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At least 991 records · Page 55

Ion Exchange and Solvent Extraction: Supramolecular Aspects of Solvent Exchange Volume 21

Preface The theme of supramolecular chemistry (SC), entailing the organization of multiple species through noncovalent interactions, has permeated virtually all aspects of chemical endeavor over the past several decades. Given that the observed behavior of discrete molecular species depends upon their weak interactions with one another and with matrix components, one would have to conclude that SC must indeed form part of the fabric of chemistry itself. A vast literature now serves to categorize SC phenomena within a body of consistent terminology. The word supramolecular itself appears in the titles of dozens of books, several journals, and a dedicated encyclopedia. Not surprisingly, the theme of SC also permeates the field of solvent extraction (SX), inspiring the framework for this volume of Ion Exchange and Solvent Extraction. It is attempted in the six chapters of this volume to identify both how supramolecular behavior occurs and is studied in the context of SX and how SC is influencing the current direction of SX. Researchers and practitioners have long dealt with supramolecular interactions in SX. Indeed, the use of polar extractant molecules in nonpolar media virtually assures that aggregative interactions will dominate the solution behavior of SX. Analytical chemists working in the 1930s to the 1950s with simple mono- and bidentate chelating ligands as extractants noted that extraction of metal ions obeyed complicated mass-action equilibria involving complex stoichiometries. As chemists and engineers developed processes for nuclear and hydrometallurgical applications in the 1950s and 1960s, the preference for aliphatic diluents only enhanced the complexity and supramolecular nature of extraction chemistry. Use of physical techniques such as light scattering and vapor-pressure measurements together with various spectroscopic methods revealed organic-phase aggregates from well-defined dimers to small aggregates containing a few extractant molecules to large inverse micelles swollen with water molecules. Extraction systems involving long-chain cations such as alkylammonium species or long-chain anions such as sulfonates or carboxylates proved especially prone to extensive aggregate formation. The related phenomenon of third-phase formation in SX systems, long misunderstood, is now yielding to spectroscopic and scattering techniques showing extensive long-range organization. Over the last 50 years, tools for studying the structure and thermodynamics of aggregation have grown increasingly sophisticated, leading to a rich and detailed understanding of what we can now recognize as SC phenomena in SX. In the 1970s and 1980s, the rapid growth of SC elicited a paradigm shift in SX. The influence of SC principles had two major effects on the course of SX research. First, it provided a framework for understanding the supramolecular behavior that was already well appreciated in the field of SX, though earlier without the SC terminology. Second, it provided the conceptual tools to control supramolecular behavior in SX, direct it for intended functionality, and to simplify it. Extraction by designed reagents has been steadily progressing ever since, with commercial applications emerging to successfully validate this approach. With the discovery of crown ethers in the late 1960s, the advancement of extractant design has fruitfully employed the concept of inclusion. While considerable initial progress occurred with such molecules, especially because of their affinity and selectivity for alkali and alkaline earth metals, other molecular platforms such as calixarenes have proven more versatile. Multidentate receptors for partial to full inclusion of cations, anions, ion pairs, as well as neutral species, have now become commonplace for selective extraction. This volume of Ion Exchange and Solvent Extraction examines how the principles of SC are being employed both in advancing the design of new highly selective SX systems and in understanding aggregation phenomena in SX systems. Chapter 1 discusses the nature and definition of SC and how it is used generally in design of novel SX reagents. Major approaches using SC principles are outlined and illustrated. Chapter 2 expands upon the theme of ion-pair recognition and introduces outer-sphere recognition of metal complexes, a novel idea with the potential for structural control of solvation, casting a new light on solvent modifiers. Chapter 3 reviews the large literature of calixarenes as extraction reagents for metal ions, where the synthetic versatility of this family of compounds has produced vast possibilities for inclusion and selective separations. Chapter 4 extends such chemistry to extraction of biomolecules, where the potential for selective separations is only beginning to be explored through site recognition in macromolecules. In Chapter 5, a detailed examination of the liquid-liquid interface as an expression of supramolecular phenomena i...

Gloe, Karsten↗

Python interface generator for Fortran based codes (a code development aid)

Forthon generates links between Fortran and Python. Python is a high level, object oriented, interactive and scripting language that allows a flexible and versatile interface to computational tools. The Forthon package generates the necessary wrapping code which allows access to the Fortran database and to the Fortran subroutines and functions. This provides a development package where the computationally intensive parts of a code can be written in efficient Fortran, and the high level controlling code can be written in the much more versatile Python language.

