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Characterization of Novel Spacecraft Materials aboard the Materials International Space Station Experiment-Flight Facility (Preliminary Results)

This work will encompass the preflight characterization of 15 novel and heritage materials currently under observation on the Materials International Space Station Experiment-Flight Facility (MISSE-FF). MISSE-FF has been upgraded to perform active reflectance measurements of the materials. Images taken in RGB/IR colors are compared to results from an extensive ground testing campaign to obtain quantitative on-orbit material evolution data. Identical materials samples are to be flown on the ram, wake, and zenith faces of MISSE-FF, enabling deconvolution of the energetic electron, proton, atomic oxygen, and ultraviolet damage pathways. Energy deposition from the space environment leads to chemical changes in the material that in turn alter the optical properties. The same chemical damage that manifests as changes in optical reflectance and absorptance also leads to changes in myriad physical properties such as mechanical strength, electrical conductivity, and chemical reactivity. Therefore, flight materials are able to be characterized based on their unique reflectance spectra by comparing on-orbit measurements of optical reflectance with extensive terrestrial experiments, which help to correlate changes in reflectance with respect to changes in other material properties. The MISSE program has been a part of the International Space Station National Laboratory for many years and has been instrumental in understanding space weather modification of material properties. However, MISSE-FF has been limited to passive experiments with only pre/post flight material studies possible. In advance of the MISSE-16 experiment, the flight facility has received a major upgrade to provide daily spectral observations by way of a RGB/IR camera and a tunable light source. The MISSE-16 mission launched in February 2022 and carries 15 material samples for 6 months of the low Earth orbital exposure. Identical materials samples are to be flown on the ram, wake, and zenith faces of MISSE-FF, enabling deconvolution of the energetic electron, proton, atomic oxygen, and ultraviolet damage pathways. This paper discusses the MISSE-16 experiment, highlights the first use of the facility upgrades, and presents results from the extensive preflight material characterization that includes directional hemispherical reflectance, bidirectional reflectance, AFM, SEM, and electrical conductivity. Additionally, data showing the modification of these properties by ground-based exposure to space-like electron and atomic oxygen flux will be discussed. Finally, updates on deployment and initial check-out of the experiment on MISSE-FF will be presented. It is the ultimate goal of this program to provide validation for the development of ground based space weather simulation facilities and techniques.

Ryan Hoffman↗
DOE OSTI2017

Fuel-Coolant Interaction Results for High Energy In-Pile LWR Fuels Experiments

Fuel-coolant interaction (FCI) has long been a subject of interest in severe-accident reactor safety applications. Significant chemical interaction also frequently results at the high temperature associated with these events in a water environment. Historical rapid, high energy transient irradiation test results are reviewed for experiments performed in transient experimental reactors in Idaho. Though such events are not credible for any deployed nuclear reactor technology, the pressure waves produced by FCI on surrounding containment structures are of importance to advanced light water reactor designs and for transient experiment design considerations. A brief introduction to steam explosion and related studies is provided in the context of these experiments. Extensive reactivity initiated accident testing programs were carried out in the Transient REActor Test (TREAT) facility, the Special Power Excursion Reactor Test (SPERT) facility, and the Power Burst Facility (PBF) from the 1960’s through the late 1970’s. A variety of fuel forms including waterlogged rods were tested in capsules containing water coolant at standard temperature pressure. A few tests were performed at high pressure and temperature in the water loop of PBF. In many of these experiments, energy deposition was high enough to greatly exceed melting temperatures of the fuel, resulting in some fraction of the fuel being dispersed into the coolant. A purpose of many of these tests was to determine the nuclear-to-mechanical energy conversion ratio as well as the extent of metal-water reaction. Relevant data collected from these tests included transient energy deposition, pressure response of the coolant, water column velocity, total hydrogen generation, and resulting particle size distributions and particle characterization. In this paper, the mechanical configuration of each experiment facility is reviewed and discussed relative to the measured responses. The empirical results for source pressure and extent of metal-water reaction are presented in the context of the experimental conditions. The results of these experiments provide a unique understanding for behavior of fuel under severe accident conditions in a reactor environment.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2018

