ML22235A651
| ML22235A651 | |
| Person / Time | |
|---|---|
| Issue date: | 09/01/2022 |
| From: | Office of Nuclear Regulatory Research |
| To: | |
| N. DiFrancesco | |
| References | |
| Download: ML22235A651 (37) | |
Text
oo~***P Supporting Decision-Making with Modeling and Simulation Performing Comprehensive Technical Analysis
- N uclearResearch Advancing Probabilistic Risk Assessment
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- NuclearResearch We invite you to explore the U.S. Nuclear Regulatory Commission's Research Prospectus for Fiscal Years 2022 through 2024.
THESE ARE EXCITING TIMES FOR RESEARCH. Our research results support the safety decisions our agency is making today. We are also preparing the agency for the future through our research of new and emerging technologies and technical advances. Such technologies and advances include accident tolerant fuels, advanced reactor designs, artificial intelligence, human-machine interface, advanced manufacturing techniques, to name but a few. To conduct our research activities, the Office of Nuclear Regulatory Research maintains an expert staff and collaborates with many domestic and international partners. We appreciate your interest and welcome your feedback on our research program.
No research without action, no action without research.
-Dr. Kurt Lewin, Founder of Modern Social Psychology
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Director gte;/4alfie Coffilf Deputy Director
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Offi<::e of Nuclear Regulatory Research
$8SM RESEARCH BUDGET Current FY 2022 203 FULL-TIME EQUIVALENT STAFF Research by the Numbers FY 2021 MAJOR RESEARCH PROGRAMS RECENT NUREGS NEW AND REVISED REGULATORY GUIDES INTERNATIONAL AGREEMENTS COMPUTER CODE USERS UNIVERSITY-LED, MISSION-RELATED GRANTS
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Al ASP ATF FAST FFR FY HEAF HRA IDHEAS LWR M
MACCS ML NRC NUREG OECD/NEA OpE PARCS PRA RAMP RE I RS RG SAP HIRE SCALE SPAR TRACE UNLP Abbreviated Terms artificial intelligence accident sequence precursor accident-tolerant fuel Fuel Analysis under Steady-state and Transients future focused research fiscal year high energy arcing fault human reliability analysis Integrated Human Event Analysis System light-water reactor mi 11 ion MELCOR Accident Sequence Code System machine learning U.S. Nuclear Regulatory Commission NRC technical report designation Organisation for Economic Co-Operation and Development, Nuclear Energy Agency operating experience Purdue Advanced Reactor Core Simulator probabilistic risk assessment Radiation Protection Computer Code Analysis and Maintenance Program Radiation Exposure Information and Reporting System regulatory guide Systems Analysis Programs for Hands-on Integrated Reliability Evaluations Standardized Computer Analyses Licensing Evaluation standardized plant analysis risk TRAC/RELAP Advanced Computational Engine University Nuclear Leadership Program 4
Prospectus Contents FUTURE FOCUSED RESEARCH SYSTEMS ANALYSIS RESEARCH
- N uclearResearch ENGINEERING RESEARCH 5
ADVANCED REACTORS RESEARCH RISK ANALYSIS RESEARCH
/4oking Ahead FFR&UNLP PROGRAMS
- NuclearResearch The FFR Program provides a vehicle to position the NRC to be ready for future state-of-the-art technologies and their potential regulatory impacts. It opens new areas of foundational knowledge on key topics.
The UNLP inspires researchers at U.S. institutions to develop innovative ideas that benefit the NRC mission and the broader nuclear community.
6 Increasing Interest Positive Feedback
UNLP Highlights
> In the first 3 years of the FFR program, $1.8M has been awarded for external support services. Sustained interest in the program may mean an increased allocation in the budgeted amount for FY 2023.
> FFR projects are generally completed in 3 years or less.
> Example projects that are at or nearing completion include Dynamic Probabilistic Analysis, Systems-Theoretic Accident Model and Processes-Based Methods for Digital Nuclear Safety System Evaluation, Digital Twins-Regulatory Viability, and Automation Tool Mapping.
> In FY 2020, the first year of the program, 54 institutions submitted over 160 proposals. In a highly competitive review process, the NRC selected 15 proposals to receive research and development grants totaling $7.3M.
> In FY 2021, nearly 100 proposals were submitted, and the NRC selected 11 proposals to receive research and development grants totaling $4.5M.