Grote, D. P.↗

Photonic devices on planar and curved substrates and methods for fabrication thereof

A versatile and rapid sol-gel technique for the fabrication of high quality one-dimensional photonic bandgap materials. For example, silica/titania multi-layer materials may be fabricated by a sol-gel chemistry route combined with dip-coating onto planar or curved substrate. A shock-cooling step immediately following the thin film heat-treatment process is introduced. This step was found important in the prevention of film crack formation--especially in silica/titania alternating stack materials with a high number of layers. The versatility of this sol-gel method is demonstrated by the fabrication of various Bragg stack-type materials with fine-tuned optical properties by tailoring the number and sequence of alternating layers, the film thickness and the effective refractive index of the deposited thin films. Measured optical properties show good agreement with theoretical simulations confirming the high quality of these sol-gel fabricated optical materials.

36 MATERIALS SCIENCE↗

Spectral Advanced Radiological Computer System Applications

The Spectral Advanced Radiological Computer System (SPARCS) is a versatile, rugged, multi-platform radiation detection system. It is an easy-to-install and easy-to-operate, gamma radiation detection system for radiological emergency response. It has been designed and built on a foundation of mobile and aerial detection experience that spans four decades. This article reviews the scope and operational thrust of the SPARCS, making references to the versatility and capability of the system and its application under various threat conditions. SPARCS is a multiplatform global gamma ray detection system used at the international level.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

Mesoscale to Molecules: Bioimaging Science (Technology) Program, Principal Investigator (PI) Meeting, August 2–3, 2016

The Mesoscale to Molecules Bioimaging Technology Program, within the Department of Energy’s (DOE) Office of Biological and Environmental Research (BER), sponsors research that addresses grand challenges for biology. These grand challenges are centered around developing a better understanding of the spatial and temporal distributions of key metabolites and biomarkers associated with microorganisms and plants related to bioenergy and environmental systems. The Bioimaging Technology Program is advancing new and improved instruments that are being designed and constructed from the ground up, adapted from other scientific disciplines, or upgraded with new capabilities to create a comprehensive and versatile toolbox for imaging biological dynamics and chemistry. These instrument development approaches involve (1) hypothesis-based technologies focused on solving particular challenges for plant biology, biofuels, and biogeochemistry and (2) broad-based systems and design-based technologies that can lead to new discoveries. Both approaches are being pursued with versatility, transferability, and portability in mind to foster widespread adoption by the larger science community for future field and laboratory studies.

09 BIOMASS FUELS↗

Mesoscale to Molecules: Bioimaging Science Program, Principal Investigator (PI) Meeting, February 28–March 1, 2018, Gaithersburg, Maryland

The Mesoscale to Molecules Bioimaging Science Program (Bioimaging Program), within the Department of Energy’s (DOE) Office of Biological and Environmental Research (BER), sponsors research at national laboratories and universities that addresses grand challenges for biology. These projects are centered on developing a better understanding of the spatial and temporal distributions of key metabolites and biomarkers associated with microbial and plant systems related to bioenergy and environmental systems. The Bioimaging Program is developing new and improved instruments, which are being designed and constructed from the ground up, adapted from other scientific disciplines, or upgraded with new capabilities to create a comprehensive and versatile toolbox for imaging biological dynamics and chemistry. These approaches involve (1) hypothesis-based approaches focused on solving particular problems for plant biology, biofuels, and biogeochemistry and (2) broad-based systems and design-based technologies that can lead to new discoveries. Scientists developing both approaches keep in mind that versatility, transferability, and portability will help foster widespread adoption by the larger science community for future field and laboratory studies.

09 BIOMASS FUELS↗

Establishing Maximal Core Excess Reactivity Envelope for TREAT Test Vehicle Insertion

The Transient Reactor Test (TREAT) Facility is an air-cooled reactor composed of graphite-urania fuel encapsulated in zirconium alloy canisters and surrounded by ~2 ft (~61 cm) of nuclear grade graphite. The primary role of TREAT is to provide in-pile nuclear-heated safety research via transient testing [1]. The following work represents further analyses building upon previously reported work to support larger volume test vehicles within TREAT [2]. The Broad Use Specimen Transient Experiment Rig (BUSTER) provides ample versatility for numerous transient test concepts. However, future testing and experiment needs will require testing environments of different in-core footprints. The versatility of TREAT allows for the development of variegated core layouts with key limitations emplaced as operational safety temperature restrictions and available core reactivity. The focus of this current effort is to gauge core arrangements for TREAT core loadings to support centralized experimental testing of varying dimensional capacity. The total core excess reactivity (ER) was computed for different arrangements to establish comparison tables that enable ready assessment of core ER available for future experiment concepts. Test vehicle worths would then be necessary to establish available ER to support transient testing requirements and to perform reactor performance and safety calculations [3,4].