Sequential Design of Experiments to Maximize Learning from Carbon Capture Pilot Plant Testing

Pilot plant test campaigns can be expensive and time-consuming. Therefore, it is of interest to maximize the amount of learning and the efficiency of the test campaign given the limited number of experiments that can be conducted. This work investigates the use of sequential design of experiments (SDOE) to overcome these challenges by demonstrating its usefulness for a recent solvent-based CO2 capture plant test campaign. Unlike traditional design of experiments methods, SDOE regularly uses information from ongoing experiments to determine the optimum locations in the design space for subsequent runs within the same experiment. However, there are challenges that need to be addressed, including reducing the high computational burden to efficiently update the model, and the need to incorporate the methodology into a computational tool. We address these challenges by applying SDOE in combination with a software tool, the Framework for Optimization, Quantification of Uncertainty and Surrogates (FOQUS) (Miller et al., 2014a, 2016, 2017). The results of applying SDOE on a pilot plant test campaign for CO2 capture suggests that relative to traditional design of experiments methods, SDOE can more effectively reduce the uncertainty of the model, thus decreasing technical risk. Future work includes integrating SDOE into FOQUS and using SDOE to support additional large-scale pilot plant test campaigns.

20 FOSSIL-FUELED POWER PLANTS↗
DOE OSTI2015

Bare, Complex, and Potassium-Filled HEU Oralloy Annuli Benchmark Experiments

Hundreds of critical experiments were constructed from Oak Ridge Alloy (oralloy) during the 1960s and 1970s at the Oak Ridge Critical Experiments Facility (ORCEF) in support of criticality safety operations at the Y-12 Plant. The purpose of these experiments included the evaluation of storage, casting, and handling limits and providing data for verification of calculation methods and cross sections for nuclear criticality safety applications. Recent contributions to the International Handbook of Evaluated Criticality Safety Benchmark Experiments (ICSBEP Handbook) include bare, complex, and potassium-filled annuli comprising multiple stacked units of highly enriched uranium (HEU), ~93.2 wt.% 235U, annuli, discs, and parallelepipeds. Prior contributions to the ICSBEP Handbook include bare (unreflected and unmoderated) cylinders; configurations of cylinders and annuli reflected with polyethylene, beryllium, or thin-graphite reflectors; GROTESQUE; and ORSphere. The newest contributions include a bare HEU 11-7 (11 inch outer diameter and 7 inch inner diameter) annulus capped at the top and bottom; bare HEU 13-7, 15-7, and 15-9 annuli; bare HEU complex annuli consisting of a 15-9 annulus containing either an off-center 7-inch-diameter cylinder, 5 × 5 inch parallelepiped, or split parallelepiped; and an HEU 13-7 annulus containing either empty stainless steel cans or potassium-metal-filled cans. The purpose of this latter pair of annulus configurations was to test the fast neutron cross sections of potassium as it was a candidate for coolant in some early space power reactor designs. A total of nine new configurations were evaluated as acceptable benchmark experiment measurements. Additional ORCEF oralloy experiments have also been identified for future benchmark evaluation.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2018

Advances and Enhancements in the Fabric for Frontier Experiments Project at Fermilab

The FabrIc for Frontier Experiments (FIFE) project within the Fermilab Scientific Computing Division is charged with integrating offline computing components into a common computing stack for the non-LHC Fermilab experiments, supporting experiment offline computing, and consulting on new, novel workflows. We will discuss the general FIFE onboarding strategy, the upgrades and enhancements in the FIFE toolset, and plans for the coming year. These enhancements include: expansion of opportunistic computing resources (including GPU and high-performance computing resources) available to experiments; assistance with commissioning computing resources at European sites for individual experiments; StashCache repositories for experiments; enhanced job monitoring tools; and a custom workflow management service. Additionally we have completed the first phase of a Federated Identity Management system to make it easier for FIFE users to access Fermilab computing resources.

