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At least 1,369 records · Page 76

Design Status of BCC Cryomodule for LCLS-II HE

A Buncher or Capture Cavity (BCC) Cryomodule is currently in development at Fermilab for use in a second injector for LCLS-II-HE. The BCC Cryomodule is designed to contain one 1.3 GHz cavity and one solenoid magnet as part of a 100MeV low emittance injector. The design considerations for the Cryomodule are similar to the LCLS-II cryomodule with additional requirements to account for additional vacuum loading at the end of this vessel due to the termination of the insulating vacuum. To accomplish this design, the cryomodule is being developed using the experience gained during the development of the LCLS-II cryomodule. The design, analysis, and status of the Cryomodule will be discussed.

43 PARTICLE ACCELERATORS↗

Status of U.S. DOE Deliverables 0 July 2023

An annual status of the US TRISO fuel qualification program is provided, with a focus on activities linked to the Generation IV International Forum (GIF) Very High Temperature Reactor (VHTR) Fuel and Fuel Cycle (FFC) Project Management Board (PMB).

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Warm Compressor system Overview and status of the PIP-II cryogenic system

The Proton Improvement Plan-II (PIP-II) is a major upgrade to the Fermilab accelerator complex, featuring a new 800-MeV Superconducting Radio-Frequency (SRF) linear accelerator (Linac) powering the accelerator complex to provide the world's most intense high-energy neutrino beam. The PIP-II Linac consists of 23 SRF cryomodules operating at 2 K, 5 K, and 40 K temperature levels supplied by a single helium cryoplant providing 2.5 kW of cooling capacity at 2.0 K. The PIP-II cryogenic system consists of two major systems: a helium cryogenic plant and a cryogenic distribution system. The cryogenic plant includes a refrigerator cold box, a warm compressor system, and helium storage, recovery, and purification systems. The cryogenic distribution system includes a distribution box, intermediate transfer line, and a tunnel transfer line consisting of modular bayonet cans which supply and return cryogens to the cryomodules. A turnaround can is located at the end of the Linac to turnaround cryogenic flows. This paper describes the layout, design, and current status of the PIP-II cryogenic system.

43 PARTICLE ACCELERATORS↗

Distribution, Ecology, Life History, and Conservation Status of the Berry Cave Salamander (Gyrinophilus gulolineatus)

The Berry Cave Salamander (Gyrinophilus gulolineatus) is a neotenic, stygobitic salamander endemic to eight cave systems and an isolated surface record in the Appalachian Valley and Ridge of eastern Tennessee. We conducted surveys for G. gulolineatus from 2017–2019 to assess the status of the species, locate new populations, and address knowledge gaps related to life history and population ecology required for conservation assessment. We confirmed G. gulolineatus presence at four historical sites, but we did not observe the species at any additional caves. At the three known sites with greatest abundance, visual counts per survey ranged 0–19 salamanders in 2017–2019. There was no apparent trend in abundance at Berry Cave. Visual counts declined 65% since the mid-2000s at Meads Quarry Cave and 80% since the early 1980s at Mudflats Cave. Mark-recapture studies in 160-m of cave stream at Berry Cave in 2017–2018 and 900-m of cave stream at Meads Quarry Cave in 2008 yielded population size estimates that ranged from 34–78 and 15–65 individuals, respectively. We identified 13 existing or potential threats to populations. Habitat degradation and groundwater contamination (associated with urbanization of the Knoxville metropolitan area and past mining operations) represent the most evident threats to long-term viability. Based on our conservation assessments, we recommend a rank of Endangered under IUCN Red List criteria and Critically Imperiled–Imperiled (G1G2) under NatureServe criteria. In opposition to the recent U.S. Fish & Wildlife Service decision, we advocate that, at minimum, G. gulolineatus remain a Candidate Species. Given the identified threats and these ranks, we offer several recommendations for research, conservation, and management of this rare salamander.