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗

Nuclear Interdiction Through Relocatable Detectors

The NNSA Office of Nuclear Smuggling Detection and Deterrence (NSDD) has investigated a set of minimal-infrastructure radiation detection systems as alternatives to fixed Radiation Portal Monitors (RPMs) for nuclear interdiction applications. These versatile and relocatable systems can improve nuclear security in missions or locations that do not warrant or support a standard fixed radiation detection system. Over 2019, a variety of relocatable detectors were characterized at the Interdiction Technologies Integration Laboratory at Pacific Northwest National Laboratory (PNNL). Evaluated detectors were diverse in their size and capabilities, ranging from backpack-sized systems to lane-spanning cargo scanning portals. Both spectroscopic and non-spectroscopic pedestrian and vehicle detection systems were characterized against uranium and plutonium sources. Signatures from the sources were modulated by both shielding and distance to quantify the performance of the relocatable systems as signal strength was decreased. Findings showed that relocatable spectroscopic detectors with isotope identification capabilities could reduce nuisance alarm rates compared to conventional fixed installation, gross-counting, radiation portal monitors. In vehicle scanning applications, detection ability generally trended with detection volume, regardless of spectral capability. In pedestrian scanning applications, several smaller backpack-sized detector systems were found to be more sensitive to detecting material than pedestrian portal monitors. The results of this characterization effort have helped inform the deployment of versatile equipment to improve nuclear security missions.

relocatable detectors, Nuclear Security↗

Developments of the Versa-Pac to Expand Use for the Industry - 17475

The Versa-Pac is a certified Type AF packaging (USA NRC Certificate no. USA/9342/AF-96), designed as a replacement for USA DOT 6M drum-type transportation packaging, which was retired approximately ten years ago. The Versa-Pac can be used directly or in conjunction with pails, drums, or inserts, and a variety of smaller containers and vessels. The Versa-Pac comes in two sizes: the VP-55 (i.e. 200-liter drum version) and VP-110 (i.e. 400-liter drum version). It features a patented design that, in combination with the drum exterior, provides enhanced structural protection to payloads under Normal Conditions of Transport and Hypothetical Accident Conditions. Since its introduction in 2010, the Versa-Pac has been utilized mainly as a one-time-use package for disposing of radioactive waste. However, the Versa-Pac package, which has the familiar simplicity of a drum, is a reusable transport package with the capability of shipping a variety of radioactive materials. In the spirit of simplicity yet versatility, the capability of the package has been improved several times in collaboration with our customers. The latest design improvements include a new configuration designated the VP-55HC (high capacity), which utilizes an internal safe geometry pipe container that increases the U-235 capacity. The pipe container is similar in design to the historic USA DOT 2R vessel. Other planned and proposed improvements include provisions to transport UF{sub 6} in 1S, 2S, and 5A/5B cylinders; design changes that further increase the amount of U-235 at enrichments less than 20 wt.%; increasing the capacity of the VP-110 with a VP-110-specific analysis; developing a new, lighter 113-liter version of the package; and introducing content limits specific to uranium oxides in multiple forms. This paper traces the engineering and design efforts involved in expanding the Versa-Pac's versatility. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Content Addition and Testing for 2017 NRC Amendment for the Versa-Pac Type A Fissile Packaging - 18120