Herner, Kenneth↗
DOE OSTI2014

The MOLLER Experiment: An Ultra-Precise Measurement of the Weak Mixing Angle Using Møller Scattering

The physics case and an experimental overview of the MOLLER (Measurement Of a Lepton Lepton Electroweak Reaction) experiment at the 12 GeV upgraded Jefferson Lab are presented. A highlight of the Fundamental Symmetries subfield of the 2007 NSAC Long Range Plan was the SLAC E158 measurement of the parity-violating asymmetry $A_{PV}$ in polarized electron-electron (M{\o}ller) scattering. The proposed MOLLER experiment will improve on this result by a factor of five, yielding the most precise measurement of the weak mixing angle at low or high energy anticipated over the next decade. This new result would be sensitive to the interference of the electromagnetic amplitude with new neutral current amplitudes as weak as $\sim 10^{-3}\cdot G_F$ from as yet undiscovered dynamics beyond the Standard Model. The resulting discovery reach is unmatched by any proposed experiment measuring a flavor- and CP-conserving process over the next decade, and yields a unique window to new physics at MeV and multi-TeV scales, complementary to direct searches at high energy colliders such as the Large Hadron Collider (LHC). The experiment takes advantage of the unique opportunity provided by the upgraded electron beam energy, luminosity, and stability at Jefferson Laboratory and the extensive experience accumulated in the community after a round of recent successfully completed parity-violating electron scattering experiments

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
DOE OSTI2020

Simulation and Development of the Radial Time Projection Chamber For the Bonus12 Experiment in CLAS12

Knowledge of the structure of nucleons (i.e. protons and neutrons) is a central topic of interest to nuclear/particle physicists. Much more is known about the structure of the proton than the neutron due to the lack of high-density free neutron targets. The Barely Off-shell Nucleon Structure experiment (BONuS12) at Jefferson Lab (JLab) is a second generation experiment upgraded/optimized to advance our knowledge of the neutron's structure using the deep-inelastic scattering of electrons off deuterium. Typically, since deuterium is a nuclear target, corrections for off-shell and nuclear binding effects must be taken into account in order to extract results on the neutron. These corrections are model-dependent and therefore have limited our success in extracting neutron information using deuterium targets. In the BONuS12 experiment, 10.6 GeV electrons are scattered off of a deuterium target. By detecting the low momentum spectator proton at backward angles, the uncertainty due to final state interactions is minimized. The goal of the experiment is to measure the ratio of the neutron to proton structure functions ($F^n_2/F^p_2$) as the Bjroken scaling variable x approaches 1. The newly designed Radial Time Projection Chamber (RTPC) for BONuS12 detects the spectator proton in coincidence with the scattered electron, which is detected in the CEBAF Large Acceptance Spectrometer (CLAS12). This work presents the simulation and development of the new BONuS12 RTPC. The design, construction, and testing of the Drift-gas Monitoring Sysytem (DMS) for the BONuS12 experiment is also described. The results of the DMS operation as well as the first preliminary data from the BONuS12 experimental run are given. Because the BONuS12 data analysis depends on CLAS12 working effectively, an effort to verify the CLAS12 operation with the extraction of the inclusive deep inelastic cross section from the first experiment in CLAS12 (Run Group A) will be presented.

Dzbenski, Nathan↗
DOE OSTI2021

Search for CPT and Lorentz invariance violation in the muon $g -2$ experiment at Fermilab

