ML21019A462
| ML21019A462 | |
| Person / Time | |
|---|---|
| Issue date: | 01/21/2021 |
| From: | Jordan Hoellman NRC/NRR/DANU/UARP |
| To: | |
| Hoellman J,NRC/NRR/DANU/UARP | |
| References | |
| Download: ML21019A462 (112) | |
Text
Advanced Reactor Stakeholder Public Meeting January 21, 2021 Microsoft Teams Meeting Bridgeline: 301-576-2978 Conference ID: 644 910 374#
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Time Agenda Speaker 10:00 - 10:15 am Opening Remarks NRC Regulatory Priorities for New and Advanced Reactors -
10:15 - 10:30 am M. Shams, NRC NRC Feedback on NEI Input Pre-application Engagement White Paper - Incorporation of 10:30 - 11:00 am A. Muniz, NRC Feedback from November 5, 2020, Stakeholder Meeting Pre-application Engagement for Greater Enrichment of Fuels 11:00 - 11:30 am M. Diaz, NRC for Advanced Reactors D. Clayton, Sandia Incorporation of HySplit Atmospheric Transport Dispersion 11:30 am - 12:00 pm National (ATD) Model into MACCS to Advance ATD Capabilities Laboratories Status of NRCs Endorsement Review of the Advanced Non-12:00 - 12:15 pm Light Water Reactor (ANLWR) Probabilistic Risk Assessment M. Gonzalez, NRC (PRA) Standard 12:15 - 1:00 pm BREAK All U.S. Department of Energy (DOE) Gateway for Accelerated 1:00 - 1:45 pm C. King, DOE/GAIN Innovation in Nuclear (GAIN) Initiatives DOE Advanced Reactor Demonstration Program (ARDP) 1:45 - 2:15 pm T. Beville, DOE-NE Update 2:15 - 2:45 pm ASME Section III, Division 5 - Discussion of Contractor J. Hoellman and Reports Supporting NRC Endorsement J. Poehler, NRC 2:45 - 3:00 pm Concluding Remarks and2 ofFuture 112 Meeting Planning NRC/All
Advanced Reactor Integrated Schedule of Activities https://www.nrc.gov/reactors/new-reactors/advanced.html 3 of 112
NRC feedback on NEI Input on Regulatory Priorities for New and Advanced Reactors January 21, 2021 Mohamed Shams, Director Division of Advanced Reactors and Non-Power Production and Utilization Facilities (DANU) 4 of 112
Background
- NEI letter dated December 18, 2020 (ML20353A393)
- NEI recommended establishing the following key regulatory objectives to inform NRC priorities:
- 1. Streamlining of regulatory processes needed to support the timely and efficient review and oversight of new and advanced reactors.
- 2. Resolution of key generic technical or policy topics needed to support the review and approval of new and advanced reactor applications.
- 3. Changes to the regulations that are needed to achieve a more modern and efficient regulatory framework.
- Specific recommendations provided in an enclosure 5 of 112
Overview
- The staff appreciates NEIs input.
- The recommended key regulatory objectives are consistent with the NRCs vision and strategy for advanced reactor readiness.
- Our ongoing activities align with the NEIs specific recommendations
- Some differences in schedules 6 of 112
Ongoing:
- Alternative Physical Security Several Requirements for Advanced Reactors (PR 4Q2021, FR 2Q2023) rulemakings
- Advanced Nuclear Reactor Generic Environmental Impact Statement (GEIS) are underway
- Emergency Preparedness Requirements for Small Modular Reactors and Other to modernize New Technologies (FR 4Q2021)
- Alignment of Licensing Processes and the regulatory Lessons Learned from New Reactor Licensing (10 CFR Part 50 and 52) framework Planned:
- Annual Fee Rule for Non-LWRs (FY2022)
- Part 51 PR = Proposed Rule FR = Final Rule 7 of 112
NEI Letter NRC Activities NRC generic environmental impact statements (GEISs) that minimizes the GEIS rulemaking underway.
scope of site-specific environmental reviews NRC is taking NRC guidance on the broader use of environmental assessments (EAs) and Rulemaking for categorical exclusion is underway and staff will consider EAs for action to categorical exclusions microreactors under rulemaking.
