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DOE OSTI2017

SECARB Report on Post-Injection In-Situ Monitoring

The Southeast Carbon Sequestration Partnership Phase III Anthropogenic Test at Citronelle Field is the United States’ largest prototype of commercial CO 2 capture from a coal-fired power station and transportation, injection, storage and monitoring. This report focuses on the results of the post-injection monitoring period for the Anthropogenic Test. Monitoring methods include both direct and indirect measurements. The Class V Experimental Permit requires extensive monitoring of injected CO 2 at the surface and at deep and shallow depths. The safety, integrity and information objectives of the CO 2 monitoring plan are in place to: (1) create and sustain wellbore integrity; (2) assure safe CO 2 injection operations; (3) verify the location and migration of the injected CO 2 plume; and (4) monitor for any CO 2 leakage. A robust suite of monitoring approaches is utilized for the in-situ monitoring and include, pressure monitoring, various seismic surveys, pulsed neutron logging, reservoir fluid sampling and injection surveys. Data and observations collected using these monitoring methods will be used in the numerical model to inform the post-injection site care monitoring plan. This report describes actions pertaining to in situ monitoring at the Anthropogenic Test Site that were undertaken during the period of September 2014 to May 2016. These monitoring techniques include the acquisition of pressure data, seismic data, pulsed neutron capture logs, reservoir fluid sampling, and tracer gas monitoring. CO 2 injection operations began on August 20, 2012 and terminated on September 1, 2014.

01 COAL, LIGNITE, AND PEAT↗

DOE OSTI2022

Detection of Damage Inducing Impact Events in Vibration Test Fixtures Using Holder Exponents

The Shock and Vibration team within the Test Engineering group at Los Alamos National Laboratory (LANL) aids in the development and qualification of weapon systems for the United States Department of Energy (DOE). Performing tests that replicate shock and vibration environments representative of a weapon’s lifetime is critical in ensuring safety, survivability, and reliability. A key factor in shock and vibration testing is accurate representation of the weapon’s boundary conditions in its end use configuration. The boundary conditions representative of a reentry body in flight are particularly difficult to replicate on an electrodynamic shaker. When executing shock and vibration tests on a reentry body, two system axes are tested with the system in a cantilevered configuration. This cantilevered testing configuration results in a moment load being applied to the system while undergoing vibration environments. A special fixture, known as the Flex-Web, was developed to decouple this moment load from the reentry body in order to more accurately represent real world boundary conditions while replicating flight environments.

42 ENGINEERING↗

DOE OSTI2017

Comparison of a Micro-Neutralization Test with the Rapid Fluorescent Focus Inhibition Test for Measuring Rabies Virus Neutralizing Antibodies

The rapid fluorescent focus inhibition test (RFFIT) is routinely used in the United States to measure rabies virus neutralizing antibodies (rVNA). RFFIT has a long history of reproducible and reliable results. The test has been modified over the years to use smaller volumes of reagents and samples, but requires a 50 µL minimum volume of test serum. To conduct pathogenesis studies, small laboratory animals such as mice are regularly tested for rVNA, but the minimum volume for a standard RFFIT may be impossible to obtain, particularly in scenarios of repeated sampling. To address this problem, a micro-neutralization test was developed previously. In the current study, the micro-neutralization test was compared to the RFFIT using 129 mouse serum samples from rabies vaccine studies. Using a cut-off value of 0.1 IU/mL, the sensitivity, specificity, and concordance of the micro-neutralization test were 100%, 97.5%, and 98%, respectively. The geometric mean titer of all samples above the cut-off was 2.0 IU/mL using RFFIT and 3.4 IU/mL using the micro-neutralization test, indicating that titers determined using the micro-neutralization test are not equivalent to RFFIT titers. Based on four rVNA-positive hamster serum samples, the intra-assay coefficient of variability was 24% and inter-assay coefficient of variability was 30.4%. These results support continued use of the micro-neutralization test to determine rabies virus neutralizing antibody titers for low-volume serum samples.

