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DOE OSTI2011

Disposal Systems Evaluation Framework (DSEF) Version 1.0 - Progress Report

The Disposal Systems Evaluation Framework (DSEF) is being developed at Lawrence Livermore National Laboratory to formalize the development and documentation of repository conceptual design options for each waste form and environment combination. This report summarizes current status and plans for the remainder of FY11 and for FY12. This progress report defines the architecture and interface parameters of the DSEF Excel workbook, which contains worksheets that link to each other to provide input and document output from external codes such that concise comparisons between fuel cycles, disposal environments, repository designs and engineered barrier system materials can be performed. Collaborations between other Used Fuel Disposition Campaign work packages and US Department of Energy / Nuclear Energy campaigns are clearly identified. File naming and configuration management is recommended to allow automated abstraction of data from multiple DSEF runs.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

DOE OSTI2018

GALE 3.1 Verification Report

This report is documentation of the verification activities that have been performed on GALE-3.1 to ensure that the codes meet the requirements and specifications set forth by NRC and that the code meets its intended purpose. Additional benchmark tests for GALE-3.1 are documented in Appendix A of NUREG-0016, Revision 2 for GALE-BWR 3.1 and Appendix A of NUREG-0017, Revision 2 for GALE-PWR 3.1. These activities are done in accordance with the GALE Software Quality Assurance Plan (PNNL-24249) and the GALE Configuration Management & Maintenance Plan (PNNL-24250). These two plans meet the requirements set for by both PNNL software quality assurance requirements and the NRC’s Software Quality Assurance Program and Guidelines (NUREG/BR-0167). The verification activities are documented to conform to Level 2 requirements of NUREG/BR-0167. Verifications were performed for both GALE-3.1 BWR and GALE-3.1 PWR Codes. The GALE 3.1 BWR and PWR codes are computerized mathematical models for calculating the releases of radioactive material in gaseous and liquid effluents. These computer codes are tools which can be used to determine conformance with the requirements of Appendix I to Title 10, Part 50 of the Code of Federal Regulations (10 CFR 50).

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

DOE OSTI2017

Status of the SAS4A/SASSYS-1 Safety Analysis Code

SAS4A/SASSYS-1 is a simulation tool used to perform deterministic analysis of anticipated events as well as design basis and beyond design basis accidents for advanced reactors. This report summarizes the current status of SAS4A/SASSYS-1, including the implementation of software quality assurance procedures for configuration management, new licenses, current users, and a gap assessment of the test suite. The existing copyright has been extended for an additional five years, which was essential so that Argonne can continue developing, distributing, and supporting the software for both domestic use and international collaborations. SAS4A/SASSYS-1 Version 5.2 was completed in March 2017 and released to users in May. The importance of SAS4A/SASSYS-1 maintenance reflects its relevance to a number of U.S. Department of Energy programs as well as domestic and international collaborations. External collaborations have also produced improvements in the SAS4A/SASSYS-1 code, and these are noted in this report. SAS4A/SASSYS-1 has a growing user base that continues to strengthen the promotion of advanced non-LWR reactor concepts. Additional users will help solidify DOE’s leadership role in fast reactor safety both domestically and in international collaborations.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

DOE OSTI2019

GALE 3.2 Verification Report

This report is documentation of the verification activities that have been performed on GALE-3.2 to ensure that the codes meet the requirements and specifications set forth by NRC and that the code meets its intended purpose. These activities are done in accordance with the GALE Software Quality Assurance Plan (PNNL-24249) and the GALE Configuration Management & Maintenance Plan (PNNL-24250). These two plans meet the requirements set for by both PNNL software quality assurance requirements and the NRC’s Software Quality Assurance Program and Guidelines (NUREG/BR-0167). The verification activities are documented to conform to Level 2 requirements of NUREG/BR-0167. Verifications were performed for both GALE-3.2 BWR and GALE-3.2 PWR Codes. The GALE 3.2 BWR and PWR codes are computerized mathematical models for calculating the releases of radioactive material in gaseous and liquid effluents. These computer codes are tools which can be used to determine conformance with the requirements of Appendix I to Title 10, Part 50 of the Code of Federal Regulations (10 CFR 50).

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

DOE OSTI2019

Advanced Synchrophasor Protocol (ASP) Development and Demonstration Project

The Advanced Synchrophasor Protocol Project had two main objectives: To develop, document, and demonstrate a new standard communications protocol (that became named the Streaming Telemetry Transport Protocol, or STTP) to overcome the issues being encountered in large-scale synchrophasor data system deployments using existing protocols – specifically with issues of scalability, data loss, bandwidth utilization, data access control, transport security options, and cost of configuration management, and to work with standards bodies to put STTP on a track for consideration as a standard protocol.