7
/4oking Ahead ADVANCED REACTORS
- NuclearResearch Research on advanced reactors facilitates the NRC's readiness for non-LWR licensing reviews.
The Near-Term Implementation Action Plan is the vehicle to execute the NRC's vision to safely achieve effective and efficient non-LWR mission readiness. Research efforts support development of computer codes and knowledge, guidance, and industry codes and standards for regulatory reviews.
8
oking Ahead Fy2 2
> Develop two demonstration plant models for system
/
and source term analysis for non-LWRs Complete MACCS radionuclide properties on atmospheric transport and dosimetry
> Issue trial-use RG 1.247
> Complete final RG endorsing American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section Ill, Division 5, including Alloy 617 Fy2 3
> Complete review of MACCS capabilities for reviewing tritium 1/ releases to the environment
> Complete scalable reactor operator licensing review guidance
> Complete computational tool for confirmatory analyses of graphite component integrity
> Complete trial RGs for risk-informed, performance-based seismic design and seismic isolation FY24
> Update two demonstration plant models for system analysis 1/ > Develop risk-informed decision-making guidance for non-LWRs
> Develop scalable human factors engineering and reactor operator licensing guidance
> Develop methodology and evaluation tools for digital twin applications and enabling technologies 9
$6.4M
FOCUS AREAS
> Fuels and Neutronics Analysis
> Thermal Hydraulics Analysis Building the NRC's analytical capability and expertise
> Accident Progression and Source Term Analysis
> Consequence Analysis
> Radiation Protection Research 10
/4.tems Analysis Research T
Sfale FUELS & NEUTRONICS ANALYSIS
- NuclearResearch Fuels and neutronics research provides the technical bases for risk-informed regulatory decision-making.
The FAST code enables confirmatory studies for new fuel designs, including ATF and high burnup fuels. The SCALE code can analyze neutronics-related phenomena (e.g., nuclear data libraries, depletion and activation, criticality and shielding, and sensitivity and uncertainty analysis) and is used to initialize other NRC safety codes.
11 e
ADVANCED Code development to support advanced nuclear technologies, including ATF, high burnup and high-assay low-enriched uranium fuels and non-LWRs, in addition to code enhancements for LWRs.
INTERNATIONAL Participation in various OECD/NEA projects to obtain data and investigate fuel and cladding behavior.
SOFTWARE Development of staff expertise in reactor physics phenomena, including criticality and shielding, and analyses of advanced fuel designs.
/4.tems Analysis Research FY22
> Annual release of computer codes for LWR and
/
non-LWR applications
> Workshops for molten salt and sodium reactors
> Issuance of research information letter on fuel fragmentation, relocation, and dispersal
> Spent fuel storage and transportation for ATF Fy2 3
> Ann~al ~el ease of computer codes for LWR and non-LWR 1/ applications
> Completion of the first phase of the OECD/NEA Framework for Irradiation Experiments (four joint experimental programs)
> In-house familiarity with U.S. Department of Energy computer codes Fy24
> Ann~al ~elease of computer codes for LWR and non-LWR 1/ appl1cat1ons
> Studsvik Cladding Integrity Program experiments
> SCALE bundle experiments studying ATF cladding materials at the QUENCH facility in Germany
> Spent fuel storage and transportation phenomena identification and ranking tables for ATF 12
$6.SM
/4.tems Analysis Research THERMAL HYDRAULICS ANALYSIS
- NuclearResearch Thermal hydraulics research leads to the development of computer codes that can simulate the behavior of nuclear reactors.
The TRACE and PARCS computer codes are used for confirmatory analyses of existing and new reactor designs to support regulatory decision-making.
Like other modern reactor system codes, they depend upon empirical correlations that have been developed from detailed experiments over decades of domestic and international research.
13 D
SOFTWARE The TRACE and PARCS computer codes are maintained, developed, and distributed for performing best estimate thermal hydraulic and neutronics reactor systems analysis.
EXPERIMENTS Participation in international experimental programs enables the NRC to obtain validation data at low cost. These data are then assessed to enhance code predictions.
INDEPENDENT The TRACE and PARCS computer codes support independent technical basis development. They are used for confirmatory analyses to support safety and security regulatory decision-making.
