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At least 739 records · Page 41

A Concept for Ultra-High Energy Electron and Positron Test Beams at Fermilab [PowerPoint]

Experimenters looking for energies higher than 30 GeV will have no current comparable alternatives when CERN test beams are shutdown for 2 years at the end of 2018. Alternate lab electron and positron test beam limits are DESY: Under 10 GeV/c, SLAC: Limited to 25 GeV/c; Fermilab: Ranged from 1 - 32 GeV (highest momenta of ~31.9986 GeV/c) and Mixed Species. A unique opportunity to attract a new group of users has presented itself. As CERN e ± test beams are mixed species, providing higher purity, ultra high energy beams has been requested.

43 PARTICLE ACCELERATORS↗

Study of Neutron-Induced Stable and Radioactive Nuclides in a Post Detonation Urban Environment

In the event of a nuclear detonation in an urban environment, response time for triage by first responders, and forensic sample collection are of the utmost importance. When it comes to response planning, decision makers within the government need to have the most up-to-date information regarding several quantities of interest so that the maximum amount of lives can be saved. Quantities of interest in a post-detonation scenario include the spatial distribution of neutron-induced stable and radioactive isotopes in the environment, fallout patterns, blast and re damage zones [1]. The UMPRINDER toolkit is developed to calculate the prompt neutron-induced stable and radioactive isotopes in the surrounding environment in a nuclear forensics post-detonation scenario. The distribution of these isotopes in the environment can be used to provide guidance in determining best routes for first responders in order to minimize dose, debris sample collection routes for subsequent radiochemical analysis, and provide initial radionuclide inventories to fallout codes in order to improve fallout zone fidelity. Other methods have approached isotope transmutation on unstructured mesh for the fusion community concerning shutdown dose rates associated with fusion reactors. UMPRINDER is the first method to be focused on calculating some of the quantities of interest for the nuclear forensics and weapon effects communities.

61 RADIATION PROTECTION AND DOSIMETRY↗

Strategic Survey of Antineutrino-based Nonproliferation Technologies

Antineutrinos carry approximately 3% of the total energy released in fission processes. As a consequence, nuclear energy production provides by far the brightest antineutrino sources on Earth. Antineutrino interactions with ordinary matter are weak and these particles cannot be shielded, making them an ideal signature of fissioning systems. However, the same property makes antineutrinos difficult to detect. Antineutrino detection technologies have matured in recent years, and emerging detection approaches warrant further investment. For near-field applications, the major enabling technological advancement, reported in 2018, is the conclusive detection of the antineutrino spectrum in segmented detectors operating at the surface with minimal shielding. For far-field applications, the highlights are the routine detection of reactor antineutrinos at hundreds of kilometer standoff in the kiloton-scale KamLAND and Borexino liquid scintillator detectors, and in particular the observation of the residual South Korean reactor antineutrino flux in KamLAND following the Fukushima disaster that led to shutdown of reactors in Japan

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

Development of Diffusion-type Hydrogen Meters for Steam Generator Leak Detection System of Sodium-cooled Fast Reactors

The goal of this project is to develop and demonstrate diffusion-type hydrogen meters (DTHMs) for hydrogen concentration in cover gas or in molten sodium. Prompt detection of steam-to-sodium leaks of a sodium-heated steam generator (SHSG) is one of the most important economic and safety issues to be addressed in designing and operating a sodium-cooled fast reactor (SFR). A water-to-sodium leak causes a violent exothermic sodium-water reaction (SWR) resulting in local temperature rise (>1,200°C) and produces hydrogen gas and highly corrosive chemicals. The SWR often induces self-enlargement (self-wastage) of the leak and rapid propagation of wastage to adjacent tubes, leading to secondary or multiple tube failures. If it is unmitigated, the hydrogen gas formation could cause a pressure increase in the reactor and may cause a SHSG blowdown, and ultimately result in shutdown of the reactor. In addition, if their effects are unmitigated, the highly corrosive chemicals formed could lead to and accelerate the corrosion problems of the SHSG and sodium piping.