42 ENGINEERING↗

DOE OSTI2019

October 2019 SAPHIRE 8 Software Quality Assurance Oversight Status Report

The software quality assurance oversight consists of updating and maintaining revision control of the System Analysis Program for Hands-on Integrated Reliability Evaluations (SAPHIRE) Version 8 quality assurance program documentation and of monitoring revision control of the SAPHIRE Version 8 source code. This report summarizes the oversight efforts through description of the revision control system (RCS) setup, operation and contents. Documents maintained under revision control include the Acceptance Test Plan (ATP), Configuration Management Plan, Quality Assurance Plan, Software Project Plan, Requirements Traceability Matrix (RTM), System Test Plan, Significance Determination Process (SDP) Interface Training Manual, and the SAPHIRE 8 “New Features and Capabilities Overview.” These documents are referred to and can be transmitted upon request of the Nuclear Regulatory Commission (NRC) Contracting Officer’s Representative (COR).

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

DOE OSTI2020

Model Package Report: Central Plateau Vadose Zone Models

This model package report describes concisely the modeling objectives, conceptualization, implementation, uncertainty and sensitivity, configuration control, limitations, data needs, and recommendations for improvement of the Central Plateau Vadose Zone Models. This collection of models is developed to meet the vadose zone simulation needs of the Hanford Site Composite Analysis (CA), the Hanford Site Cumulative Impact Evaluation (CIE), and are expected to find other applications in Hanford Site remedial cleanup decision-making processes. This model package report describes and documents the development of the models themselves to fulfill technical approaches defined for the CA and the CIE. This report does not document any specific calculation using these models: instead, applications of individual vadose models to perform specific calculations will be documented in environmental calculation files, including inputs and results, as appropriate. Configuration management for the Central Plateau Vadose Zone Models is managed through assignment of unique sequential numerical version numbers and archival of the models in the Environmental Modeling Management Archive.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

DOE OSTI2024

SCALE Procedure for Verified, Archived, Library of Inputs and Data (VALID)

This procedure provides a framework for preparing, reviewing, and storing model inputs and derived data so that individuals with authorized access to the Verified, Archived, Library of Inputs and Data (VALID) repository can use the inputs and data with confidence in their analyses. This procedure uses documented checks and reviews to ensure that the inputs and data were correctly generated using appropriate references. Configuration management is implemented to prevent inadvertent modification of the inputs and data or inclusion of models that have not been reviewed. This procedure also provides guidance to be followed if errors are identified or if input or data revisions are needed.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

DOE OSTI2025

Software Quality Assurance for the MOOSE-Based Open-Source Multiphysics Code Cardinal - An Expanded CI Testing Suite

Cardinal is a wrapping of the GPU-oriented spectral element Computational Fluid Dynamics (CFD) code NekRS and the Monte Carlo particle transport code OpenMC within the Multiphysics Object-Oriented Simulation Environment (MOOSE). Cardinal provides high-resolution thermal-hydraulics and/or radiation transport feedback to MOOSE multiphysics simulations. Multiphysics feedback is implemented in a geometry-agnostic manner which eliminates the need for rigid one-to-one mappings. A generic data transfer implementation also allows NekRS and OpenMC to couple to any MOOSE application, enabling a broad set of multiphysics capabilities. Cardinal simulations can also leverage combinations of MPI, OpenMP, and GPU resources. Cardinal continuous development and improvement efforts have led to the software being considered as a high-fidelity design and licensing tool for key areas of nuclear reactor relevant physics, including neutron transport, fluid flow, heat transfer, and mechanical processes. The fast development and expansion of the software from a pure R&D framework towards its application in the nuclear industry and regulation require a focus on developing, enhancing and, maintaining Cardinal’s software quality through strict adherence to a Software Quality Assurance (SQA) framework and SQA program. To facilitate compliance with SQA standards, the Cardinal SQA Program has been initiated during Fiscal Year 2023 (FY23). During the development of the Cardinal SQA Program, multiple gaps have been identified. These gaps are primarily related to model verification and code pedigree as they relate to the use of Cardinal as a safety analysis tool. These gaps have been captured in a report published in 2023. A second report highlighted the progress made during Fiscal Year 2024 (FY24) and described Argonne’s effort to document and integrate software verification within Cardinal’s software development process. This report documents a snapshot of the verification test cases currently available for Cardinal and NekRS in their assimilation into a Continuous Integration (CI) platform. Following the CI practice permits the integrating of source code changes frequently and ensuring that the integrated codebase clears the verification testing for the software. It should be noted that the SQA program itself, including the program plans, procedures, configuration management, and testing strategies, need to be developed in a future step of this task.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

DOE OSTI2025

Toroid Signal Processing Container with Redis Integration

This report presents the research, design, and implementation of a Toroid Signal Processing Container with Redis Integration, conducted during my internship assignment. The project focused on developing a modular signal processing sys- tem capable of performing baseline correction, droop compensation, and real- time data communication for beam diagnostic signals. Using Redis as a message broker and configuration manager, the system ensures modularity, scalability, and efficient inter-process communication. Signal correction algorithms, such as Asymmetric Least Squares (ALS) baseline smoothing and a numerical droop correction approach, were implemented and tested using Linac beam data. The results confirm that this system improves signal fidelity and supports real-time analysis requirements, offering valuable contributions to the field of beam instrumentation and data acquisition systems.