0
/4.tems Analysis Research FY22
> Complete TRACE Version 5, Patch 7
/
> Complete the ARTHUR experimental program
> Complete two plant models to be ready for emergent licensing needs 2 3
> Complete TRACE Version 5, Patch 8 FY 1/,
Complete TRACE assessment cases for the ATLAS-3 experimental program
> Continue to provide regulatory support for the review of research reactors and a radioisotope production facility
> Complete two plant models to be ready for emergent licensing needs FY24
> Complete TRACE Version 5, Patch 9 1/ > Complete the ETHARINUS experimental program
> Continue to provide regulatory support for the review of research reactors and a radioisotope production facility
> Complete two plant models to be ready for emergent licensing needs 14
$6.lM
/4.tems Analysis Research ACCIDENT PROGRESSION &
SOURCE TERM ANALYSIS
- NuclearResearch Research to develop, validate, and maintain state-of-the-art tools for severe accident and source term analysis.
The MELCOR computer code is used to support safety issue resolution and risk-informed decision-making.
MELCOR is a system-level code that simulates the entire spectrum of accidents and phenomena from initiation to core degradation and fission product release from the fuel and transport to the containment and the outside environment.
15 SOFTWARE Code modernization and readiness for advanced nuclear technology applications, including ATF, high burnup and high-assay low-enriched uranium fuels, non-LWRs, and small modular reactors.
INTERNATIONAL Participation in various OECD/NEA projects to obtain data for code verification and validation.
SOFTWARE Using MELCOR to maintain staff expertise in new technologies.
/4.tems Analysis Research FY22
> Ann~al ~elease of MELCOR for LWR and non-LWR
/
applications
> Annual technical meetings on Cooperative Severe Accident Research Program
> Workshops for molten salt and sodium reactors
> Source term analysis for chromium-coated ATF
> Non-LWR fuel cycle demonstration calculations Fy23
> Ann~al ~elease of MELCOR for LWR and non-LWR 1/ applications
> Annual technical meetings on Cooperative Severe Accident Research Program
> Modernization of the core code models
> OECD/NEA experimental programs and data analysis
> Fusion reactor demonstration project Fy24
> Ann~al ~elease of MELCOR for LWR and non-LWR 1/ appl1cat1ons
> Annual technical meetings on Cooperative Severe Accident Research Program
> Modernization of the radionuclide and transport code models
> OECD/NEA experimental programs and data analysis 16
$2.SM
/4.tems Analysis Research Dr-y Dep,osition
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Groundshine CONSEQUENCE ANALYSIS
- NuclearResearch Research to develop and apply accident consequence codes to evaluate offsite consequences from hypothetical severe accidents.
Consequence analysis supports risk-informed decision-making by evaluating the public health effects and economic costs of mitigation actions for severe accidents and assists in emergency planning. The analyses also provide input to cost-benefit studies and support plant-specific evaluations of severe accident mitigation alternatives required for environmental assessments.
17 B
SOFTWARE Develop and apply the MACCS computer code to model the offsite consequences from hypothetical severe accidents at nuclear power plants.
INTERNATIONAL Leverage research from international organizations and other Federal agencies to continually improve the MACCS code.
EMERGENCY Provide insights to support methodology and guidance for determining emergency planning zone sizes for nuclear power plants.
/4.tems Analysis Research FY2 2
> Issue protective action recommendations scoping
/
study report
> Complete MACCS radionuclide properties on atmospheric transport and dosimetry
> Complete initial evaluation of consequences from non-LWR source term demonstration calculations using MACCS Fy2 3
> Continue the evaluation of consequences from non-LWR 1/ source term demonstration calculations using MACCS
> Develop screening analysis to inform the level of detail needed for severe accident mitigation design alternative and severe accident mitigation alternative analyses for new and non-LWR applications
> Complete Level 3 PRA consequence analysis reports for the remaining reactor accident analyses Fy24
> Complete review of MACCS capabilities for reviewing tritium 1/ releases to the environment
> Continue the evaluation of consequences from non-LWR source term demonstration calculations using MACCS
> Address WinMACCS graphical user interface obsolescence 18
$2.SM
/4.tems Analysis Research RAMP RADIATION PROTECTION RESEARCH
- NuclearResearch Research for radiation protection, dose assessment, emergency response, and monitoring of radiation exposures for occupational safety.