59 BASIC BIOLOGICAL SCIENCES↗

DOE OSTI2019

Execution of an Alternative Modeling Strategy for Closure of the Rainier Mesa Corrective Action Unit at the Nevada National Security Site - 19099

The Underground Test Area (UGTA) Project of the U.S Department of Energy (DOE) is investigating radionuclide contaminant movements in groundwater derived from a decades-long period of underground nuclear testing at the Nevada National Security Site (NNSS) to support regulatory corrective action and closure requirements. The project is built around an integrated campaign of drilling and sampling, data interpretation, computer modeling, and broader monitoring activities conducted under a joint Federal Facilities Agreement and Consent Order (1996 as amended) (FFACO) between the State of Nevada, the DOE, and the U.S. Department of Defense. The FFACO strategy is applied to individual Corrective Action Units (CAUs) that roughly envelop disparate geographic testing areas at the NNSS. The Rainier Mesa/Shoshone Mountain (RMSM) CAU is a geologically and hydrologically complex system lying in a remote up-gradient section of the NNSS. It was the site of 67 underground tests conducted between 1957 and 1992, 61 at Rainier Mesa proper, and 6 at Shoshone Mountain, isolated to its south. The original strategy to close the RMSM CAU required a simulation-based investigation to define the evolution of contaminated volumes of groundwater (in 3D) under uncertainty as a means to define a surface-projected contaminant boundary and to serve as a basis for longer term monitoring activities. Early models developed under this strategy proved to be quite complex and difficult to calibrate. Additional costs required to better characterize the system were judged to be out of balance with the low risks associated with this particular CAU. As a result, an Alternative Modeling Strategy (AMS) was adopted. The AMS removes the requirement for developing ensembles of 3D simulations and replaces it with a simpler one requiring the generation of multiple 1D streamline models. These are meant to encompass a range of alternative, yet plausible release and transport scenarios as a means to bound the overall lateral extent of contaminant transport. This paper will review the modeling approach developed under the AMS and its application to the Rainier Mesa portion of the CAU. Preliminary model results made under different parametric assumptions and boundary condition scenarios will be presented. Additional refinements of the model and its further application will be discussed. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

DOE OSTI2025

A Safe Response to Renewable Energy Hazards

The International Association of Fire Fighters (IAFF) and Underwriters Laboratories, LLC (UL) in conjunction with UL Solutions initiated a joint project in 2022 under an agreement with the United States Department of Energy-Office of Energy Efficiency and Renewable Energy (DOE-EERE). This project focused on two separate and important initiatives related to energy efficiency in residential buildings. Initiative 1: Fire Performance on Energy Efficient Exterior Walls. Initiative 2: Firefighting Tactics in Residential Properties with Building Energy Storage Systems (BESS). The project’s first initiative addresses concerns surrounding new technologies with enhanced, energy-efficient exterior walls installed on residential properties. The concerns of fire rapidly traveling vertically up the exterior of these walls were examined. This addressed a growing concern from the first responder community that many times, the fires on the exterior of residential buildings have already evolved into an attic fire by the time of arrival – making it problematic to address the fire scenario. The test plan for Initiative 1 incorporated a modified version of an American Society for Testing and Materials (ASTM) test method, ASTM E2707, Standard Test Method for Determining Fire Penetration of Exterior Wall Assemblies Using a Direct Flame Impingement Exposure, as the foundation of the research. The test method involved a wall structure intended to represent retrofit construction to evaluate how fire would spread vertically or laterally. The second aspect of the UL-IAFF Project focuses on the fire service response to Residential Battery Energy Storage System (RBESS) incidents. These simulation tests were constructed in the large-scale fire test facility at UL Solutions’ Northbrook, IL campus. A baseline test was conducted that involved a test structure with no batteries—shelving units populated with standardized commodities, representing a typical garage with cellulosic and plastic contents. Three additional tests have been conducted to generate data with the contribution of energy storage system (ESS) batteries to compare fire and explosion hazards against the baseline test. Through this work, fire service tactical considerations can be explored. From the data, the team can determine 1) the visual indicators of a residential fire that has involved an RBESS (or, potentially, other large batteries) and 2) the impact of fire service-initiated ventilation of the structure on the fire conditions and explosion risks.

