correct and coordinated actions are needed. In this study, a distribution system prioritized load restoration based on a simplified single-bus system is studied: with imperfect renewable generation forecast, the performance of an RL controller is compared with that of a deterministic model predictive control (MPC). Our experiment results show that the RL controller is able to learn from experience, adapt to the imperfect forecast information and provide a more reliable restoration process when compared with the baseline MPC controller.

61 RADIATION PROTECTION AND DOSIMETRY↗

The Need for a Maximum Intensity Accident in ANS 8-Series Standards

The Y-12 National Security Complex has installed one Criticality Accident Alarm System (CAAS) under the ANS 8.3 framework as a safety significant system, and is in the process of designing, installing, and qualifying another. As a safety significant system, the Y-12 CAAS is required to demonstrate that it is able to perform its function and actuate an alarm when exposed to the radiation from both a Minimum Accident of Concern and a maximum intensity accident. The ANS 8-series standards do not present a maximum accident to be considered, nor do they specify radiation tolerance requirements for the CAAS equipment, leading CAAS vendors to potentially use other standards that provide inadequate criteria. In this paper, the historical basis and need for a maximum intensity accident in the ANS standards is discussed, the fission rate of a maximum intensity accident is proposed, and the effects of this accident on CAAS analysis and the vendor’s equipment qualification are discussed.

61 RADIATION PROTECTION AND DOSIMETRY↗

URANIUM HOLDUP MONITORING WITH COMPTON IMAGING AS FUNCTION OF DEPTH AND MASS

Mass quantification using standoff gamma detection is a logical progression for MC&A applications in uranium processing facilities. While obtaining a ground truth from physical collection and weighing of masses is ideal and routine, it poses a logistical problem from both a standpoint of ALARA programs as well as interruptions to operations. The standard approach is the Generalized Geometry in Holdup (GGH) method that can apply for many cases where geometries of the holdup match simulated models; however, there are many cases where a model may not exist or a feature of the holdup geometry is such that it does not match a model particularly well.1 Gamma imaging at standoff distances and outside process equipment has potential to address these shortcomings and improve mass estimations while reducing personnel exposure; however, algorithms still require a significant degree of benchmarking to build sufficient confidence in algorithms before displacing GGH in some procedures. This paper presents the creation of a set of laboratory standards of depleted U3O8 in fixed size containers covering a range of masses and effective thicknesses up to the infinite thickness for the 185-keV line. These blocks are identically sized aluminum boxes loaded such that a thin, flat face is placed towards the imager, while the back side contains closed cell foam to apply pressure to keep the powder in a fixed position at the front face as the sources are manipulated for measurements. Included is an analysis of the mass estimation using a commercially available Compton imaging instrument where multiple geometries are created showing limitations in current methodologies.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

BERYLLIUM DETECTION BY FLUORESCENT SPECTROSCOPY

Facilities that machine and process materials involving beryllium oxide are hazardous to workers safety and require monitoring of contamination. A primary goal in industrial worker safety in beryllium containing facilities is avoiding inhalation, which may cause chronic beryllium disease (CBD). Decontamination is labor intensive due to the miniscule size of beryllium dust and the difficulty of detecting its presence on surfaces. Current methods of beryllium detection, while successful, involve numerous intermediate steps such as obtaining wipe samples, applying buffers, centrifuging with ammonium bifluoride, additives to reduce influence of other competing metal ions, and require potentially long wait times of around 24 hours for a single surface sample. In some cases, these samples must be sent to testing facilities across the country and results may not be available for days. Therefore, for the purposes of this study, it has been deemed important to test new fluorescent dyes that can rapidly produce a beryllium presence confirmation via application spray.

61 RADIATION PROTECTION AND DOSIMETRY↗

3D Virtual Simulation for Radiation Safety and Survey Training

3D virtual technologies have been widely used in remote training. Training integrated with 3D visualization technologies can enhance students’ engagement and reduce cost. The Applied Visualization Lab collaborates with College of Eastern Idaho on creating a 3D desktop application that simulate a pipe environment for radiation safety and survey training. Students can learn to perform radiation and contamination surveys remotely on their desktop. This simulation provides random scenarios, guided instructions, user interactions, and visual and sound feedback. It will promote utilizing virtual training for education outreach and minimize radiation and contamination exposure during the training.

3D↗

MSIPP-NSSTC Course on Gamma Ray Spectroscopy – Part I

The presentation titled: "MSIPP-NSSTC Course on Gamma Ray Spectroscopy – Part I" to be presented as part of a course at UNLV for undergraduate/graduate students under the US DOE/NNSA sponsored MSIPP-NSSTC program

61 RADIATION PROTECTION AND DOSIMETRY↗