This research promotes computer code development under RAMP. It also supports regulatory decisions affecting radiation protection through development of the abnormal occurrence report for Congress, REIRS, and occupational health RGs.
19 SOFTWARE Develop and maintain RAMP computer codes in the areas of nuclear power plant licensing and siting, decommissioning, atmospheric transport and dispersion, and emergency response.
CONSOLIDATION Gain RAMP computer code flexibility, efficiencies, and increased user-friendliness by consolidating similar dose assessment codes.
INTERNATIONAL Leverage global experti.se a d
research results to improve the RAMP computer codes.
/4.tems Analysis Research FY2 2
> Issue annual abnormal occurrence report for
/
Congress
> Issue annual REIRS report
> Complete atmospheric transport and dispersion module for the RAMP consolidated computer code FY 2 3
> Issue annual abnormal occurrence report for Congress 1/ > Issue annual REIRS report
> Issue RG 8.39, Revision 2, "Release of Patients Administered Radioactive Material" FY24
> Issue annual abnormal occurrence report for Congress 1/ > Issue annual REIRS report
> Complete consolidated RAMP computer code including the consolidated control room habitability, source term, and environmental pathways modules and user interface 20
$4.3M
FOCUS AREAS Delivering technology and engineering solutions to make the NRC a modern, risk-informed regulator
> Seismic, Geotechnical, and Structural
> Instrumentation, Electrical, and Cybersecurity
> Materials Performance 21
/4gineering Research
- SEISMIC, GEOTECHNICAL, &
STRUCTURAL
- NuclearResearch Performance assessment of nuclear power plant structures.
The performance of structures in nuclear installations is an essential aspect of their safety and security.
Safety-related systems, structures, and components must be designed to ensure performance of their intended safety functions under design-basis events as required by NRC regulations.
22 Hazard Analysis Data Analysis Long-Term Operation
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Engineering Research FY2ly Seismic site response-Senior Seismic Hazard Analysis Committee Level 2 study Research information letter on aging of posttensioned concrete containment vessels with emphasis on concrete creep and creep rupture Risk-informed, performance-based seismic safety and seismic isolation for advanced reactors Seismic source characterization and ground-motion model updates Three-dimensional physics-based ground motion study Irradiation-assisted concrete degradation Harvesting irradiated concrete materials Prestressed concrete containment aging Probabilistic liquefaction model development 23
$4.3M
/4gineering Research INSTRUMENTATION, ELECTRICAL, &
CVBERSECURITY
- NuclearResearch Research into digital instrumentation and control systems, cybersecurity, and electrical engineering.
Enables the safe use of new technologies in nuclear facilities, while also ensuring system security and data integrity. Also evaluates the potential degradation of electrical components and aging of cables in the existing fleet of nuclear power plants.
24 Instrumentation &
Control Engineering Safety
/
Engineering Research Research on potential cyber risks from wireless technologies in risk-significant networks Regulatory assessment of attack surface definitions, characterizations, and tools to assist cybersecurity Evaluation of the effectiveness of systems-theoretic accident model and processes-based methods for system hazard identification Evaluation of methodologies and results of hazard analyses for digital instrumentation and control systems Cybersecurity-focused overview of novel technology implementations in nuclear power plants Electrical cable condition monitoring assessment reports Criteria for determining the safety of wireless technologies at nuclear power plants Zero trust paradigm for cybersecurity in nuclear power plants Characterizing cybersecurity using Al/ML for safety, control, and cyber protection systems Contributions to Institute of Electrical and Electronics Engineers and International Electrotechnical Commission standards (all FYs)
Ongoing research regarding condition monitoring of cables at nuclear power plants 25
$3.SM
/4gineering Research MATERIALS PERFORMANCE
- NuclearResearch Assessment of materials performance for manufacturing and long-term plant operations to ensure component integrity.
Preparing for review of advanced manufacturing technology applications and industry proposals related to nondestrutctive examination. Also facilitates risk-informed decision-making for component integrity assessments and addresses the impacts of material degradation for long-term operation.