The Muon g-2 experiment at Fermilab (E989) aims to measure the anomalous magnetic moment of the muon, $a_{\mu}= (g-2)/2$, to a groundbreaking precision of $140$ ppb, obtaining a near four-fold increase in precision over the previous experiment, E821, at the Brookhaven National Laboratory (BNL). The value of $a_{\mu}$ from BNL currently differs from the Standard Model prediction by $\sim 3.7$ standard deviations, suggesting the potential for new physics and therefore, motivating a new experiment.Because the theory predicts this number with high precision, testing the g-factor through experiment provides a stringent test of the SM and can suggest physics beyond the Standard Model. The goal of the Fermilab Muon $g-2$ experiment is to increase the statistical precision by more than a factor of 20 and reduce systematic errors by a factor of 3. By measuring muon precession rate ($\omega_a$) in an external magnetic field, the anomalous magnetic moment will be calculated. This is an incredibly challenging experiment with a unique opportunity to provide new insight into nature. \\ The $g-2$ data also provides a great opportunity for setting the most stringent limits on some of the Standard Model Extension CPT Lorentz violating (LV) parameters in the muon sector. One of the CPT and Lorentz violating signatures that we can look for using $g-2$ data is a sidereal variation of $\omega_a(t)$. Extensive simulation studies confirm that the sensitivity regarding the sidereal varation roughly scales with $\omega_a$ uncertainty. Hence, the $g-2$ experiment at FNAL should be able to reach limits of $\sim 5\times10^{-25}$ GeV. Because the CPT and LV analyses are essentially studies of variations in $\omega_a$ as a function of time and charge, performing an $\omega_a$ analysis sets the stage for the CPT and LV measurement. This dissertation focuses on the methodology of a fully functioning framework and analyzing the Fermilab Muon $g - 2$ Run 2 data containing $\sim 11$ billion events above an energy threshold of $1.7$~GeV.

72 PHYSICS OF ELEMENTARY PARTICLES AND FIELDS↗
DOE OSTI2017

A Search For Weakly Interacting Massive Particles Utilizing A Profile Likelihood Ratio Technique With The Super CDMS Soudan Experiment

Dark matter accounts for ~26.8% of the universe’s mass and ~85% of the matter of the universe. The majority of dark matter is in the form of non-baryonic dark matter. Among all the dark matter particle candidates, the Weakly Interacting Massive Particle (WIMP) is considered the most promising. Tens of experiments around the world are under the searches of WIMPs. The Super Cryogenic Dark Matter Search (SuperCDMS) is one of the leading direct dark matter search experiments. Its latest experiment was located in the Soudan Underground Laboratory in northern Minnesota. By placing its germanium (Ge) detectors deep underground, it aimed at performing a rare-event search in the case that a WIMP would collide with a Ge nucleus and leave a Ge nuclear recoil signal in the detectors. These Ge detectors were operated at a temperature of ~50 mK to reduce the noise from disturbing the ionization and phonon signal collections. A high mass WIMP search analysis is performed on the recent collected data sets at Soudan. It aims at exploring WIMPs with masses from the order of 10 GeV/c 2 and above. With a raw exposure of 1657.54 kg-days, an exclusion limit is set on the spin-independent WIMP-nucleon cross section at 1.32 ×10 -44 cm 2 for a 75 GeV/c2 WIMP at a 90% confidence level by the profile likelihood ratio technique. Neutrons are the most dangerous background in a direct dark matter search experiment. The nuclear recoil signal that a neutron produces in a Ge detector is indistinguishable from vii that a WIMP produces. Protection against them is one of the key aspects for the next generation of SuperCDMS experiment at SNOLAB. An active neutron veto system was proposed to be implemented in this future experiment to make it more robust from neutrons. The feasibility of both the plastic and liquid neutron veto systems was studied.

Qiu, Hang↗
DOE OSTI2016

Uncertainty as a Function of Time for Subcritical Experiment Parameters Using the Hage-Cifarelli Formalism

When designing critical or subcritical experiments, it is desirable to have an estimate of the measurement uncertainties prior to performing an experiment. In addition, an important goal is to have the smallest measurement uncertainties possible given measurement time constraints. Having well-designed experiments with small uncertainties helps improve nuclear data and therefore has direct impacts on criticality safety. This work shows how the uncertainties in various measurement parameters vary as a function of counting time and provides an approach to estimate measured uncertainties and guides in optimizing the available counting time. The uncertainty in six parameters used in subcritical experiments was investigated as a function of time: singles count rate (R{sub 1}), doubles count rate (R{sub 2}), lifetime (1/λ), leakage multiplication (M{sub L}), spontaneous fission rate (FS), and detector efficiency (ε). A comparison to measured data will be presented at the meeting. The approach and results in this work will be used to optimize measurement time in future subcritical experiments and will be used to help estimate measurement uncertainties during the design phase. Having well-designed experiments with the smallest uncertainties possible can help the criticality safety community through data validation. (authors)