32 ENERGY CONSERVATION, CONSUMPTION, AND UTILIZATI↗

DOE OSTI2018

The Giants of the Nuclear Testing Era: The Works of Robert K. Osborne

Dr. Robert (Bob) Kidder Osborne was a key physicist and nuclear weapons designer—a giant, in fact, in the sense of Isaac Newton’s use of the term—at Los Alamos National Laboratory (LANL) during the days of weapons designing and testing (1943–1992). (See figure 1.) His career began a few short years after the end of World War II, in August 1949, and spanned over 30 years. He retired from the Laboratory in March 1981. During his career, the United States was designing, building, and testing new nuclear weapons at a prodigious rate. Most of these designs were tested using full-scale nuclear tests (like Operation Plumbbob - Franklin Prime, shown in figure 2). Designers, like Osborne, relied on the results of these tests to prove, and improve, their designs. These improved designs led to developing weapons that contributed to a growing stockpile, which reached its numerical peak in 1967.1 Osborne was a major figure in the development of these advanced weapons designs. He was also largely responsible for the Laboratory’s development of one-point safety, hydronuclear testing, and he was the lead designer of the primary for the W76 nuclear warhead, which is the most numerous warhead in the current U.S. stockpile. Osborne was also an important mentor to many of the Laboratory’s weapons designers.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

DOE OSTI2015

SECARB Annual Report on In-Situ Monitoring Program

The Southeast Carbon Sequestration Partnership Phase III Anthropogenic Test at Citronelle Field is the United States’ largest prototype of commercial CO 2 capture from a coal-fired power station and transportation, injection, storage and monitoring. This report details the results of the second and third year of injection monitoring results for the Anthropogenic Test. Monitoring methods include both direct and indirect measurements. The Class V Experimental Permit requires extensive monitoring of injected CO 2 at the surface and at deep and shallow depths. The safety, integrity and information objectives of the CO 2 monitoring plan are in place to: (1) create and sustain wellbore integrity; (2) assure safe CO 2 injection operations; 3) verify the location and migration of the injected CO 2 plume; and (4) monitor for any CO 2 leakage. A robust suite of monitoring approaches are utilized for the insitu monitoring and include, pressure monitoring, various seismic surveys, pulsed neutron logging, reservoir fluid sampling and injection surveys. Data and observations collected using these monitoring methods will be used in the numerical model to inform the post-injection site care monitoring plan. This report describes actions pertaining to in situ monitoring at the Anthropogenic Test Site that were undertaken during the period of October 2013 to January 2015. This report details the results of the second and third year of injection monitoring results for the Anthropogenic Test. Work Product 9.2.2.b details the shallow monitoring results for 2014. CO 2 injection operations began on August 20, 2012 and terminated on September 1st 2014.

01 COAL, LIGNITE, AND PEAT↗

DOE OSTI2015

SECARB Annual Report on In-Situ Monitoring Program

The Southeast Carbon Sequestration Partnership Phase III Anthropogenic Test at Citronelle Field is the United States’ largest prototype of commercial CO 2 capture from a coal-fired power station and transportation, injection, storage and monitoring. This report details the results of the background and first year of injection monitoring results for the Anthropogenic Test. Monitoring methods include both direct and indirect measurements. The Class V Experimental Permit requires extensive monitoring of injected CO 2 at the surface and at deep and shallow depths. The safety, integrity and information objectives of the CO 2 monitoring plan are in place to: (1) create and sustain wellbore integrity; (2) assure safe CO 2 injection operations; 3) verify the location and migration of the injected CO 2 plume; and (4) monitor for any CO 2 leakage. A robust suite of monitoring approaches are utilized for the in-situ monitoring and include, pressure monitoring, various seismic surveys, pulsed neutron logging, reservoir fluid sampling and injection surveys. Data and observations collected using these monitoring methods will be used in the numerical model to inform the post-injection site care monitoring plan.

01 COAL, LIGNITE, AND PEAT↗

DOE OSTI2020

Alaska North Slope 2018 Hydrate-01 Stratigraphic Test Well: Technical Results

The Hydrate-01 Stratigraphic Test Well was drilled in December 2018 to confirm that a seismically-identified location within the western Prudhoe Bay Unit might be suitable for extended-duration scientific production testing. The well featured the acquisition of a full suite of logging-while-drilling data, collection of side-wall pressure cores, and installation of distributed temperature and distributed acoustic sensor (DTS, DAS) fiber-optic cables. Evaluation of the logging-while-drilling data confirms gas hydrate is present at high saturation in two target sands of high reservoir quality. Acquired logs and samples enable critical petrophysical information to be compiled for input into production models. The well tested two primary targets: the deeper Unit B is highly favorable due to optimal reservoir temperature and minimal observed risk for direct communication with permeable, hydrate-free water-bearing zones. The shallower Unit D provides a secondary target and opportunity to