26 Emerging Applications Defense In Depth 1111 Software Tools and Evaluation
/
Engineering Research FY24/
Assessment of electron beam welding and powder metallurgy hot isostatic pressing Evaluation of modeling and simulation for ultrasonic examination predictions Issuance of probabilistic fracture mechanics RG Assessment of irradiated materials test results Release of flaw evaluation software Evaluation of advanced phased array ultrasonic techniques New release of the Fracture Analysis of Vessels-Probabilistic code and upgrades to the Extremely Low Probability of Rupture code Assessment of primary water stress corrosion cracking initiation testing of Alloy 690/52/152 materials Assessment of automated data analysis and ML for nondestructive examination Benchmarking of the Fracture Analysis of Vessels-Probabilistic code and the Extremely Low Probability of Rupture code Assessment of primary water stress corrosion cracking initiation testing of Alloy 690/52/152 weld dilution zones, heat affected zones, and weld defects 27
$9.0M
FOCUS AREAS Developing risk-informed solutions to current and anticipated regulatory challenges
> Human Reliability and Organizational Factors
> Operating Experience
> Risk Tools and Studies
> Fire Research and External Hazards Analysis 28
/4,k Analysis Research HUMAN RELIABILITY &
ORGANIZATIONAL FACTORS
- N uclearResearch Provides safety perspectives on the impact of human performance on nuclear power plants and other NRC-licensed facilities.
Improves understanding of complex human, organizational, and system interactions, which will help to ensure the continued safety of nuclear operations with novel technologies and advanced concepts of operation.
Virtually every system... places "operator error" high on its list of causal factors-generally about 60 to 80 percent of accidents are attributed to this factor.
Use state-of-the-art principles to develop human and organizational factors guidance +
' +
Apply robust scientific basis to develop and improve HRA methods for risk analyses 29 Leverage domestic and international programs to gain data and insights
/4k Analysis Research Fy2 2
> Enhance HRA method for all nuclear applications: IDHEAS
/
for Event and Condition Assessment
> Develop new method for performing dependency analysis in HRA applications: IDHEAS-Dependency
> Provide update on the human factors challenges associated with the incorporation of adaptive automation
> Report on the use of cognitive task analysis for human factors engineering reviews
> Complete human factors engineering training program Fy2 3
> Update human factors engineering program review model based on 1/
lessons learned from new and advanced reactor reviews
> Develop new method for calculating the effects of time on human error:
IDHEAS-Time
> Publish research information letters on the results of the NRC's human performance test facility experiments
> Enhance guidance for performing expert elicitations
> Enrich database on human error to support HRA method development:
IDHEAS-Data Fy24
> Update Human-System Interface Design Review Guidelines based on 1/
lessons learned from new and advanced reactor reviews
> Develop new method for crediting recovery actions in HRA:
IDHEAS-Recovery
> Enhance technical bases for minimum joint human error probabilities
> Issue guidance for the use of independent safety culture assessments in the nuclear industry 30
$3.SM
/4.k Analysis Research OPERATING EXPERIENCE
- NuclearResearch Evaluation of OpE to gain risk insights, understand industry performance, and inform NRC risk models.
The ASP Program evaluates OpE to identify precursors to potential core damage. OpE data collection and analysis looks for long-term component and system performance trends and is used for initiating event frequencies and failure parameters in the NRC's plant risk models.
31 RISK INSIGHTS Evaluates U.S.
nuclear power plant OpE to identify, document, and rank operational events by core damage probability parameters.
PUBLIC WEBPAGE Displays on the NRC's public webpage trends and insights from initiating events, system and component failures, and common-cause failures.
DATA ANALYTICS Collaboration with the U.S. Department of Energy to evaluate data analytics and Al/ML for use to increase the effectiveness of NRC OpE evaluations.
/4k Analysis Research Fy2 2
> Calendar year 2021 ASP analyses and issuance of
/
annual ASP report
> SPAR model data parameters update
> Evaluation of initiating and loss of offsite power events
> System and component reliability studies update
> Development and evaluation of component-specific priors for common-cause failures Fy2 3
> Calendar year 2022 ASP analyses and issuance of annual 1/ ASP report
> Evaluation of initiating and loss of offsite power events
> Collection, coding, and provide quality assurance of reactor operating data
> Maintenance and enhancement of the database that houses the long-term OpE data and licensee event reports Fy24
> Calendar year 2023 ASP analyses and issuance of annual 1/ ASP report
> Evaluation of initiating and loss of offsite power events
> Collection, coding, and provide quality assurance of reactor operating data
> Maintenance and enhancement of the database that houses the long-term OpE data and licensee event reports 32
$4.0M
/4.k Analysis Research RISK TOOLS&
STUDIES
- NuclearResearch Timely, realistic, and repeatable risk assessments to support NRC licensing, rulemaking, oversight, and OpE evaluation activities.