Bowers, Elliot [Cabrillo Coll.]↗

DOE OSTI2013

Lessons Learned from the 200 West Pump and Treatment Facility Construction Project at the US DOE Hanford Site - A Leadership for Energy and Environmental Design (LEED) Gold-Certified Facility

CH2M Hill Plateau Remediation Company (CHPRC) designed, constructed, commissioned, and began operation of the largest groundwater pump and treatment facility in the U.S. Department of Energy’s (DOE) nationwide complex. This one-of-a-kind groundwater pump and treatment facility, located at the Hanford Nuclear Reservation Site (Hanford Site) in Washington State, was built to an accelerated schedule with American Recovery and Reinvestment Act (ARRA) funds. There were many contractual, technical, configuration management, quality, safety, and Leadership in Energy and Environmental Design (LEED) challenges associated with the design, procurement, construction, and commissioning of this $95 million, 52,000 ft groundwater pump and treatment facility to meet DOE’s mission objective of treating contaminated groundwater at the Hanford Site with a new facility by June 28, 2012. The project team’s successful integration of the project’s core values and green energy technology throughout design, procurement, construction, and start-up of this complex, first-of-its-kind Bio Process facility resulted in successful achievement of DOE’s mission objective, as well as attainment of LEED GOLD certification, which makes this Bio Process facility the first non-administrative building in the DOE Office of Environmental Management complex to earn such an award.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

DOE OSTI2012

Insights Gained for Updating an Analog I&C System to a Digital System

Licensees at both Nuclear Power Plants (NPPs) and Non-Power Reactors (NPRs) are increasing their use of state-of-the-art digital technology in instrumentation and control (I&C) systems because digital systems offer improved reactor control, information processing, and information storage over analog. Digital I&C systems can range from experimental systems for reactor control research (at NPRs), to measurement and display systems, to complete reactor console replacements. Because of the increasing difficulty in finding spare parts for their original analog I&C systems, many licensees have begun or have plans to upgrade, refurbish, or replace their old analog I&C systems with digital systems. The perception is that upgrading to a digital I&C system will solve all of a facility s obsolescence problems. However, licensees need to be aware of several issues associated with upgrading to a digital system including obsolescence of the digital system (hardware and software) because of the short product life cycle and the associated cost to acquire, store, and maintain a long-term supply of spare parts. Configuration management and cyber security are also vitally important for any upgrade. Further, it must be recognized that the introduction of software and microprocessors could create new failure mechanisms, such as software errors and increased susceptibility to electromagnetic interference. In fact, experience has shown that these failure mechanisms may cause the reactor to malfunction in a way not previously considered. Thus, a conversion from analog to digital I&C systems solves some problems while potentially introducing others. Recognition of the additional risks coupled with good design, engineering, review, and testing can identify and minimize these risks.

Adams, A.↗

DOE OSTI2016

Advanced Nuclear Technology. Using Technology for Small Modular Reactor Staff Optimization, Improved Effectiveness, and Cost Containment, 3002007071

Through this grant, the U.S. Department of Energy (DOE) will review several functional areas within a nuclear power plant, including fire protection, operations and operations support, refueling, training, procurement, maintenance, site engineering, and others. Several functional areas need to be examined since there appears to be no single staffing area or approach that alone has the potential for significant staff optimization at new nuclear power plants. Several of the functional areas will require a review of technology options such as automation, remote monitoring, fleet wide monitoring, new and specialized instrumentation, human factors engineering, risk informed analysis and PRAs, component and system condition monitoring and reporting, just in time training, electronic and automated procedures, electronic tools for configuration management and license and design basis information, etc., that may be applied to support optimization. Additionally, the project will require a review key regulatory issues that affect staffing and could be optimized with additional technology input. Opportunities to further optimize staffing levels and staffing functions by selection of design attributes of physical systems and structures need also be identified. A goal of this project is to develop a prioritized assessment of the functional areas, and R&D actions needed for those functional areas, to provide the best optimization

32 ENERGY CONSERVATION, CONSUMPTION, AND UTILIZATI↗

DOE OSTI2012

The CMS online cluster: Setup, operation and maintenance of an evolving cluster

The CMS online cluster consists of more than 2700 computers running about 15000 application instances. These applications implement the necessary services to run the data acquisition of the CMS experiment. In this paper the IT solutions employed on the cluster are reviewed. Details are given on the adopted solutions which include the following topics: implementation of reduction and load balanced network and core IT services; deployment and configuration management infrastructure and its customization; a new monitoring infrastructure. Special emphasis will be put on the scalable approach allowing to increase the size of the cluster with no administration overhead. Finally, the lessons learnt from the two years of running will be presented.