37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CH↗

Energy Paths for the Yurok People

This Yurok Tribe energy strategic planning study examined electricity usage, costs and infrastructure, as well as electricity needs on the Reservation. It also assessed the Tribe’s energy resources. Equipped with this information, the project team conducted an energy options analysis that examined different project opportunities and identified key projects that are both feasible to implement and will help the Tribe reach its stated Energy Vision. A key finding of the energy needs assessment is that there are still numerous households that are without grid electric power, and it is likely that most of them will remain disconnected from the grid because of their remoteness. To provide these community members with reliable, affordable, modern energy services their homes will need to be electrified via a robust off-grid energy services program that installs and maintains off-grid energy systems. This is the key need that is explored and addressed in this plan. The approach taken is to establish a new business entity, a Tribal Energy Authority or Utility, that will operate a Tribal Energy Program. The Energy Strategic Plan identifies a number of potential funding sources that could be used to support both the On-grid and Off-grid Energy Programs. This plan also promotes continued efforts to reduce electricity consumption through the implementation of energy efficiency measures in existing facilities and the enforcement of a strong energy-efficient building code for all new construction on the Reservation. Finally, the plan promotes added resilience at critical Tribal facilities on the Reservation by recommending that battery energy storage systems and microgrid controls be coupled with rooftop solar PV systems to create cutting edge microgrid facilities that can provide critical power services to Tribal facilities when the main electric grid is shutdown.

29 ENERGY PLANNING, POLICY, AND ECONOMY↗

System Study: Residual Heat Removal 1998–2018

This report presents an unreliability evaluation of the residual heat removal (RHR) system in two modes of operation (low-pressure injection in response to a large loss-of-coolant accident and post-trip shutdown-cooling) at 104 U.S. commercial nuclear power plants. Demand, run hours, and failure data from calendar years 1998 through 2018 for selected components were obtained from the Institute of Nuclear Power Operations (INPO) Industry Reporting and Information System (IRIS), formerly the INPO Consolidated Events Database (ICES). The unreliability results are trended for the most recent 10 year period while yearly estimates for system unreliability are provided for the entire active period. No statistically significant increasing or decreasing trends were identified in the RHR results.

99 GENERAL AND MISCELLANEOUS↗

Slag Management of Carbon Feedstock Used in Gasification FY17 TCF between Eastman Chemical and NETL (Final Report)

NETL, in collaboration with Eastman Chemical Corp (Kingsport, TN), targeted the joint evaluation and refinement of a slag management program developed by NETL (NETL IP, patent applied for) to control gasifier slag properties formed from ash in individual or combinations of different coal-based carbon feedstock materials and specific slag modifiers used in gasification. Slag forms from mineral or organic-metallic impurities in the carbon feedstock that melt at the high temperatures of gasification, coalescing to form a liquid (slag) that must flow from the gasifier. Slag additives, also known as slag modifiers, are often added to the carbon feedstock to modify the ash chemistry and achieve desired slag flow properties at target temperatures used in gasification. If slag does not flow from a gasifier, its buildup within the gasification chamber will cause either gasifier shutdown to physically remove the slag (consuming time and damaging the protective refractory lining), or the gasification temperature must be increased to lower slag viscosity so it can flow from the gasifier, leading to greater refractory wear/corrosion, along with increased fouling and downstream component wear. Because of these issues, gasification is typically targeted at the lowest temperature possible where slag will flow in a controlled manner (a temperature range called T100 for the lowest temperature, with T250 being the highest temperature where the slag has achieved the desired fluidity). That temperature range also needs to yield a desired syngas composition, highlighting the importance of knowing and being able to control carbon feedstock slag viscosity and the temperature of thermal breakdown of the carbon feedstock. Slag viscosity varies with changes in the gasification chamber temperature, oxygen partial pressure, and slag chemistry. The slag model work with Eastman Chemical targeted predicting and controlling molten coal ash slag behavior at specific gasification conditions. The final goal of the refined model was to develop/refine the NETL slag model so a gasifier operator would be able to predict slag behavior prior to purchasing or using a carbon feedstock and control slag properties once a carbon feedstock is being gasified, allowing a gasifier user to determine what mineral additives or blends of different carbon materials would be needed to achieve desired slag properties at targeted gasification conditions. For a given carbon feedstock and desired gasification condition, the actual gasification cost and slag behavior would be able to be predicted using the slag management program in advance of purchasing or using the carbon feedstock – allowing accurate control of slag ash behavior in real time. As part of the TCF project work with Eastman Chemical, the viscosity of several ash compositions of interest to them would be measured and used to populate the slag model, along with a large database of historical slag temperature, chemistry, and viscosity information they possess – information that would in-crease the predictive accuracy of the slag management model with slag ash chemistry of interest to them. As part of the model evaluation and refinement, the predictive model and its database will be installed on computers at Eastman Chemical and used to manage slag properties in a gasifier during real-time operation of their gasifier. In summary, success of the slag management program at Eastman Chemical would support its use by other gasifier operators to manage slag chemistry and properties over other desired gasification temperature ranges, allowing greater process control and efficiency of their carbon feedstock conversion during gasification.