Risk tools support projects such as Level 3 PRA, which is a sitewide, full-scope PRA that includes all radioactive sources for a two-unit reference pressurized-water reactor.
This project is advancing the state of practice in areas such as human reliability, multiunit risk, severe accidents, and more.
33 RISK MODELS Maintain the NRC's SPAR models for all operating nuclear power plants with the goal of reflecting current designs and operations.
SOFTWARE Use the SAPHIRE computer code to support the development of the agency's SPAR models.
RISK ASSESSMENT Provide living Level 1, 2, and 3 PRA models to support enhanced risk-informed decision-making and analyses of emerging technologies.
/4k Analysis Research FY2 2
> SAPHIRE updates to add user-requested features
/
> Hundreds of requested SPAR model changes to support event and condition assessments
> SPAR dashboard for expanded access to risk insights from SPAR models for nonrisk experts
> Level 3 PRA project internal reports for reactor low power and shutdown, spent fuel pool, and dry cask storage
> Draft NUREGs for comment on reactor, at-power, internal events and internal floods, and dry cask storage 23
> SAPHIRE Version 9.0 with cloud-based capabilities FY
~ / > Hundreds of requested SPAR model changes to support event and
/
condition assessments
> Expanded SPAR model capabilities in external hazards, diverse and flexible coping strategies, and HRA
> Level 3 PRA project internal report for integrated site risk
> Draft NUREGs for comment on reactor, at-power, internal fires, seismic and high winds; reactor, low power and shutdown; and spent fuel pools Fy24
> Integration of IDHEAS for Event and Condition Assessment into 1/
SAPHIRE as a replacement for SPAR-H
> Hundreds of requested SPAR model changes to support event and condition assessments
> Enhancements to SAPHIRE and SPAR models to assess time-sensitive and quickly changing conditions
> Draft Level 3 PRA NUREGs for comment on integrated site risk and project summary 34
$4.4M
/4,k Analysis Research FIRE RESEARCH & EXTERNAL HAZARDS ANALYSIS
- N uclearResearch Research to develop the tools, methods, and data for analyzing risks from fire and external hazards.
NRC regulations require each operating nuclear unit to be capable of performing safe shutdown and maintenance of the reactor when challenged by a fire or other natural hazards.
Research enhances realism in fire and other external hazard PRAs to support risk-informed decision-making.
We learn from every natural disaster.
Whether it's a fire or a flood, we learn something from it so we can Analyze fire hazards and the impact on reactor safety in a probabilistic framework respond to the better.
L
+Assess potential ris+
of external flooding and the impact on reactor safety in a probabilistic framework 35 Systematically assess new natural hazard information and its impacts on existing estimates
/4k Analysis Research Fy2 2
> In cooperation with the Electric Power Research Institute,
/
develop an improved methodology for assessing fire risk including HEAFs
> Lead the OECD/NEA testing program for HEAF
> Perform fire PRA model refinements to improve PRA realism; update methods in NUREG/CR-6850
> Develop draft probabilistic flood hazard assessment guidance
> Maintain the NRC's Natural Hazard Information Digest
> Host annual workshops and knowledge management training Fy2 3
> Co~plete testing and publish results from the OECD/NEA HEAF 1/ testing program
> Perform fire PRA model refinements to improve PRA realism; update methods in NUREG/CR-6850, including the development of low power and shutdown risk for fire PRAs
> Publish draft probabilistic flood hazard assessment regulatory guidance for public comment
> Maintain and expand the NRC's Natural Hazard Information Digest
> Host annual workshops and knowledge management training Fy24
> Continue to develop tools, methods, and data to improve realism in 1/ fire PRAs, including updates based on fire frequency and OpE
> Publish final probabilistic flood hazard assessment regulatory guidance
> Maintain and expand the NRC's Natural Hazard Information Digest
> Research extreme weather events, such as cold-air outbreaks and high winds, in the context of climate change and their potential hazards for nuclear power plants
> Host annual workshops and knowledge management training 36
$2.4M
Operating Reactors Nuclear Materials