Coarasa, J. A.↗

DOE OSTI2018

Flexible and Scalable Data-Acquisition Using the artdaq Toolkit

The Real-Time Systems Engineering Department of the Scientific Computing Division at Fermilab is developing a flexible, scalable, and powerful data-acquisition (DAQ) toolkit which serves the needs of experiments from bench-top hardware tests to large high-energy physics experiments. The toolkit provides data transport and event building capabilities with the option for experimenters to inject art analysis code at key points in the DAQ for filtering or monitoring. The toolkit also provides configuration management, run control, and low-level hardware communication utilities. Firmware blocks for several commercial data acquisition boards are provided, allowing experimenters to approach the DAQ from a high level. A fully-functional DAQ "solution" of the toolkit is provided in otsdaq, sacrificing some flexibility in favor of being ready-to-use. artdaq is being used for several current and upcoming experiments, and will continue to be refined and expanded for use in the next generation of neutrino and muon experiments.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

DOE OSTI2013

Lessons Learned from the 200 West Pump and Treatment Facility Construction Project at the US DOE Hanford Site - A Leadership for Energy and Environmental Design (LEED) Gold-Certified Facility - 13113

CH2M Hill Plateau Remediation Company (CHPRC) designed, constructed, commissioned, and began operation of the largest groundwater pump and treatment facility in the U.S. Department of Energy's (DOE) nationwide complex. This one-of-a-kind groundwater pump and treatment facility, located at the Hanford Nuclear Reservation Site (Hanford Site) in Washington State, was built to an accelerated schedule with American Recovery and Reinvestment Act (ARRA) funds. There were many contractual, technical, configuration management, quality, safety, and Leadership in Energy and Environmental Design (LEED) challenges associated with the design, procurement, construction, and commissioning of this $95 million, 52,000 ft groundwater pump and treatment facility to meet DOE's mission objective of treating contaminated groundwater at the Hanford Site with a new facility by June 28, 2012. The project team's successful integration of the project's core values and green energy technology throughout design, procurement, construction, and start-up of this complex, first-of-its-kind Bio Process facility resulted in successful achievement of DOE's mission objective, as well as attainment of LEED GOLD certification (Figure 1), which makes this Bio Process facility the first non-administrative building in the DOE Office of Environmental Management complex to earn such an award. (authors)

54 ENVIRONMENTAL SCIENCES↗

DOE OSTI2023

Software Bill of Materials in the Nuclear Industry

Nuclear power plants (NPP) have thousands of digital assets throughout their facility. Typically, NPPs have asset and configuration management programs that capture the make, model, and version of a component. This information, however, usually only includes first- or second-tier components and does not capture the complete enumeration of software components and their dependencies within operational technology (OT) equipment. As seen with recent cyberattacks, this level of detail is insufficient for identifying if and where an exploitable vulnerability exists within a facility. A software bill of materials (SBOM) provides this detailed enumeration. Further, integrating SBOMs with vulnerability data sources and vulnerability attestation reports can provide improved awareness leading to better cyber risk management and incident response. Preferably, SBOMs are provided by the supplier; however, when an NPP already owns a device, it is less likely they will have a supplier provided-SBOM. Fortunately, SBOMs can be generated on installed digital assets. This paper provides an introduction to the U.S. Department of Energy Office of Nuclear Energy paper titled “Towards Software Bill of Materials in the Nuclear Industry,” which describes the SBOM ecosystem and provides a suggested approach to methodically and seamlessly integrate an SBOM program in an NPP.

98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL P↗

DOE OSTI2019

Engineering Challenges for the In Situ Disposal (ISD) of the 20 MWe Nuclear Power Demonstration (NPD) Reactor - 19407

The Nuclear Power Demonstration (NPD) reactor is the first CANDU{sup R} type power reactor to be decommissioned. This first of a kind project is to decommission the station using an In-Situ Disposal (ISD) strategy, and presents some engineering challenges to implement. Based on current technology and successful application of industry lessons learned, these challenges are being met. This paper presents a summary of those challenges, to recover from a long period of Storage With Surveillance, solve configuration management, assess the existing structure, determine the performance of the structure following seismic events during the disposal period, adapt the facility design to ISD and select a grout in-fill, and describe the regulatory and public interaction, to demonstrate the integrity of what will be a future disposal site. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