Boswell, Ray↗

DOE OSTI2016

SDU6 Interior Liner Testing & Evaluation

Two liner materials (Marseal® M-3500 and REMA Chemoline® 4CN) proposed for use as a liner inside the Saltstone Disposal Unit 6 (SDU6) were subjected to specific ASTM tests (tensile and lap-shear) after immersion in 50% and 100% simulant solutions for 1000 hours at the Savannah River Ecology Laboratory. Both liner materials exhibited good resistance to the simulant chemistry, at least based on the tests performed and the test duration/conditions imposed. In lap-shear tests, both materials failed in the base material rather than peeling apart, confirming good adhesion. The REMA 4CN bromobutyl elastomer showed superior bonding characteristics and absence of warping or delamination at the conditions tested. The Marseal M-3500 material (PVC/EVA blend with polyester reinforcement) exhibited deformation and debonding in some locations. The cause of the deformation and delamination observed in the Marseal M-3500 material is not fully known, but possibly attributed to thermomechanical stress at immersion temperatures, and the thermoplastic nature of the material. The immersion temperature (68 °C) is slightly greater than the maximum use temperature limit quoted for the Marseal M- 3500 liner (65 °C), though the basis for the service limit is unknown. The testing performed was limited in scope and only for these two liner materials. These tests were primarily performed to screen for severe incompatibility or short-term degradation in Saltstone bleedwater simulants at bounding solution temperatures. Additional testing is recommended to assess long-term performance and the overall service life of the liner.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

DOE OSTI2018

20 Channel Quench Detector

A multi-channel quench detector is useful for troubleshooting of prototype HTC superconducting magnets with current lead connections and imbedded splices. There are commercially available quench detectors, but not with as many channels, or with the particular functionality of this unit. This unit was designed specifically for cold testing of a superconducting sextupole prototype, which is wound with many turns of HTC ribbon. Associated with the current lead connections and the imbedded splices are 18 voltage taps, thus 17 quench detection channels are required to monitor the condition of the magnet. Of the 20 differential input channels in this quench detection unit, 19 are configured in a ladder network. The 20th channel is isolated and can be connected across any pair of voltage taps. This quench detector is designed to be used to monitor the condition of a series-connected superconducting magnet powered by a unipolar supply, and therefore the polarity and sequence of the voltage taps must be observed. There are 20 toggle switches and 20 red LEDs on the front panel of the unit which are associated with the 20 quench detection channels. There are also 2 green LEDs to indicate the state of the +5 V and +25 V internal supplies. Channel input impedance is ~10 kΩ. The input lines are diode protected against negative voltage transients and can tolerate up to +25 V, which is greater than the compliance of supplies typically used to power superconducting magnets. The front panel switches are used to enable or disable individual channels. If a channel is not used it is disabled. There are 20 pots on the quench detector PCB. They provide adjustment for the sensitivity of each of the 20 channels. There is an onboard reference to facilitate channel sensitivity calibration. The detection sensitivity range is from ~27 mV to ~700 mV. Typically all channels are set for the same sensitivity. The response time is ~20 μs, but the time constant can be increased if desired by adding a single capacitor to each channel. When the magnet under test is cooled to the superconducting state and the supply current to the windings is slowly ramped up to the set point, if there is a voltage rise across a pair of voltage taps which exceeds the quench detection limit of a given channel, then the front panel LED for that channel illuminates and all other channels are disabled within ~25 ns. Thus only the first quench is detected for the channels which are enabled. A pushbutton switch on the front panel is used to reset a quench detection. A 25 pin D-subminiature connector on the back of the unit is used for the channel inputs. TTL level ‘quench’ and ‘quench-not’ signals, and DPDT relay contacts, are provided through a 9 pin D-subminiature connector on the back to indicate a detected quench condition, which could be used to disable the power supply and engage an energy absorber.

