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At least 667 records · Page 37

Complete Report on the Development of Welding Parameters for Irradiated Materials

The advanced welding facility at the Radiochemical Engineering Development Center of Oak Ridge National Laboratory, which was conceived to enable research and development of weld repair techniques for nuclear power plant life extension, is now operational. The development of the facility and its advanced welding capabilities, along with the model materials for initial welding trials, were funded jointly by the U.S. Department of Energy, Office of Nuclear Energy, Light Water Reactor Sustainability Program, the Electric Power Research Institute, Long Term Operations Program and the Welding and Repair Technology Center, with additional support from Oak Ridge National Laboratory. Welding of irradiated materials was initiated on November 17, 2017, which marked a significant step in the development of the facility and the beginning of extensive welding research and development campaigns on irradiated materials that will eventually produce validated techniques and guidelines for weld repair activities carried out to extend the operational lifetimes of nuclear power plants beyond 60 years. This report summarizes the final steps that were required to complete weld process development, initial irradiated materials welding activities, near-term plans for irradiated materials welding, and plans for post-weld analyses that will be carried out to assess the ability of the advanced welding processes to make repairs on irradiated materials.

36 MATERIALS SCIENCE↗

Successful Completion of FY18/Q1 ASC L2 Milestone 6355: Electrical Analysis Calibration Workflow Capability Demonstration.

The Sandia Analysis Workbench (SAW) project has developed and deployed a production capability for SIERRA computational mechanics analysis workflows. However, the electrical analysis workflow capability requirements have only been demonstrated in early prototype states, with no real capability deployed for analysts’ use. This milestone aims to improve the electrical analysis workflow capability (via SAW and related tools) and deploy it for ongoing use. We propose to focus on a QASPR electrical analysis calibration workflow use case. We will include a number of new capabilities (versus today’s SAW), such as: 1) support for the XYCE code workflow component, 2) data management coupled to electrical workflow, 3) human-in-theloop workflow capability, and 4) electrical analysis workflow capability deployed on the restricted (and possibly classified) network at Sandia. While far from the complete set of capabilities required for electrical analysis workflow over the long term, this is a substantial first step toward full production support for the electrical analysts.

42 ENGINEERING↗

Completion of a Chlorination Test Using 250 grams of High-Burnup Used Fuel Cladding from a North Anna Pressurized Water Reactor

A second large -scale chlorination test was completed in February 2017 by chlorinating 250 g of used nuclear fuel (UNF) cladding from a North Anna pressurized water reactor (PWR). Analytical results and a Zr mass balance from this test are described and compared with previous results obtained by the Zirconium Recovery and Recycle Project.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

Laboratory Directed Research and Development Program - FY 2017 ORNL Annual Summary of Completed Projects

This report includes summaries of all ORNL LDRD research activities completed by September 30, 2017. It is sent to the ORNL Technical Officer for export control review and classification review prior to being delivered to the Office of Scientific and Technical Information. LDRD is a relatively small but vital program whose purpose is to meet the DOE mission. It allows ORNL and other DOE laboratories to improve their distinctive capabilities and to enhance their ability to conduct cutting-edge R&D for DOE and SPP sponsors. R&D projects funded through LDRD support the following general goals: maintain the scientific and technical vitality of the Laboratory; enhance the Laboratory’s ability to address future DOE missions; foster creativity and stimulate exploration of forefront areas of science and technology; serve as a proving ground for new concepts in R&D; and support high-risk, potentially high-value R&D. ORNL has established a program with three components to meet its LDRD objectives and to fulfill the particular needs of the Laboratory: the Director’s R&D Fund, the Seed Money Fund, and the Distinguished Fellowship Fund (Householder, Russell, Weinberg, and Wigner Fellowships). As outlined in Table 1, these three funds are complementary. The Director’s R&D Fund develops new capabilities in support of the Laboratory initiatives, the Seed Money Fund is open to all innovative ideas that have the potential for enhancing the Laboratory’s core scientific and technical competencies, and the Distinguished Fellowship Fund allows the Laboratory to hire exceptional early career scientists to refresh its scientific and technical capabilities. Provision for multiple routes of access to ORNL LDRD funds maximizes the likelihood that novel ideas with scientific and technological merit will be recognized and supported.