NRC NEPA regulation already allows for NRC allows existing environmental analyses environmental analyses to be incorporated optimize the to be incorporated into a projects EA or EIS into EAs and or EISs.
NRC clarity on an approach to use the environmental applicants environmental report (ER) as the Not a planned activity draft EA or EIS ISG-029 provides guidance to the staff on NRC elimination of unnecessary burden in reviews alternative site analysis focusing its review of the alternative site analysis.
NRC implementation of changes that Ongoing activities: Issued ISG-029, increases efficiency of environmental developing a GEIS, and participates in FAST-reviews 41 and EO-13807 (one Federal Decision).
Not a planned activity: This requires NRC elimination of duplicative adjudicatory Commission decision and possible hearings for NRC environmental reviews rulemaking.
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- ISG for Construction Permit Applications Ongoing
- Technology Inclusive Content guidance of Applications Guidance (TICAP) (2021) development
- Advanced Reactor Content of facilitates Applications Guidance (ARCAP)
(ISGs in 2021) safety-focused
- Fuel Qualification reviews
- Endorsement Non-LWR PRA standard
- Environmental ISG (Issued) 9 of 112
- The staff has published generic licensing review schedules in accordance with Section 102(c) of NRCs NEIMA https://www.nrc.gov/about-nrc/generic-schedules.html.
actions
- The staff has developed a preapplication white paper to encourage robust preapplication interactions to facilitate and shorter review schedules.
- The staff has implemented strategies such as core review initiatives teams and the use of audits to facilitate timely and efficient reviews.
continue
- The staff is working on guidance to focus the level of detail in applications and to focus the staffs review on safety and to improve risk significant areas.
review
- The staff completed the NuScale DC, Clinch River ESP, and APR1400 DC reviews on or ahead of schedule.
timeliness
- In all cases, adequate time will be taken to provide reasonable assurance of adequate protection to the health and safety of the public.
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- Siting - awaiting Commission SRM
- Advanced Manufacturing Technologies (AMT)
- AMT Action plan was published in July 2020 Staff is (ML19333B980) working to - Public workshop was held in December 2020
- Initial AMT application and review guidelines timely resolve framework document (Subtask 2C in the Action Plan) published July 2020 technical and (ML20203M254) (Revision under policy topics development).
- Applicability of Regulations to Non-LWRs
- Staff response to NEI input planned in early 2021
- Revision to staff white paper planned in 2021 11 of 112
Conclusion
- Staff will continue to seek input from stakeholders on ongoing and planned activities
- Staff priorities are focused on ongoing license application reviews, preapplication engagement reviews, NEIMA required activities, Commission directed rulemakings, and activities to prepare for new applications.
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Finalization of Draft White Paper -
Preapplication Engagement to Optimize Application Reviews Adrian Muniz, Project Manager Advanced Reactor Licensing Branch January 21, 2021 13 of 112
- Draft White Paper was discussed during the Background 11/05/2020 advanced reactor meeting
- Stakeholders provided feedback for staffs consideration
- NRC staff considered the comments and is revising the document, as appropriate
- See ADAMS Accession No. ML21014A267 for current version 2
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- Clarified the need for pre-application engagement to support efficient application reviews. Key areas include:
- Preliminary PRA and/or peer review results for audit
- PRA acceptability for its use in the application
- Deviations from endorsed standards and staff guidance Summary of
- Early availability of risk insights
- Level of detail and degree of realism of PRAs for different licensing applications including construction permit
- Regulatory Exemptions Key Changes - Regulatory gap analysis should be informed by staffs draft white paper titled Analysis of Applicability of NRC Regulations for Non-LWRs
- Environmental Sections
- Updated the list of guidance documents that should be considered in developing an environmental report in preparation for pre-application interactions
- Revised and clarified examples of issues that have been challenging for previous combined license and early site permit application reviews
- Clarified the timeframe to begin pre-application interactions 3
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- Review and concurrence of Revised Draft White Paper for final issuance NEXT STEPS
- Final White Paper will be posted on NRCs advanced reactors website 4
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5 Questions?
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NMSS/DFM Pre-application Engagement for Advanced Reactor Fuels Fuel Cycle Facilities, Transportation &
Storage January 21, 2021 Marilyn Diaz Office of Nuclear Material Safety and Safeguards (NMSS)
Division of Fuel Management (DFM) 18 of 112
NMSS/DFM Advanced Reactor Fuel Activities Support NRR Advanced Reactor (AR) program.