47 OTHER INSTRUMENTATION↗

DOE OSTI2017

Simulation-based Testing of Control Software

It is impossible to adequately test complex software by examining its operation in a physical prototype of the system monitored. Adequate test coverage can require millions of test cases, and the cost of equipment prototypes combined with the real-time constraints of testing with them makes it infeasible to sample more than a small number of these tests. Model based testing seeks to avoid this problem by allowing for large numbers of relatively inexpensive virtual prototypes that operate in simulation time at a speed limited only by the available computing resources. In this report, we describe how a computer system emulator can be used as part of a model based testing environment; specifically, we show that a complete software stack including operating system and application software - can be deployed within a simulated environment, and that these simulations can proceed as fast as possible. To illustrate this approach to model based testing, we describe how it is being used to test several building control systems that act to coordinate air conditioning loads for the purpose of reducing peak demand. These tests involve the use of ADEVS (A Discrete Event System Simulator) and QEMU (Quick Emulator) to host the operational software within the simulation, and a building model developed with the MODELICA programming language using Buildings Library and packaged as an FMU (Functional Mock-up Unit) that serves as the virtual test environment.

97 MATHEMATICS AND COMPUTING↗

DOE OSTI2016

A superconducting direct-current limiter with a power of up to 8 MVA

A resistive switching superconducting fault current limiter (SFCL) for DC networks with a nominal voltage of 3.5 kV and a nominal current of 2 kA was developed, produced, and tested. The SFCL has two main units—an assembly of superconducting modules and a high-speed vacuum circuit breaker. The assembly of superconducting modules consists of nine (3 × 3) parallel–series connected modules. Each module contains four parallel-connected 2G high-temperature superconducting (HTS) tapes. The results of SFCL tests in the short-circuit emulation mode with a maximum current rise rate of 1300 A/ms are presented. The SFCL is capable of limiting the current at a level of 7 kA and break it 8 ms after the current-limiting mode begins. The average temperature of HTS tapes during the current-limiting mode increases to 210 K. After the current is interrupted, the superconductivity recovery time does not exceed 1 s.

75 CONDENSED MATTER PHYSICS, SUPERCONDUCTIVITY AND↗

DOE OSTI2019

Developing and Testing a New Gas Distribution System for the Fluidized Bed of the Integrated Waste Treatment Unit (IWTU) Steam Reformer - 19219

The Integrated Waste Treatment Unit (IWTU) has been tasked with using steam reforming technology to treat 3.4 million liters of radioactive sodium-bearing waste (SBW) at the INL. Progress in developing steam reforming for SBW treatment has been hampered by numerous processing issues associated with the existing process equipment during simulant testing. The primary issue was high differential temperatures that developed in the fluidized bed of the denitration mineralization reformer (DMR). Based on technical evaluations and computer modeling, it was determined that the primary cause of poor fluidization in the DMR was the existing fluidized gas distributor. This distributor consisted of a combination of a ring header and four removable fluidizing gas rails. The combined ring header/rail system was unable to effectively fluidize the bed at the bottom of the DMR (around and below the ring header). As a result, a decision was made to design and test a new fluidized gas distributor. Conceptual designs focused on three different distributors: a modified design of the current system; a flat plate with bubble caps; and a conical bottom with dual plena. After testing the conceptual prototypes at Hazen Research Inc., the conical bottom distributor was chosen. A 30-day test with simulant SBW feed was then performed with the new distributor. During testing, a temperature differential of less than 2 deg. C was maintained in the DMR fluidized bed. The results supported the conclusion that poor fluidized gas distribution was the primary cause of high temperature differentials in the DMR fluidized bed. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

DOE OSTI2015

Explicit integration with GPU acceleration for large kinetic networks

We demonstrate the first implementation of recently-developed fast explicit kinetic integration algorithms on modern graphics processing unit (GPU) accelerators. Taking as a generic test case a Type Ia supernova explosion with an extremely stiff thermonuclear network having 150 isotopic species and 1604 reactions coupled to hydrodynamics using operator splitting, we demonstrate the capability to solve of order 100 realistic kinetic networks in parallel in the same time that standard implicit methods can solve a single such network on a CPU. This orders-of-magnitude decrease in computation time for solving systems of realistic kinetic networks implies that important coupled, multiphysics problems in various scientific and technical fields that were intractable, or could be simulated only with highly schematic kinetic networks, are now computationally feasible.

71 CLASSICAL AND QUANTUM MECHANICS, GENERAL PHYSIC↗

DOE OSTI2013

Scaling considerations for a multi-megawatt class supercritical CO2 brayton cycle and commercialization.