The Versa-Pac is a certified Type A, fissile packaging (USA NRC Certificate no. USA/9342/AF-96), often used as a waste package for one time use. Continuous content additions have improved the versatility of the package resulting in expanded uses for the nuclear industry. Principal design of the Versa-Pac packaging maintains the use of an inner liner positioned inside a 55-gallon (VP-55) or 110-gallon drum (VP-110), as used for decades in the transport and disposal of Type A fissile materials. The Versa-Pac is used directly or in conjunction with pails, pipe containers, poly bottles, and a variety of smaller containers, inserts and vessels. The Versa-Pac content developments assist the industry with site shutdown, decommissioning, and cleanup operations, allowing for removal, transport, and storage options for the residual waste materials. A 2017 NRC license amendment application adds new capabilities to the Versa-Pac that include a low 1.25 wt% {sup 235}U enriched uranium loading, small quantities of UF{sub 6} in the form of 1S and 2S cylinders, and a payload mass increase from 250 to 350 pounds for the Versa-Pac 55-gallon version (VP-55). The lower uranium enrichment loading of 1.25 wt% {sup 235}U allows for a higher uranium mass limit. The inclusion of 1S and 2S UF{sub 6} cylinders fills an industry need to remove and dispose of long-stored material during site cleanup activities. The content payload mass limit is increased for low contaminated or radioactive heavy metal contents, such as cut plant components and ingots. Regulatory certification of new contents is demonstrated by test, analysis, and a combination of these techniques to show that the design function of the Versa-Pac as a Type A fissile package remains unchanged. Specific UF{sub 6} criticality and thermal analysis upgrades are added to the design documentation to accommodate 1S and 2S UF{sub 6} cylinders. The parameters for criticality analyses are simplified, ensuring no credit for cylinder containment is required for HAC thus reducing the reliance on a single specific shoring device. An upgrade of the Versa-Pac thermal analysis demonstrates compliance with ANSI N14.1 UF{sub 6} cylinder thermal limits. A new drop test sequence for the VP-55 was performed, documenting the addition of the 350-pound payload and demonstrating the VP-55 maintains structural integrity during the NCT and HAC drop, crush and puncture events as defined by 10 CFR 71. The testing and analyses show no loss of the material occurs and the package maintains the material in a subcritical state. This paper traces the engineering and licensing efforts involved in expanding the Versa-Pac's versatility for the 2017 NRC amendment application; summarizing the new testing and results for the payload increase, the content addition criticality and thermal evaluations, and content description for the Versa-Pac Safety Analysis Report. The NRC license amendment is scheduled for Winter 2017. Testing and supporting analyses reported in the Versa-Pac Safety Analysis Report demonstrates the content developments met the performance requirements of 10 CFR 71 for a Type A fissile package. A revision of the NRC Certificate of Compliance is expected in Spring 2018. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

DEM and MELT In-Can Vitrification Process for Fukushima Daiichi Water Treatment Secondary Waste - 20034

Fukushima Daiichi Nuclear Power Station was severely damaged by a tsunami induced by the earthquake on March 11, 2011. A large amount of water treatment secondary waste has been generated from the purification work of contaminated water that consists of the water flowing into the reactor building. The Mid and Long-Term Road map specifies that solid waste at Fukushima Daiichi Nuclear Power Station should be stored safely and reasonably according to its characteristics. In order to meet this goal, a versatile treatment solution is needed, and the In-Can vitrification seems to be a suitable solution. The DEM and MELT In-Can vitrification process is being developed and qualified in France to treat waste arising from decommissioning and dismantling operations. This qualification is carried out through the consortium of the DEM and MELT project coordinated by CEA which gathers Orano, ECM technologies and Andra. The DEM and MELT In-Can vitrification process is a robust, simple and versatile in situ vitrification process. It is designed for high or intermediate level waste and is compact enough to be implemented in an existing facility or close to the waste to be treated. It is developed to treat liquid and solid waste, to produce a small amount of secondary waste and to minimize investment and operating costs. The DEM and MELT In-Can vitrification process is also developed with a modular design in order to be adapted to nuclear operators needs and requirements. The In-Can melting process has already been developed and fully qualified by the CEA for Alpha liquid waste and can be rated TRL 7 for this scope. The In-Can vitrification technology is considered as a qualified solution that could be applied for the treatment of waste resulting from the D and D work in Fukushima Daiichi Nuclear Power Station. The feasibility evaluation of the DEM and MELT In-Can vitrification process for Fukushima Daiichi water treatment secondary waste is a project led by Orano, CEA and ANADEC. This R and D project is performed by the funds from the Ministry of Economy, Trade and Industry as The Subsidy Program 'Project of Decommissioning and Contaminated Water Management'. This paper presents the first results of this feasibility evaluation, from the scenarios and glass formulation definition to the industrial implementation feasibility. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Modbus RTU for Embedded Cyber Secure Inverter Controller