99 GENERAL AND MISCELLANEOUS↗

Report on the completion of the development of processing map from as-cast Alloy 709 materials

This report provides details on the completion of the development of the processing map from the as-cast Alloy 709 materials. The report is a Level 4 deliverable in FY18 (M4NT18AN050502012), under the Work Package NT-18AN05050201, “A709 Development” performed by Argonne National Laboratory, as part of Advanced Structural Materials Program for the Advanced Reactor Technologies (ART). The report describes the development of a processing map to guide the development of hot work regimens for A709. The maps combine high-temperature flow stress measurements, described in a companion report by Oak Ridge National Laboratory, and metallographic observations, described here, into a single diagram that can be used to select hot working parameters to avoid regions of plastic instability and to avoid the development of unfavorable microstructures. This report describes the process of creating the map, provides the final map for A709, and uses the processing map to describe two potential hot work regimens that could be used in processing a DOE round ingot into bar stock.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

Partial completion of post-irradiation examination of the ORNL samples

A total of six Grade 92 and two 800H samples were identified and secured as the selected ORNL samples, which were irradiated in the High Flux Isotope Reactor (HFIR) of ORNL to 0.46–14.66 dpa at 400 to ~720°C. The Grade 92 is an optimized heat and named as G92-2b. The two 800H samples have one sample as the standard solution-annealed condition and the other sample as a thermos-mechanically processed (TMP) condition with a maximized fraction of low-Σ coincidence site lattice (CSL) boundaries. Tensile tests were completed for the selected ORNL samples using the Irradiated Materials Examination and Testing (IMET) hot cell facility at ORNL. The G92-2b samples were tested at room temperature. The lower temperature irradiation at 400–496.7°C to 0.52–14.66 dpa resulted in minimal changes in tensile properties. However, the higher temperature irradiation at ~683.3–720°C to 0.46–14.63 dpa tended to reduce yield and tensile strength by about –136 to –311 MPa and plastic elongation with the increasing dose. The 800H and 800H-TMP samples were tensile-tested at their irradiation temperature 580°C, which showed >40% increase in yield and tensile strength with nearly 9% reduction in elongation for 800H-TMP compared with 800H.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

FY19 L2 MRT 6744 Milestone Completion: Digital Time-Resolved Spot Diagnostic (D-TRSD)

This milestone report describes development of the Digital Time-Resolved Spot Diagnostic (D-TRSD) into a functioning diagnostic that has been proven in the laboratory. Laboratory tests complete the MRT 6744 exit criteria with the recording and analysis of a spot size measurement for two consecutive pulses on a two-pulse source. Additional channels will be added in the near future to provide an 84-channel measurement capability. The new modular design is more portable than the previous generations and will be much easier to set up at radiographic facilities across the complex.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

BEE - FY20 P6-3: Release BEEWorkflowManager, BEETaskManager, and client application 2.3.6.01 – LANL ATDM ST / STNS01-4 P6 Milestone Completion Documentation

Release BEEWorkflowManager, BEETaskManager, and client software. The BEEWorkflowManager daemon runs on the HPC cluster login node. It accepts workflows submitted by the BEE client. These workflows are specified using the Common Workflow Language (CWL) standard. The BEEWorkflowManager loads workflows into the Neo4j graph database to create the workflow directed acyclic graph (DAG), and submits the workflow tasks to the BEETaskManager for execution. The BEEWorkflowManager records the state of the workflow and its tasks, and communicates this state to the BEE client. The BEEWorkflowManager will start, pause, and cancel a running workflow and its tasks at the command of the BEE client. The BEETaskManager daemon runs on the HPC cluster login node. It accepts tasks from the BEEWorkflowManager, turns those tasks into HPC resource manager jobs (e.g. a slurm job script), and submits the job to the cluster resource manager. The BEETaskManager then tracks the status of the job (pending, running, complete) and updates the BEEWorkflowManager. The BEETaskManager will also cancel a queued or running job when commanded to do so by the BEEWorkflowManager. The first release of the BEETaskManager will support the Slurm resource manager and the Charliecloud linux container runtime.

97 MATHEMATICS AND COMPUTING↗

BEE - FY20 P6-2: Support for HPC resource managers 2.3.6.01 – LANL ATDM ST / STNS01-6 P6 Milestone Completion Documentation

BEE uses abstract interfaces between core functionality and specific driver code. An example of this is the worker_interface. The worker_interface is used by the BEETaskManager to communicate with the HPC system-specific resource manager (e.g. Slurm) and container runtime (e.g. Charliecloud). BEE initially only supported the Slurm HPC resource manager. This activity will make HPC resource manager support a configurable option. When this activity is complete BEE will support both the Slurm and LSF resource managers.

97 MATHEMATICS AND COMPUTING↗

Evidence of Completion of Milestone 3: Experimental Testbed

Construction and deployment of the experimental testbed encountered scheduling delays, and completion was subsequently further delayed by curtailment of LANL operations due to the COVID–19 pandemic. Between March and October, LANL was in a state of “Limited Operations” such that only certain “mission–critical” work was performed with approximately 25% on–site staffing. In spite of this, much of the lab space preparation was executed and the five initial model house” units were constructed and installed during this period. Still, the pace of construction was impacted by difficulty in coordinating personnel and minimizing contact between workers.