59 BASIC BIOLOGICAL SCIENCES↗

Building Alternative Indices of Socioeconomic Status for Population Modeling in Data-Sparse Contexts (Short Paper)

Population modeling requires clear definitions of socioeconomic status (SES) to ensure overall estimate accuracy and locate potentially underserved subpopulations. This presents a challenge as SES can be measured in myriad ways and for divergent purposes, and the data required to calculate these metrics may be lacking, particularly in low and middle income countries (LMICs). To support more refined SES measurement, we explore improvements upon the Demographic and Health Survey’s (DHS) Wealth Index (DHS-WI) using alternative characterizations of SES based on multiple correspondence analysis (MCA) and hierarchical clustering. We produce the MCA-derived metrics first on a full suite of household economic, demographic, and dwelling variables, then on a reduced set of occupant-only SES characteristics. We explore the utility of these metrics relative to DHS-WI based on their ability to 1) differentiate DHS household types and 2) identify mixtures of SES levels within DHS samples and mapped at high spatial resolution. We find that our full suite MCA yields more clearly defined SES segments and that our reduced MCA delineates occupant SES most clearly, suggesting potential pathways to improve upon the DHS-WI in future population modeling efforts for LMICs.

Cunningham, Angela↗

Fuel Conversion Efforts at the High Flux Isotope Reactor – a 2023 Status Update

The High Flux Isotope Reactor (HFIR) provides one of the world’s highest steady-state neutron fluxes in the world for neutron scattering experiments focused on impactful scientific discovery, as well as materials irradiation studies and production of medical, industrial, and research isotopes. Efforts are ongoing to convert HFIR from high-enriched uranium (HEU) to low-enriched uranium (LEU) fuel while maintaining or enhancing current performance and safety margin, thus sustaining HFIR’s mission portfolio and reactor-based neutron science leadership. This paper presents a status update on the HFIR fuel conversion efforts.

Sizemore, Carol↗

Status of DUNE Offline Computing

We summarize the status of Deep Underground Neutrino Experiment (DUNE) Offline Software and Computing program. We describe plans for the computing infrastructure needed to acquire, catalog, reconstruct, simulate and analyze the data from the DUNE experiment and its prototypes in pursuit of the experiment's physics goals of precision measurements of neutrino oscillation parameters, detection of astrophysical neutrinos, measurement of neutrino interaction properties and searches for physics beyond the Standard Model. In contrast to traditional HEP computational problems, DUNE's Liquid Argon Time Projection Chamber data consist of simple but very large (many GB) data objects which share many characteristics with astrophysical images. We have successfully reconstructed and simulated data from 4% prototype detector runs at CERN. The data volume from the full DUNE detector, when it starts commissioning late in this decade will present memory management challenges in conventional processing but significant opportunities to use advances in machine learning and pattern recognition as a frontier user of High Performance Computing facilities capable of massively parallel processing. Our goal is to develop infrastructure resources that are flexible and accessible enough to support creative software solutions as HEP computing evolves.

43 PARTICLE ACCELERATORS↗

Current status of the DOE/NNSA nuclear criticality safety program hands-on criticality safety training courses

In 2011 the US Department of Energy/National Nuclear Security Administration (DOE/NNSA) Nuclear Criticality Safety Program (NCSP) developed and piloted a 2-week nuclear criticality safety (NCS) practitioner course to support training and qualification of new NCS staff. The course was developed in accordance with the American National Standard Institute/American Nuclear Society (ANSI/ANS) standard for NCS training and qualifications (ANSI/ANS-8.26-2007). In 2013, an NCS manager's course was developed for process supervisors, managers, regulators, and other professionals with NCS-related responsibilities. These courses consist of classroom education, facility training, and hands-on subcritical and critical experiments training. Each course is currently offered twice per year. The 2-week practitioner course offers a week of classroom training, with practical workshops and exercises focused on teaching students how to perform an NCS evaluation. The second week of training involves hands-on critical and subcritical experiments and measurements. The first week is offered in Las Vegas, Nevada, at the DOE Nevada Field Office or the National Atomic Testing Museum. Depending on the student's clearance level, the second week is offered at Sandia National Laboratory (SNL) (uncleared and L-cleared students) or at the National Criticality Experiments Research Center (NCERC) (Q-cleared students). The 1-week manager's course is offered at SNL or NCERC, depending on clearance or interest, and includes classroom and hands-on critical and subcritical experiments and measurements. This paper provides an overview and status report for the DOE/NNSA NCSP training courses in NCS and provides information about future course offerings. (author)