Readiness to license and certify fuel facilities, transportation packages, and spent fuel storage installations.
Enrichment (10 CFR Part 70),
Fuel fabrication (10 CFR Part 70),
Transportation package certification (10 CFR Part 71),
Spent fuel storage installations (10 CFR Part 72),
Material Control & Accounting (MC&A) (10 CFR Part 74) 19 of 112 2
Readiness Activities - Fuel Cycle Facilities Regulations (10 CFR Part 70) are adequate for the review of fuel enrichment and fabrication for technologies being developed at higher enrichments.
We continue to assess our regulatory framework to identify any challenges and/or data needs.
We are conducting technical evaluations to assess necessary updates for the guidance to account for AR designs Finalized report on possible material control and accounting approaches for a pebble bed reactor (ML20112F355).
Updating NRC guidance for material control and accounting for Category II fuel cycle facilities.
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Readiness Activities - Storage, Transportation & Disposal We have experience in the approval of transportation packages and storage systems for TRISO and metallic fuels.
We are completing technical evaluations on transport and storage activities of ARF designs to identify potential information needs and determine whether additional updates to safety review guidance may be warranted.
Review of Operating Experience for Transportation of Fresh (Unirradiated) Advanced Reactor Fuel Types Potential Challenges with Transportation of Fresh (Unirradiated) Advanced Reactor Fuel Types Storage Experience with Spent (Irradiated) Advanced Reactor Fuel Types Potential Challenges with Storage of Spent (Irradiated) Advanced Reactor Fuel Types Transportation Experience and Potential Challenges with Transportation of Spent (Irradiated) Advanced Reactor Fuel Types Disposal Options and Potential Challenges to Waste Packages and Waste Forms in Disposal of Spent (Irradiated)
Advanced Reactor Fuel Types 21 of 112 4
How are we preparing?
Meetings between AR vendors will help staff gain knowledge on specific designs and technologies.
Training sessions will provide staff with insights into significant safety features of specific designs and technologies.
Technical reports addressing potential challenges will help staff risk inform their reviews.
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Pre- Application Engagements We encourage pre-application engagements to support an efficient review of new applications and amendments.
- NMSS/DFM Letters to Advanced Reactors Stakeholders to encourage potential applicants to engage in early communication and interactions.
Pre-application engagements provide benefits for NRC staff and applicants.
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Conclusions NMSS/DFM is proactively identifying potential technical challenges and information needs associated with the safe use of AR fuels in the areas of enrichment, fabrication, transport and storage.
NRC expects some of the efforts related to accident tolerant fuel to benefit the licensing and certification of ARFs.
Applicants are encouraged to engage early to ensure a common understanding of the regulatory issues associated with new AR fuel technologies.
We have experience with advanced technologies with regards to fuel cycle and transportation licensing, and we have the regulatory infrastructure in place. We continue to gather information to ensure our readiness. 7 24 of 112
Marilyn Diaz U. S. Nuclear Regulatory Commission Office of Nuclear Material Safety and Safeguards Division of Fuel Management Marilyn.Diaz@nrc.gov 301-415-7110 25 of 112
Incorporation of HYSPLIT Atmospheric Transport and Dispersion (ATD) Model into MACCS to Advance ATD Capabilities PRESENTED BY Dan Clayton Sandia National Laboratories Presented at the Advanced Reactor Stakeholder Meeting , January 21, 2021 Sandia National Laboratories is a multimission laboratory managed and operated by National Technology & Engineering Solutions of Sandia, LLC, a wholly owned subsidiary of Honeywell 26 of 112 International Inc., for the U.S. Department of Energys National Nuclear Security Administration under contract DE-NA0003525.
SAND2021-0549 PE
=
Background===
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Purpose for MACCS Created by Sandia to support NRC research and regulatory requirements
- Origins go back to the mid-1970s Typically used for prospective analyses, e.g.,
- Probabilistic risk assessments (NUREG-1150 and Level 3 PRA)
- Probabilistic consequence assessments (SOARCA)
- Cost/benefit analyses (commonly used for environmental analyses in licensing)
Very versatile with a large set of user inputs
- Intended to run rapidly for PRA applications
- Large set of weather trials (hundreds or thousands)
- Significant set of release categories (ten or twenty)
A release category is a group of similar source terms that can be represented by one or a few source terms.