24 POWER TRANSMISSION AND DISTRIBUTION↗

Complete Documentation of Applicable Regulations and Regulatory Authority for Transportation

This report fulfills the M4 milestone M4MR-20PN0303023, “Complete Documentation of Applicable Regulations and Regulatory Authority for Transportation. Microreactors are very small nuclear reactors with a power output of 20MWe or less and are designed to be factory-built, modular in nature, and highly portable. The objective of this report is to identify and document applicable regulations, the appropriate regulatory authority, and the associated framework for microreactor transport. Sections 2 and 3 of this report summarize U.S. Department of Transportation (DOT) and NRC regulations related to the transportation of Class 7 (radioactive) materials. These sections concentrate on the transport of fissile material packages and Type B packages, which would be most applicable to the transport of a microreactor before and after irradiation. Section 4 summarizes DOE hazardous and radioactive material transportation regulations. Section 5 summarizes U.S. Coast Guard regulations related to the transport of radioactive material. Section 6 discusses state requirements for the permitting of oversize and/or overweight truck shipments. Section 7 presents detailed schedules of requirements for transporting fissile material packages and Type B packages based on NRC and DOT regulations. The schedules are presented in a two-column format, the right column is the regulatory requirement and the left column is the citation of the regulation in which the requirement is found.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Complete spectroscopy in the attosecond regime

Harnessing light waveforms at attosecond time scales provides information of the structure and dynamics of matter on it's natural time scales. For this reason attosecond metrology has been at the forefront of the optical sciences for more than a decade, and it represents the latest time-domain frontier of the quantum world. Attosecond light pulses are commonly generated using higher-order harmonic generation (HHG) , a process capable of generating XUV coherent pulses. In addition to generate attosecond pulses, HHG can be used to study the structure and dynamics of atoms and molecules by analyzing the spectral content of the XUV pulses. This approach is known as HHG spectroscopy and it provides a coherent, time-dependent approach to study structure and dynamics in the quantum world. In this proposal we will generate harmonics from two optical foci produced by a system of a two-dimensional spatial light modulator (SLM) and a lens. In the far eld the train of attosecond pulses will interfere creating harmonic-dependent fringes. The position of such fringes is a direct measurement of the relative phase between the two foci and they also carry information about the quantum state of the target atom or molecule. Therefore, by measuring the amplitude and relative phase of the emitted harmonics we will have access to both, the amplitude and phase of the dipole moments of the studied target. Because the two beams are completely indistinguishable from each other up to a few millimeters from the focus, both driving pulses share the exact beam path. So far we have measured a jitter of 700 zeptoseconds with a 12.5 attosecond resolution in the delay control of the two foci. These two time scales represent some of the best time controls ever achieved to date.

74 ATOMIC AND MOLECULAR PHYSICS↗

Light Water Reactor Sustainability Program: Complete the weld campaign on Ni-base irradiated materials using stress improved laser welding including the preliminary weld quality inspections

This report summarizes the most recent welding campaign on irradiated Ni-base alloy 182 and the preliminary weld quality inspections at the Radiochemical Engineering Development Center (REDC). Equipment and capabilities were developed jointly by the U.S. Department of Energy, Office of Nuclear Energy, Light Water Reactor Sustainability Program, the Electric Power Research Institute, Long Term Operations Program (and the Welding and Repair Technology Center), and Oak Ridge National Laboratory. Irradiated nickel alloy 182, with target helium contents of 5 atom parts-per million (appm), 10 appm, and 20 appm, were laser welded in the hot cell successfully. The significant, on-going effort to weld irradiated alloys with high helium concentrations and comprehensively analyze the results will eventually yield validated repair techniques and guidelines for use by the nuclear industry in extending the operational lifetimes of nuclear power plants. This report fulfills the FY 2023 milestone M3LW-22OR0406013, “Complete the weld campaign on Ni base irradiated materials using stress improved laser welding including the preliminary weld quality inspections”.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

Two-dimensional quantum gas with real time control of complete Hamiltonian (Final Report)

We developed a novel quantum platform with the complete capability to control individual atoms and their mutual interactions in real time. Ultracold atoms are employed since they have the lowest temperature and decoherence. This system is the ultimate dream of quantum physicists where the Hamiltonian of every single atom, including its kinetic energy, potential energy, and interactions, can be independently programmed in real time. We also initiated a new theoretical collaboration to explore its full potential.

74 ATOMIC AND MOLECULAR PHYSICS↗

Completion of IER 305: Molybdenum Sleeve Experiments and Preparations for Performing IER 441: Epithermal Tantalum Experiments [Slides]

This presentation includes a look into Sandia critical experiments including the 7uPCX, BUCCX, and assembly design. This presentation touches on the completion of IER 305 with CED-3b, CED-4a, and CED-4b. Finally, there are preparations to perform IER 441 including new hardware, critical configurations, and next steps.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