The Modbus communication protocol is a widely adopted communication standard in industrial control systems. This communication protocol is known for being reliable and straightforward to implement while being versatile in terms of its operating parameters while supporting multiple formats over various hardware infrastructures and architectures. Many intelligent devices such as Programmable Logic Controllers (PLCs), Human-Machine Interfaces (HMIs), Internet-of-Things (IoT), and various Operational Technologies (OT) utilize Modbus for their communication systems. These types of systems must communicate with each other through a standardized and central communication process. To support the integration of these modular systems, a Field-Programmable Gate Array (FPGA) can act as an embedded central routing fabric for this communication to take place. Embedded systems are versatile enough to interface with various devices and systems to accomplish various goals. Additionally, embedded systems require relatively small physical designs to minimize the required resources to facilitate the intended application by providing low-level system access. This minimization of system resources goes hand in hand with reducing the financial cost of a proposed solution or system. As remotely collaborating researchers often use FPGAs to prototype designs that are required to have a method for data transmission among systems, it is imperative to provide a baseline standard for communications among devices and systems. A typical method of implementing the Modbus RTU communication protocol in an embedded environment is using integrated logic architectures within the FPGA called “Intellectual Property (IP) cores.” IP cores can be designed using integrated logic or circuit designs to function as an embedded processor. These IP cores can then perform the required computational actions to support the Modbus RTU communication protocol by utilizing high-level programming languages such as the C programming language. The hardware description language of Very High-Speed Integrated Circuit Hardware Description Language (VHDL) allows for the control of real hardware at the logic gate and signal level. These logic gates and signals can be designed and controlled to perform desired actions based on the system design. Programming an FPGA using VHDL allows an individual to access the lowest abstraction level of the system during FPGA development. This level of abstraction is referred to as the register-transfer level (RTL), which gives access to manipulating values and variables at the register level. This register-level manipulation provides precision over creating the logical circuit within the FPGA, thus minimizing the required code to perform desired operations. The Modbus RTU communication protocol can be implemented within an FPGA using VHDL programming to establish a standardized and embedded serial communication pathway. This implementation provides a standardized communication protocol to streamline research efforts among researchers, thus increasing the efficiency of research efforts. Additionally, this Modbus RTU implementation requires fewer resources when compared to typical communication protocol implementations that utilize an IP core, reducing the hardware requirement for effective research efforts.

communication↗

Nanocellulose as an embedding matrix and applications thereof

A versatile drug delivery system comprised of plant-based nanocellulose can be used for providing high loading and extended release for virtually any drug. This system is made from nanocrystalline cellulose chemically cross-linked to form a hydrogel. This versatile hydrogel-based drug delivery system can be functionalized to support extended release of oral dosing, relieving patient burden and increasing quality of life.

Ray, Anamika↗

Field Programmable Gate Array Data Capture for Control Systems

Some Industrial Control Systems (ICS) networks are based on protocols such as Serial and Industrial Ethernet. These protocols currently have no existing cybersecurity monitoring tools, leaving a large gap in the cyber defense of critical infrastructure. In order to analyze such ICS traffic, it is first necessary to implement methods of capturing the ICS data. Whereas traditional methods of analyzing data would use microprocessors, the nature of high-speed analog data can be difficult to implement on such a versatile processor, as they are rather inefficient for doing a single task. Whereas Field Programmable Gate Arrays (FPGAs) provide an adequate tool in analyzing high speed data, as despite the lack of program versatility, Programmable Logic can implement a solution with minimal clock cycles, allowing time for each new packet of data to be captured before a new data sample is taken.

42 ENGINEERING↗

The influence of nitrogen and nitrides on the structure and properties of proton irradiated ferritic/martensitic steel

The 12Cr1MoWV (wt%) ferritic/martensitic steel HT9 is a candidate material for fuel cladding in advanced nuclear reactors, such as the Versatile Test Reactor currently under development. As such, understanding the relationship between microstructure and mechanical properties in the context of irradiation environments for these steels is critical. N content, and more specifically interstitial N, has been hypothesized to be detrimental to irradiated properties at lower temperatures (less than 0.3T m ) to a total of 6 dpa; however, in this work at a dose of 1 dpa the irradiated microstructure was improved with added N, leading to less irradiation hardening. Three variants of HT9 were irradiated with 1.5 MeV protons to a dose of 1 dpa at 300°C. The HT9 variants included Low (10 ppm), Mid (190 ppm), and High (440 ppm) N alloys that were otherwise nearly identical. Changing the N content had a variety of effects on the irradiated defect structures. As N content increased, the average dislocation loop diameter decreased, while the number density of loops increased. Additionally, extensive Ni clustering was observed on dislocations and interfaces. The Mid and High N specimens exhibited significantly less hardening (ΔHV≃100) relative to the Low N specimen (ΔHV≃160). The decrease in hardening is attributed to vanadium carbonitride acting as a sink for Ni clusters that would otherwise form on dislocations. Under the irradiation conditions used, these results suggest increasing the N content in HT9 may have a desirable effect on the irradiated structure and properties at the dose studied, as well as the swelling resistance at higher doses. In other words, N content appears to be a powerful tool for tailoring the self-interstitial atom cluster mobility in F/M steels for different temperature and dose applications.