Each source term can be complex, multi-isotope, and time-dependent.
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Challenges to Gaussian Plume Model Use of Gaussian model questioned
- Adequacy at locations that experience lake or sea breezes
- Suitability for river valleys that strongly influence local winds
- Adequacy for areas with significant surface relief
- Distance to which a Gaussian plume model is reliable Challenges motivated a detailed benchmark study (NUREG-6853, 2004)
- Four ATD models Lagrangian model (LODI)
Two Gaussian puff models (RASCAL and RATCHET)
Gaussian plume segment model (MACCS)
- Showed differences in the annual average exposure and deposition results were nearly within a factor of two out to 100 miles
- Did not address sea breezes, river valleys, or other terrain variations 29 of 112 4
HYSPLIT Selection 30 of 112
Selection of Advanced ATD Model Essential features
- Treats Lagrangian particles
- Executable can be distributed to users (either by Sandia or directly from developer)
- Source code available in case modifications are required for integration
- Code meets QA requirements
- Treats 3D wind field (gridded data)
Desirable features
- Can model both puffs and particles
- Supports a variety of gridded weather data formats
- Facilitates graphical post processing 31 of 112 6
Evaluation of Advanced ATD Model HYSPLIT FLEXPART LODI CALPUFF RASCAL SCIPUFF Includes Essential Feature Distributable Yes Yes No Yes Yes Yes Source Code Yes Yes No No Yes No QA Yes Yes Yes Yes Yes Yes Treats 3D Wind Yes Yes Yes Yes No Yes Meets All Yes Yes No No No No Requirements Score on Desirable Feature Puffs & Particles 5 3 Not scored Not scored Not scored Not scored Weather Formats 5 4 Not scored Not scored Not scored Not scored Graphics 5 1 Not scored Not scored Not scored Not scored Supports Linux &
5 5 Not scored Not scored Not scored Not scored PC Total Score 20 13 Not scored Not scored Not scored Not scored 32 of 112 7
Interface Requirements Multiple aerosol diameters (typically 10) plus inert gases Variable emission rates Multiple release elevations Transient air and ground concentrations (to work with evacuation model)
Option to choose particles or puffs One year of weather data to support weather sampling Mapping native concentration grid to MACCS grid 33 of 112 8
Implementation 34 of 112
MACCS Modules ATMOS
- Source term definition
- Weather sampling algorithms
- Atmospheric transport, dispersion, and deposition Option for either HYSPLIT or Gaussian model EARLY (1 to 40 days)
- Doses as modified by emergency-phase countermeasures such as sheltering, evacuation, relocation, and KI ingestion
- Multiple population cohorts
- Acute and latent health effects from early acute exposure CHRONC (1 week to >50 years)
- Doses as modified by intermediate and recovery-phase protective actions such as relocation, interdiction, decontamination, and condemnation
- Latent health effects from chronic exposure to deposited materal
- Economic impact from early and late phase protective actions 35 of 112 10
Implementation Choices Unit releases without radioactive decay and ingrowth in HYSPLIT (MACCS treats these aspects) for each hour of a calendar year MACCS then scales and sums unit releases to account for variable emission rates Releases at several fixed elevations or buoyancy fluxes (MACCS determines which to use)
Multiple aerosol diameters with possibilities for dry deposition, wet deposition, both, or neither
- 2*N+2 possibilities for N aerosol diameters Air and ground concentrations tracked at time interval
- 60 min, 15 min, 5 min, 1 min 36 of 112 11
Overall Process 37 of 112 12
Generating HYSPLIT Files 38 of 112 13
Normalized Release Release one-Bq of a tracer species for each aerosol size over a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period and then track during transport
- Generating /Q and D/Q values for each period and aerosol size
- One year equates to 8,760 simulations
- Provides enough data to effectively model any source term over every hour for the entire year Expanded to account for buoyancy effects
- Requires additional sets (8,760 more runs per year) for each additional release level
- Specify sets of release heights or power levels
- Release heights utilize MACCS calculated rise heights
- Powel levels determine rise heights from HYSPLIT buoyancy calculations
- Appropriate file set determined based on weather conditions and plume segment sensible heat 39 of 112 14
GenHysplit Code Used to generate and organize the HYSPLIT output concentration files Configured to run on a Linux system to be able to access large computer resources at Sandia National Laboratories
- Has also been run in a Windows environment
- Preliminary testing on a cloud-based machine Designed to be flexible
- Many options controlled by input file 40 of 112 15
Converting HYSPLIT Output to MACCS Input 41 of 112 16
HyGridConvert Code MACCS utilizes a non-uniform polar grid Converts the HYSPLIT output concentrations to defined MACCS polar grid Configured to run on a Windows machine Can be run separately or called by WinMACCS (preferred).