01 COAL, LIGNITE, AND PEAT↗

Development of Thermal Tomography Imaging System for In-Service Nondestructive Evaluation of Additively Manufactured Components

Additive manufacturing (AM) is an emerging method for cost-efficient fabrication of nuclear reactor parts. AM of metallic structures for nuclear energy applications is currently based on laser powder bed fusion (LPBF) process, which can introduce internal material flaws, such as pores and anisotropy. Integrity of AM structures needs to be evaluated nondestructively because material flaws could lead to premature failures due to exposure to high temperature, radiation and corrosive environment in a nuclear reactor. Thermal tomography (TT) provides a capability for non-destructive evaluation of sub-surface defects in arbitrary size structures. We investigate TT of AM stainless steel 316L specimen with imprinted internal porosity defects using relatively low-cost, small form factor infrared (IR) camera based on uncooled micro bolometer detector. Sparse coding related K-means singular value decomposition (SVD) machine learning, image processing algorithms are developed to improve quality of TT images through removal of Additive white Gaussian noise without blurring the images. Following initial qualification of an AM component for deployment in a nuclear reactor, a compact TT can also be used for in-service nondestructive evaluation (NDE). With capability to perform in-service NDE of the AM component lifecycle, TT data can be used for development of a component digital twin. MIT research reactor (MITR) has been identified as a representative environment to perform investigation of feasibility of in-service NDE during shutdown. Preliminary study of radiation level in the MITR viewport, with geometric parameters potentially compatible with compact TT system, has been conducted.

36 MATERIALS SCIENCE↗

Out-of-pile performance of High Temperature Irradiation Resistant and Cladding Thermocouples

The High Temperature Irradiation Resistant thermocouple (HTIR-TCs) has proven to be the nuclear temperature sensor. It outlast and outperforms all other commercially available thermocouples above 1100 °C inside reactor pressure vessels; also, recent calibration methods have pushed the HTIR-TC to accurately read temperatures through thermal transients during reactor shutdowns and restarts. The new temperature range of HTIR-TCs is from 0 °C to 1650 °C. The main objective of this study is to address manufacturing a more robust TC for handling and inserting into reactor experiments; to also apply the TC to a wider application. The TC has shown to be mainly susceptible to oxygen levels inside the heat treatment and calibration process and it is recommended that O2 levels be brought to as low as possible. However, through modeling efforts the O2 has been found to intercalate only within the first few layers of niobium on the outer sheath. Lastly, multiple materials were used for the sheath and insulators; all with similar outcomes when testing occurred over a long period of time.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

Determining the Appropriate Emergency Planning Attributes for Microreactors

Micro-reactor designs incorporate design features that provide very low reactor decay heat power at 24 hours after shutdown that is manageable in comparison with larger reactors. This attribute translates into a low probability of core damage negligible offsite dose. This paper provides the conceptual framework for appropriately structuring emergency planning requirements for micro-reactors while ensuring the U.S. Nuclear Regulatory Commission’s (NRC) commitment to safety is met. Due to the diversity in reactor designs comprising the micro-reactor community, this paper identifies the necessary concepts that should be considered to ensure emergency plans for micro-reactors are appropriate for the risk. This paper does not mandate specific design features for micro-reactors but provides reactor designers a conceptual framework for a scalable, graded approach to Emergency Planning Standards that should be considered in their individual designs in order to support simplified emergency plans. Given that accident source terms associated with micro-reactors are essentially negligible when compared with those for large light water reactors, revisions to emergency planning standards are justified. A graded approach to implementing emergency planning guidance can be used to appropriately structure micro-reactor emergency plans and reduce the size of the emergency planning zone and plume exposure pathway. Appropriately structuring emergency planning requirements will better optimize licensee and offsite agencies emergency planning resources and reduce the resources associated with emergency planning.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗

Fission Gas Measurements in Spent Fuel: Literature Review

The fission-derived noble gases, xenon(Xe) and krypton(Kr), have long been proposed as a tool for supporting nuclear safeguards and declarations verification. A vast body of literature outlines how these non-reactive fission gases released during reactor operation and shutdowns correlate to burnup level, power history, other reactor specifications and reprocessing activities. However, irradiation conditions can vary appreciably both radially and axially within a fuel pin.