Small-scale supercritical CO2 demonstration loops are successful at identifying the important technical issues that one must face in order to scale up to larger power levels. The Sandia National Laboratories supercritical CO2 Brayton cycle test loops are identifying technical needs to scale the technology to commercial power levels such as 10 MWe. The small size of the Sandia 1 MWth loop has demonstration of the split flow loop efficiency and effectiveness of the Printed Circuit Heat Exchangers (PCHXs) leading to the design of a fully recuperated, split flow, supercritical CO2 Brayton cycle demonstration system. However, there were many problems that were encountered, such as high rotational speeds in the units. Additionally, the turbomachinery in the test loops need to identify issues concerning the bearings, seals, thermal boundaries, and motor controller problems in order to be proved a reliable power source in the 300 kWe range. Although these issues were anticipated in smaller demonstration units, commercially scaled hardware would eliminate these problems caused by high rotational speeds at small scale. The economic viability and development of the future scalable 10 MWe solely depends on the interest of DOE and private industry. The Intellectual Property collected by Sandia proves that the ~10 MWe supercritical CO2 power conversion loop to be very beneficial when coupled to a 20 MWth heat source (either solar, geothermal, fossil, or nuclear). This paper will identify a commercialization plan, as well as, a roadmap from the simple 1 MWth supercritical CO2 development loop to a power producing 10 MWe supercritical CO2 Brayton loop.

Fleming, Darryn D.↗

DOE OSTI2020

Structures, Systems, and Components Classification Criteria for the Versatile Test Reactor

The Versatile Test Reactor (VTR) is a fast spectrum test reactor currently being developed in the United States under the direction of the US Department of Energy (DOE), Office of Nuclear Energy. The VTR mission is to enable accelerated testing of advanced reactor fuels and materials required for advanced reactor technologies. The conceptual design of the 300 MWth sodium-cooled metallic-fueled pool-type fast reactor has been led by the U.S. National Laboratories in collaboration with General Electric-Hitachi and Bechtel National Inc. As part of the VTR authorization process by the DOE, it is necessary to identify the safety classification of structures, systems, and components (SSCs) to determine the proper design, surveillance, operation, and incident-reporting requirements. Since VTR is utilizing a risk-informed, performance-based authorization process based on the Licensing Modernization Project (LMP) described in NEI 18-04 [1], the criteria for SSC classification, which are reviewed here, includes both risk information from the probabilistic risk assessment (PRA) and prescriptive requirements.

Grabaskas, David↗

DOE OSTI2016

PRELIMINARY RESULTS OF THE AGC-4 IRRADIATION IN THE ADVANCED TEST REACTOR AND DESIGN OF AGC-5 (HTR16-18469)

The United States Department of Energy’s Advanced Reactor Technologies (ART) Program will irradiate up to six nuclear graphite creep experiments in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL). The graphite experiments are being irradiated over an approximate eight year period to support development of a graphite irradiation performance data base on the new nuclear grade graphites now available for use in high temperature gas reactors. The goals of the irradiation experiments are to obtain irradiation performance data, including irradiation creep, at different temperatures and loading conditions to support design of the Very High Temperature Gas Reactor (VHTR), as well as other future gas reactors. The experiments each consist of a single capsule that contain six stacks of graphite specimens, with half of the graphite specimens in each stack under a compressive load, while the other half of the specimens are not be subjected to a compressive load during irradiation. The six stacks have differing compressive loads applied to the top half of diametrically opposite pairs of specimen stacks. A seventh specimen stack in the center of the capsule does not have a compressive load. The specimens are being irradiated in an inert sweep gas atmosphere with on-line temperature and compressive load monitoring and control. There are also samples taken of the sweep gas effluent to measure any oxidation or off-gassing of the specimens that may occur during initial start-up of the experiment. The first experiment, AGC-1, started its irradiation in September 2009, and the irradiation was completed in January 2011. The second experiment, AGC-2, started its irradiation in April 2011 and completed its irradiation in May 2012. The third experiment, AGC-3, started its irradiation in late November 2012 and completed in the April of 2014. AGC-4 is currently being irradiated in the ATR. This paper will briefly discuss the preliminary irradiation results of the AGC-4 experiment, as well as the design of AGC-5.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