42 ENGINEERING↗
DOE OSTI2019

Experiments and Simulation of a Borehole in Salt to Understand Heat, Brine, and Vapor Migration - 19192

Disposition of heat-generating nuclear waste (HGNW) remains a continuing technical and sociopolitical challenge. Numerous concepts for HGNW management have been proposed and examined internationally, including an extensive focus on geologic disposal. One proposed geologic material is salt because of its low permeability and viscoplastic deformation that causes self-repair of damage done to the salt by waste emplacement activities. Evaluating the safety and technical challenges of storing HGNW in a salt repository is an ongoing process involving experiments and supporting numerical simulation. Currently an experiment is underway at the Waste Isolation Pilot Plant (WIPP) to explore how the presence of a heat generating source affects phenomena such as brine migration, vapor transport, and mechanical changes to the bedded salt. A sub-horizontal heated borehole test is in progress in the underground at the WIPP that includes a centrally located 10.2 cm diameter borehole with an adjustable heater surrounded with smaller diameter boreholes instrumented with thermocouples. The central borehole contains an inflatable packer, heating block, brine sampler, and constantly flowing nitrogen gas circulation system. Air-injection tests performed in the central borehole provide pressure measurements that are used to constrain permeability of the system. The steady-state temperatures, as well as the rise and fall of temperature when the heater is cycled on and off, have been measured for up to 60 days. In the borehole, dry nitrogen gas circulation evaporates water and outflows to a desiccant container where water mass is measured daily during the experiment to quantify vapor removal. Although this test is a 'shake-down' for a planned second round of fresh borehole testing, we have gathered a rich dataset. These data allow us to build simulations using the Finite Element Heat and Mass transfer code (FEHM) to evaluate the experimental results, determine field-scale parameters, and identify code improvements to reproduce important physical processes that may not be accounted for at present. A 3-D numerical mesh, built using LaGrit software (lagrit.lanl.gov; Miller et al., 2007), includes increasing resolution around the central borehole. Modeling of the experiment allows for determining the local thermal conductivity and permeability of any damaged bedded salt around the borehole, where damage from drilling may change the permeability, porosity and saturation conditions, by parameter testing and inverse methods. Additionally, assumptions about brine and vapor flow and transport are being tested by comparing measured and simulated results. The combination of experimental data and model results provide additional data to help support the safety case for safe and effective HGNW disposition in bedded salt formations. Initial results from this experiment show that water flow into the borehole is within previous experimental results. Further, we have found that the design of the heater block is restricting energy to flow into the rock salt. Thus, this test has proven useful in design of the next generation experiment where infrared heating may be used to bypass issues caused by air gaps located around the current stainless steel block heater. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2016

An analysis method for experiment power in the ATR

The Advanced Test Reactor (ATR) at Idaho National Laboratory (INL) is used for testing and qualification of nuclear fuels and materials. The ATR has been irradiating the lead test assembly (LTA) for the planned Ki-Jang Research Reactor (KJRR) in Korea. Irradiation and subsequent Post-Irradiation Examination (PIE) of the LTA will lead to qualification of the fuel to support licensing activities. Qualification of the LTA requires the experiment to meet specific thermal and burn-up conditions. In particular, plate 20 of the experiment must obtain a heat flux between 137 and 200 W/cm{sup 2} with a target U-235 depletion of 79-84%. Due to the limited instrumentation and burn-up monitoring capabilities, assurance of meeting experiment goals is verified through modelling. In order to validate the experiment model using ATR operating data, a methodology was developed to compare the calculated experiment power with ATR power monitoring instrumentation. This paper discusses the methodology used to quantify the experiment power and uncertainty in the model based on ATR operating conditions. (authors)

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2017

Single Rod Reflood Quenching Experiments with Simulated Decay Heat for Accident-Tolerant Fuel Claddings