07 ISOTOPE AND RADIATION SOURCES↗

Industrial Energy Management During a Pandemic: Lessons Learned from DOE Better Plants Program Partners

The COVID-19 pandemic is causing many challenges for manufacturers, especially those that depend on workers whose jobs cannot be performed remotely. This has detrimentally impacted the energy management workforce, energy support system performance, as well as operations and supply chains.This article discusses four primary challenges for industrial energy management caused by the pandemic, strained budget for energy projects, increased energy intensity caused by low production rates and other safety practices, limited access to energy systems, and the lost knowledge and experience of senior staff. This article also proposes some potential solutions for these challenges that include implementing no- and low-cost energy conservation measures, adopting alternative financing options, improving shutdown procedures, reducing baseloads, creating an effective online energy-monitoring system, performing virtual energy assessments, building a robust EnMS, and attending online and in-person training events.

29 ENERGY PLANNING, POLICY, AND ECONOMY↗

A Conservative Approach to Defining Photovoltaic System Hazards to Firefighters

Sandia National Laboratories performed analysis to develop conservative hazard guidelines regarding firefighters working near photovoltaic (PV) arrays. Assuming implementation of NFPA 70 system shutdown requirements, the analysis focused on DC hazards only. Several different PV variables were considered, including system grounding and DC voltage classes. The hazard scenarios considered the contact conditions, current paths through the body, and PPE. Guidelines for the hazard definitions for men and women were based on the IEC TS 60479-1 guidelines. The importance of PPE was illustrated in the results.

14 SOLAR ENERGY↗

The 2020 Low Energy Gold Run in the Injectors

During Run 20 the injectors provided Gold to RHIC at four different energies (3.85, 4.59, 5.75, and 7.3 GeV). The majority of the run was spent providing 4.59 and 5.75 GeV beams. The RHIC physics program using 5.75 GeV beam took place from Dec. 10, 2019 to Feb. 24, 2020, although there was a period of about 2 weeks (Jan. 27 th to Feb. 10 th ) where 7.3 and 4.59 GeV were used. The 4.59 GeV program took place from Feb. 24. 2020 to Sept.1 2020. Data taking for the 4.59 GeV program was interrupted by the COVID-19 shutdown which lasted about 3 months, from Mar. 20 to June 21. So, the 5.75 GeV program was about 2 months long and the 4.59 GeV program was about 3 months long. There were also other short periods where 7.3 GeV beam was provided to RHIC for CeC development and fixed target data taking. 3.85 GeV beam was also provided near the end of the run in preparation for next year (Sept. 2-11).

43 PARTICLE ACCELERATORS↗

Lifecycle Study of the Electronic Optical Sealing System (EOSS): Assessment of Technical Challenges and Needs

Action Sheet 1 between the United States Department of Energy (DOE) National Nuclear Security Administration (NNSA) and Forschungszentrum Julich (FZJ) for "Assessment of Lifecycle Challenges for the Electronic Optical Sealing System (EOSS)" explores the lifecycle challenges of the EOSS and identifies a strategy for the further management of the EOSS within the context of Germany's safeguards implementation. Specifically, the assessment explores lifecycle challenges for use of the seal during reactor operation, shutdown and removal of spent fuel, and the decommissioning process in Germany, identifying possible upgrades to the seal, and providing recommendations to the International Atomic Energy Agency (IAEA) and the European Atomic Energy Community (Euratom) on what should be done to ensure the reliability and usability of the EOSS over the next decade.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