36 MATERIALS SCIENCE↗

Simulation of natural circulation cartridge loop experiments and application to molten salt reactors

This work uses the TRAC/RELAP Advanced Computational Engine (TRACE) thermal hydraulics (TH) code to model natural circulation cartridge loop experiments previously conducted at Oak Ridge National Laboratory (ORNL) using water and compares the simulated and experimental results. TRACE is also used to characterize natural circulation in the cartridge loop vehicle using FLiNaK as the working fluid. The experimental vehicle is a buoyancy-aided, annular cartridge loop, referred to as a thermosyphon, and is designed to aid in qualifying liquid–fueled and/or liquid–cooled irradiation experiments for the Versatile Test Reactor (VTR), which is currently being designed in the United States. Out-of-pile water experiments have been conducted using the cartridge and the Thermosyphon Test Loop facility at ORNL, and future experiments are anticipated that would use other molten salt surrogates as the working fluid, followed by eventual insertion of a similar cartridge into VTR. Additionally, this work aims to determine how well TRACE can replicate the natural convection conditions that were observed experimentally; this serves as an initial step for validating the modeling tool for design and safety calculations to support future irradiation experiments in VTR. Initial predictions of potential experiments were made using FLiNaK as the natural circulation fluid to demonstrate the relevance of the cartridge design to molten salt reactors (MSRs). Results from this study indicate that TRACE can accurately capture natural convection phenomena in the thermosyphon and that several design changes to the current cartridge vehicle are necessary to achieve hydraulic conditions similar to those expected in MSRs.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗

Integrating Advanced Modeling and Accelerated Testing for a Modernized Fuel Qualification Paradigm

With the increasing interest in sodium fast reactor technology, as seen by applications to the U.S. Nuclear Regulatory Commission for the OKLO Aurora plant, fuel testing for the TerraPower Traveling Wave Reactor, and the impending construction and startup of the versatile test reactor (VTR), a modernized, accelerated approach to fuel qualification is needed. To guide this effort, a Phenomena Identification Ranking Table–styled analysis was performed for a U-Pu-Zr sodium-free annular fuel system. This analysis evaluated a series of fuel design properties and parameters against their contributions to key fuel performance phenomena. The resulting priority parameters were then reviewed against existing modeling and experimental capabilities to support investigation of the highest-priority parameters. A pathway for qualification was then established using highthroughput, high-volume experiments from MiniFuel and FAST in parallel with advanced physics-based model development. This effort outlines how the first stages of qualification can be reduced from the typical 20+-year development cycle to 5 to 7 years by deploying accelerated irradiation testing platforms. As with any accelerated test, these methods are prototypic in some aspects and less so in others; however, by coupling with advanced fuel performance modeling and simulation capabilities, the larger space of irradiation parameters and material response provided offers advantages for the validation of physics-based models supporting the deployment of novel fuel designs. As a test case, this paper utilizes a proposed Mark II fuel system for the upcoming VTR. Thus, an accelerated qualification method can be tested for the development of MARK II driver fuel so that by the time of VTR startup, lead test assemblies for a Mark II fuel can be initiated.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

Monte Carlo Analysis of Coolant Stream Impurity Gamma Emissions in Gas-Cooled Fast Reactors

It is well established that a rapid increase in the concentration of fission products in the reactor coolant stream can serve as an early indication of fuel failure. We use Monte Carlo simulations to investigate the feasibility of using several gamma detectors as diagnostic equipment to monitor the presence of major fission product isotopes in high-temperature gas-cooled reactor (HTGR) coolant streams for early detection of fuel failure and therefore the prevention of fuel failure conditions. Herein we model the response of high-purity germanium (HPGe), CdZnTe, NaI(Tl), and LaBr 3 (Ce) detectors of typical commercial sizes to the gamma emissions from nuclides expected to be found within the coolant stream of the Versatile Test Reactor (VTR) under development by the U.S. Department of Energy. The results indicate that for the 233- and 250-keV gamma rays from 133 Xe and 135 Xe, respectively, the 3σ detection criterion is met in under 1 min using a single HPGe detector. Changes in other spectral lines associated with Xe nuclides are detected within 1 h regardless of the choice of detector.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