The Loss-of-Coolant Accident (LOCA) is a hypothetical situation which includes a sudden loss of coolant, overheating of fuel rods, and emergency coolant injection. This situation could be modeled as a quenching process of cladding material into the coolants, a reverse process of boiling the coolants. The KAERI have been developing a CrAl-coating type Accident-Tolerant Fuel (ATF) claddings to enhance safety margin in such severe accident situations and evaluations for the performance in various aspects are on process. We established a single-rod type reflood quenching experiment setup to simulate the LOCA process. Unlike other conventional quenching experiment setup, our experiment setup is capable of heating during the reflooding process, simulating the decay heat in the real core. We installed heaters and thermocouples (TC) inside the cladding specimens to minimize any disturbances on the interfacial layer during the experiment. Currently the setup is on test run and we present experiment data and verification with conventional Zircaloy-4 claddings. We are going to conduct the reflood quenching experiment with KAERI's CrAl-coated ATF claddings to evaluate the cooling performances.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2015

Bare, complex, and potassium-filled HEU oralloy annuli Benchmark experiments - 14103

Hundreds of critical experiments were constructed from Oak Ridge Alloy (oralloy) during the 1960's and 1970's at the Oak Ridge Critical Experiments Facility (ORCEF) in support of criticality safety operations at the Y-12 Plant. The purpose of these experiments included the evaluation of storage, casting, and handling limits and providing data for verification of calculation methods and cross sections for nuclear criticality safety applications. Recent contributions to the International Handbook of Evaluated Criticality Safety Benchmark Experiments (ICSBEP Handbook) include bare, complex, and potassium-filled annuli comprising multiple stacked units of highly enriched uranium (HEU), ∼93.2 wt.% {sup 235}U, annuli, discs, and parallelepipeds. Prior contributions to the ICSBEP Handbook include bare (unreflected and unmoderated) cylinders; configurations of cylinders and annuli reflected with polyethylene, beryllium, or thin-graphite reflectors; GROTESQUE; and ORSphere. The newest contributions include a bare HEU 11-7 (11 inch outer diameter and 7 inch inner diameter) annulus oralloy-capped at the top and bottom; bare HEU 13-7, 15-7, and 15-9 annuli; bare HEU complex annuli consisting of a 15-9 annulus containing either an off-center 7-inch-diameter cylinder, 5 x 5 inch parallelepiped, or split parallelepiped; and an HEU 13-7 annulus containing either empty stainless steel cans or potassium-metal-filled cans. The purpose of this latter pair of annulus configurations was to test the fast neutron cross sections of potassium as it was a candidate for coolant in some early space power reactor designs. A total of nine new configurations were evaluated as acceptable benchmark experiment measurements. Additional ORCEF oralloy experiments have also been identified for future benchmark evaluation. (authors)

36 MATERIALS SCIENCE↗
DOE OSTI2022

Reactor physics benchmark experiments at the JSI TRIGA MARK II reactor - Current status and future outlook

Full text of publication follows. With the development of new high-fidelity computational methods, improvement of nuclear data, and multiphysics modelling, there is an increased need for benchmark experiments to experimentally validate the models, methods and input data. Many of the nuclear facilities designed to perform reactor physics benchmark experiments have been shut down. Therefore, research reactors offer a great opportunity for benchmark experiments, if they are well designed and performed with great care and accuracy. In this presentation we provide an overview of the past and ongoing activities related to benchmark experiments at the Jozef Stefan Institute TRIGA Mark II research reactor. The following experiments have been performed: criticality with fresh fuel, {sup 197}Au(n,γ) and {sup 27}Al(n,α) reaction rates in irradiation channels, absolute and relative {sup 197}Au(n,γ), {sup 235}U(n,f) and {sup 238}U(n,f) reaction rates in the core, burnup, kinetic parameters, control rod worth, isothermal reactivity coefficient, self-shielding, slow and fast (pulse) transients, nuclear heating, delayed and prompt gamma ray production, temperature profiles for multi-physics. Since the existing fleet of research reactors is ageing very rapidly and new experiments are needed, new research reactors should be designed and built to meet the needs of future advanced reactors, education and training, and other technologies in the coming years. We will review planned activities at the JSI TRIGA reactors and plans for the new research reactor in Slovenia. (authors)

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2023

νBDX: a Coherent Elastic Neutrino Nucleus Scattering (CEνNS) experiment at Jefferson Lab