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

Overview and status of domestic and international standards for nuclear criticality safety

For many years, the domestic and international consensus standards for nuclear criticality safety (NCS) have provided guidance for those performing hands-on operations involving fissionable materials. These consensus standards have been crucial to reducing the number of criticality accidents in process facilities. The last known criticality accident inside the United States was in 1978 (39 years ago at this writing) at the Idaho Chemical Processing Plant, and outside the United States, an accident occurred at Tokai-Mura, Japan, in 1999 (18 years ago at this writing). The domestic consensus standards for NCS include the American Nuclear Society (ANS) standards. The ANS Standards Board, the NCS Consensus Committee, and the ANS-8 Subcommittee oversee the development and maintenance of these standards. There are currently eighteen standards in revision (seven) or maintenance (eleven) cycles, and one standard is currently in development. The international consensus standards for NCS calculations, procedures, and practices are maintained and developed within the International Organization for Standardization, Technical Committee 85 on Nuclear Energy, Subcommittee 5 on Nuclear Fuel Technology, and Working Group 8, Nuclear Criticality Safety. Seven standards are currently available, one standard is in revision, and four standards are at various stages of development. This paper provides the NCS community with an overview and status report of domestic and international NCS consensus standards to stimulate interest and to support their continued development. (author)

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

The Status of LILW Complex Disposal Facility Construction in Korea-18511

This paper provides the status and experiences of Low and Intermediate-level radioactive Waste (LILW) disposal facility in Korea. The LILW disposal facility is being constructed in Gyeongju-si, Korea. It can dispose of 800,000 drums (hereafter, 'drums' means '200 liter drum equivalents' unless specified otherwise) of radioactive waste in a site of 2,060,000 m{sup 2}. The first stage of the LILW facility construction was completed in June 2014, and approved for use by Nuclear Safety and Security Commission (NSSC) in December 2014. The first stage of the LILW facility, which is a type of underground silo with disposal capacity of 35,200 m{sup 3} (100,000 drums), consists of a construction tunnel, an operation tunnel, an access shaft, and six silos, etc. Silo for final disposal is located 80∼130 m below sea level, 25 m in diameter and 50 m in height. The capacity of each silo is approximately 16,700 drums. The second stage of the LILW facility is under construction and will be completed by December 2020. The second stage of the LILW facility, which is a type of near-surface disposal with disposal capacity of 32,875 m{sup 3} (125,000 drums), consists of an underground gallery, three movable cranes and twenty vaults, etc. Vault for final disposal is located about 100 m above sea level, 20 m in width, 20 m length and 10.9 m in height. The capacity of each vault is approximately 6,250 drums. A second receipt and storage facility is to be completed by June 2021. This facility is under designing to prepare for further increasing radioactive waste receipt quantities. It has storage capacity of 10,000 drums (existing receipt and storage facility have storage capacity of 7,000 drums)and will be divided into several sections for pre-disposal work, storage, a passage to link the existing facility to the second receipt and storage facility and truck bay, etc. These components of the LILW disposal facilities are together called LILW complex disposal facility. It is the world's first LILW disposal facility with two different types of disposal facilities in one site. For efficient operation, these disposal facilities share a receipt and storage building, a waste water treatment system, a measurement and monitoring system, etc. Once the construction of the first two stages is completed, LILW disposal facilities will be incrementally expanded, and as the whole LILW disposal facilities are completed, all LILW in Korea will be disposed of these disposal facilities efficiently according to its radioactivity level and managed safely by KORAD. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Final Status Surveys of Subsurface Contaminated Areas - 19473

This paper addresses how the U.S. Army Corps of Engineers (USACE) has performed final status surveys (FSS) at sites with subsurface contaminated areas. The Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM) guidance addresses only surficial contamination. This paper will explore alternative methodologies used by the USACE to demonstrate compliance with the release criterion when contamination extends below the surface. Special challenges posed by small areas of elevated activity at depth will also be addressed. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