An updated estimate of the Mu2e experiment sensitivity

The Mu2e experiment at Fermilab will search for the conversion of a negative muon into an electron inside the field of a nucleus. This process does not conserve charged-lepton flavour and is heavily suppressed in the Standard Model (SM), with a branching ratio < 10-50. Any evidence of it would be an undeniable evidence of new physics beyond the SM. The project sets out to achieve a single event sensitivity of $\sim 3 × 10^{-17}$ on the ratio between the probability for a conversion of a negative muon into an electron and the one for a muon capture by the nucleus. Such a sensitivity would represent a 4 orders of magnitude improvement on the previous upper limit for the process, making possible to test predictions of different extensions of the SM. Mu2e uses three superconducting solenoids to produce and measure the muon conversions. In the first solenoid, the Production Solenoid, pions and kaons are produced, together with other secondary products, by 8 GeV kinetic energy proton interactions in a tungsten target. A gradient magnetic field is specifically designed to direct low momentum particles into the Transport Solenoid, an S-shaped magnet that filters out particles with unwanted charge and momentum. Muons, produced by pion and kaon decays, finally reach the aluminum Stopping Target in the Detector Solenoid, where they eventually stop and convert. The result of the conversion process is a monochromatic electron of ~105 MeV/c momentum. The Detector Solenoid also hosts the two main detectors: a straw tube tracker and two CsI calorimeter disks, both providing measurement of event kinematics. A germanium detector and a LaBr crystal are located downstream of the Detector Solenoid to measure the X and gamma rays produced by the muon captures in the Stopping Target. A veto system of scintillators covering the Detector Solenoid and half of the Transport Solenoid is used to identify and reject cosmic rays interactions. With respect to the initial project, the Mu2e running plan has evolved to a staged configuration with 2 years at reduced intensity before the 2025 accelerator shutdown for the neutrino beam upgrade and 2 or 3 years at full intensity after that. This, together with geometry changes and a better knowledge of detector performances obtained by the first slice tests, has required a full revision of the signal over background selection that is the subject of this thesis. In order to achieve a new estimate of Mu2e sensitivity, the simulation of the data corresponding to the first 2 years of data acquisition has been performed. This includes both conversion electrons (CE) and the main sources of background: cosmics, decay-in orbits (DIO), radiative pion captures (RPC) and antiprotons. The characteristics of the signal and of the main backgrounds have been studied to define the best selection variables for CE. A special effort has been devoted to the evaluation of the antiproton background. The lack of experimental data for antiproton production cross section makes the systematic uncertainty on this background significant. A new parameterization of the cross section has been developed to fit the existing data and to provide a more reliable estimate of the systematic uncertainty by comparing the results of the old and the new model. A special effort has been devoted to the optimization of the antiprotons Monte Carlo generator. This study has also revealed that the dominant component within this background is represented by antiprotons produced in the opposite direction with respect to the Transport Solenoid entrance and then redirected to it by back-scattering processes in the Production Target. This ultimately highlights the sensitivity of the background estimate to the G4 handling of antiproton interactions in the 1 to 3 GeV/c momentum range. Finally, the final experimental sensitivity has been studied. The momentum and time selection have been optimized to obtain the 5-sigma discovery reach or, in case of no signal, the upper limit on conversion probability. The results confirm that, in the firs t two years of data taking, Mu2e will be able to improve the current experimental sensitivity for muon-to-electron conversion in an atomic field by more than 3 order of magnitudes.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

Optimal Header Design for Diffusion Bonded Heat Exchangers

Microchannel heat exchangers have seen increasing adoption in many high-pressure applications in recent decades but are subject to particulate fouling from the relatively small channel size compared to traditional designs. Typical cleaning methods require process shutdown, heat exchanger removal, cleaning, then reassembly. The objective of this project was to refine and transfer technology to enable header design improvements for Cleaning-in-Place (CIP), allowing for reduced/negligible process interruption for the cleaning process. The technology transfer was from Sandia National Laboratories (Sandia) to Vacuum Process Engineering, Inc. (VPE). This primary purpose of CIP was developed while considering channel flow uniformity and heat exchanger cost. The project phases were to 1) capture and define potential improvement options, 2) evaluate options with both simulation and experiments, and 3) transfer design knowledge to the industry partner. These efforts resulted in improved header designs from the first known focused effort in this area. The improved designs will help the entire microchannel heat exchanger field that has applications in supercritical CO 2 power cycles, hydrogen (fuel cell) vehicle fueling, liquified natural gas processing, and more.

42 ENGINEERING↗

Radionuclide Inventory and Decay Heat Quantification Methodology for Severe Accident Simulations.

The MELCOR and MACCS computer codes require inputs for radionuclide inventory and decay heat in order to simulate severe accident phenomenology, source term, and consequences. Therefore, Sandia National Laboratories ( SNL ) has developed accurate and automated methods using SCALE 6 in conjunction with automation scripts to directly generate MELCOR and MACCS input records for radionuclide inventories and decay heating. Consistent information between the two codes is essential for realistic modeling of severe nuclear accidents it is the radionuclide inventory and decay power that are the principal safety problems of any severe accident that assumes successful reactor shutdown. SNL plans to conduct best-estimate calculations and uncertainty analyses using MELCOR and MACCS for several reactors, including units 1 - 3 of Fukushima Daiichi, which entail accurate and technically-scrutable information for the input models. The SNL methodology for generating radionuclide and decay power inputs directly from SCALE6 calculations is mostly presented in the context of supporting Fukushima modeling efforts. Furthermore, certain historical assumptions used by MELCOR and MACCS in the abstraction of radionuclide classes and their properties are reviewed, and these assumptions are compared to modern code predictions by SCALE6.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