Particle physics is an ever-changing field seeking to explain phenomena that lie at the limits of our current knowledge. Among discovered and hypothesized interactions, Coherent Elastic Neutrino-Nucleus Scattering (CE?NS) stands out as a fascinating and elusive phenomenon, offering a unique window into the nature of neutrinos and their interactions with matter. CE?NS, a process predicted by the Standard Model, represents one of the subtle ways in which neutrinos can interact with atomic nuclei. Unlike other neutrinonucleus interactions, CE?NS occurs coherently, meaning that the entire nucleus collectively responds to the neutrino-mediated weak force, resulting in small energy transfers to the nucleus as a whole. The extremely rare nature of CE?NS events presents a formidable challenge to experimenters seeking to detect and study these interactions. Recent advances in detector technologies and the implementation of large-scale experiments, such as coherent neutrino scattering experiments at research facilities around the world, have opened up new avenues for exploring this elusive phenomenon. These experiments aim not only to observe CE?NS directly but also to extract valuable information on neutrino properties, nuclear structure, and potential deviations from the Standard Model. This thesis aims to study the feasibility of an experiment to study CE?NS at The Thomas Jefferson National Accelerator Facility, Newport News, VA, USA. This would be an experiment that exploits the production of neutrinos by an electron beam dumped on a thick target (the beam dump). The large quantity of neutrinos produced and their energy profile are well suited to the purpose of studying the CE?NS. In my thesis, I will start from previous studies on CE?NS and from theoretical considerations regarding the process, then quantify the expected events for a hypothetical experiment and possible backgrounds through simulations aimed at optimizing the geometry of the future detector. I will also show some tests on selected detector components that will be part of a first prototype.

Grazzi, Stefano↗
DOE OSTI2024

Assessment of Measurement Uncertainties in the Jupiter High-240 Experiment

The Jupiter High-240 experiment performed in May of 2019 was previously discussed as a variant of the original Jupiter experiment incorporating plutonium metal alloy fuel plates with higher 240Pu content and lead plates, using both a reference configuration and a second configuration where eight lead plates were replaced with aluminum to simulate voiding. Measurements were recorded for experiment period, the “pressure” of the Comet ram upon closure for each near-critical measurement, and temperature. The experiment reactor period is the time it would take to increase the neutron population by a factor of e. For this experiment, the copper reflectors and upper third of the fuel sits upon a support structure with the lower fuel arrays raised up into the center of the reflectors using a ram (see Fig. 1). The recorded logbook temperature for each measurement corresponds to a resistance temperature detector (RTD) located at the top center of the upper fuel array. This paper summarizes the evaluated uncertainties for the Jupiter High 240 experiment as contributed via the recorded measurements and nuclear data and their assessed impact upon the computation of system reactivity and eigenvalue.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
DOE OSTI2020

Neutronics Analysis of Cold Critical KRUSTY Experiments using MCNP and Serpent

Kilowatt Reactor Using Stirling Technology (KRUSTY) is a prototype designed as a proof of concept for NASA’s Kilo power program, which was funded in order to create a small reactor for various space applications such as providing power for a colony on Mars or the moon and eventually as a possible option for powering rockets on deep space missions. KRUSTY was tested at the National Criticality Experiments Research Center (NCERC) located at the Nevada National Security Site (NNSS) from November 2017, through March 2018. The experimental campaign was conducted in four phases: com ponent critical experiments, cold critical experiments, warm critical runs, and high temperature demonstration. The component critical and cold critical experiments were used to determine the worth of the beryllium oxide (BeO) reflector rings and the boron carbide (B4C) control rod disks under different conditions. These conditions were altered by the addition and subtraction of other components in the assembly. The component critical phase was performed at atmospheric pressure and had four solid support rods spanning the center core; whereas the cold critical phase had the center core placed in a vacuum chamber and eight sodium-filled heat pipes spanning the center core region. This summary discusses the static neutronic analysis completed on the cold critical phase of the campaign using MCNP ® and Serpent. These two codes were used to assess any potential differences or biases in the simulation results. Understanding these potential biases is a key step toward the final goal of being able to fully analyze the transient experiments performed during phases 3 and 4 of the campaign.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