History and Status of DoE's Standardized Canister - 19657

The U.S. Department of Energy (DOE) is responsible for managing spent nuclear fuel (SNF) currently in its possession, as well as SNF that will come into its possession in the future. DOE will rely upon the standardized canister to confine radionuclides and precluding the moderator in order to ensure safe, long-term management and disposition of SNF in its possession. This strategy helps minimize characterization costs (i.e., funds and exposure) and other technical challenges associated with the traditional approach of relying on fuel-specific properties to demonstrate compliance with the regulator. The use of the standardized canister offers the following benefits: - The standardized canister design is complete. It has been tested under a variety of drop and accident scenarios and was subsequently licensed under 10 CFR 72 as a storage system as part of the Foster Wheeler Environmental Corporation (FWENC) Facility. It is also part of the license submittal for Yucca Mountain. - There is high confidence that the standardized canister design can be stored within commercially-available storage casks and licensed as part of a transportation-system package. - A robust standardized canister simplifies accident analyses and does not rely on characterization of the contained waste. This simplifies safety analysis, provides a greater level of confidence with stakeholders and reduces cost and risk. - A common design for the associated packaging, closure, and loadout facilities results in significant savings. - The DOE standardized canister would simplify design efforts, procurement, and fabrication. - Standardizing handling activities and associated training, procedures, equipment, and tooling leads to enhanced safety and surety of operations. The standardized canister is the preferred package for these materials. It withstood scrutiny by the Yucca Mountain Repository License Application, the Nuclear Regulatory Commission's (NRC) Advisory Committee on Nuclear Waste, the Nuclear Waste Technical Review Board, an American Society of Mechanical Engineers peer review, and the FWENC storage license application. This evaluation summarizes and documents the status of the design and rationale for the DOE standardized canister, and outlines remaining needs before deployment. In addition, it discusses the factors that have the potential to influence storage, transportation, and disposal of DOE SNF. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Panel Session 109: US HLW Repository: Status and Next Steps

This panel focused on the technical, institutional and broader political issues associated with advancing a US HLW Repository program including programmatic, regulatory, legislative and funding challenges. Panelist with presentations: WM 2020 HLW Repository Status and Next Steps (Leo Blundo)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Panel Session 94: US DOE Procurement Opportunities and End-State Contracting Model Status

This panel focused on DoE's procurement implementation strategy and planned activities for its first-tier contractors (Tier 1 procurements). This panel also focused on the implementation status of DoE's End State Contracting Model, which uses a single-award ID/IQ approach to give DOE flexibility to better define discrete scopes of work for site closure or end states. The panelists provided their prospective on progress toward the implementation of this new approach, lessons learned and the path forward for upcoming opportunities utilizing this contracting model. Panelists with presentations: EFCOG (Billy Morrison); DOE Procurement Opportunities - 4 Ways for Small Business Participation (Anne Marie Bird); US DOE Procurement and Contracting Opportunities (Aaron Deckard)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Update on the Status of Deep Borehole Disposal of High-Level Radioactive Waste in Germany - 20285

The phase-out of nuclear energy in Germany will take place in 2022. A site for final disposal of high level radioactive waste (HLRW) has not yet been found, but a site selection process was restarted by Act on the Search for and Selection of a Site for a Disposal Facility for High-Level Radioactive Waste (Site Selection Act - StandAG 2017). This act was based on a recommendation by a commission which also advised to follow up the development of deep borehole disposal (DBD) as an alternative option for final disposal of HLRW. This paper summarizes briefly the status of DBD in Germany and if this option should be pursued in Germany. Although there are some merits of DBD, it can only be a real option if research and development is supported. The technical equipment for boreholes of the required size will only be developed if there is funding and a feasibility test. Furthermore, any concept of DBD and technology must be detailed further, and some requirements of the act must be reconsidered. The paper concludes that despite the possible merits of DBD, the political and financial support for R and D will only be provided for the time being if DBD is pushed by interested parties. Alternatively, if the site selection procedure is not progressing well, then the alternative option of DBD may find greater interest in the future. However, its availability will be severely limited due to the missing development of detailed concepts and its demonstration of feasibility. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Alloy 709 Procurement and ASTM Standardization Status

A presentation that provides the status of procuring commercial-heats of the plate-product form of Alloy 709 and incorporating the plate-product form of Alloy 709 into the applicable ASTM standards.

36 MATERIALS SCIENCE↗