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MACCS Meteorological Preprocessor 43 of 112 18
MacMetGen Description MACCS-formatted meteorological file needed for MACCS calculations
- Weather sampling
- Calculating plume rise height (if binned release heights used)
- Precipitation effects on evacuation speed Can be time consuming to collect site data and compile into file MacMetGen developed to automate MACCS formatted meteorological file generation Makes use of same meteorological files used to drive HYSPLIT
- Ensure consistency
- Can be any data set if in similar format 44 of 112 19
MacMetGen Information Flow 45 of 112 20
MACCS Use of HYSPLIT Data 46 of 112 21
Combination with Source Term Break each plume into one-hour segments and associate each one hour segment with a single HYSPLIT converted file (mcd file)
For each segment, multiply the normalized concentrations for each aerosol bin by the actual hourly release amounts for each different radionuclide/aerosol size Account for the radioactive decay and ingrowth at the time in the calculation Results in an air and a ground concentration array as a function of radionuclide, grid cell and time in MACCS These concentrations are then used by MACCS to determine consequences using the EARLY and CHRONC modules 47 of 112 22
Verification 48 of 112
Verification Test Cases Test cases were created to verify the implementation of the HYSPLIT/MACCS coupling Compared results from HYSPLIT/MACCS with HYSPLIT standalone Modified Inputs
- Single plume segment -> Multiple plume segments
- Single, fixed deposition velocity -> Ten aerosol sizes, each with own deposition velocity calculated from internal HYSPLIT model
- Constant weather -> Spatially and temporally varying weather
- Insignificant radioactive decay -> Significant radioactive decay
- No evacuation -> With evacuation 49 of 112 24
Compared Results Atmospheric Model Outputs
- Peak (around the compass) time-integrated air concentration (/Q, s/m3) over the region
- Peak (around the compass) ground concentration (D/Q, 1/m2) over the region
- Land areas (km2) that exceed various levels of contamination Consequence Output
- Peak (around the compass) ionizing radiation dose (Sv) over the region 50 of 112 25
Test Result Summary All quantities for all six text cases match at all distances Test Case 1 comparison of peak air concentration Test Case 1 comparison of land areas that exceed 1,000 Ci/m2 51 of 112 26
Wrap-up 52 of 112
Summary MACCS coupled with HYSPLIT has been implemented and verified
- Supplements Gaussian plume segment model in MACCS with an alternative The ability to incorporate HYSPLIT model results in MACCS is a major improvement in the capabilities of MACCS simulations and provides a state-of-the-art alternative to the use of the Gaussian plume segment model Need to balance the need for higher fidelity models with associated higher computational costs 53 of 112 28
Status and Plans to Develop Regulatory Guide Endorsing the Advanced Non-LWR PRA Standard Advanced Reactor Stakeholder Meeting January 21, 2021 Michelle Gonzalez, RES 54 of 112 1
Agenda
- Update of Staff Endorsement of the ASME/ANS Advanced Non-LWR PRA Standard
- Development of Staff White Paper on PRA Acceptability for ANLWRs
- Schedule 55 of 112 2
- JCNRM ballot of the ANLWR PRA Standard ASME/ANS RA-S-1.4-2021
- Initial ballot- May 2020
- Recirculation ballot- August, 2020 Update on
- Final issuance by ANSI anticipated Staff February 2021 (tentative)
- NEI 20-09 (Rev 0)- Performance of PRA Endorsement Peer Reviews Using the ASME/ANS Advanced Non-LWR PRA Standard
- Initially submitted May 2020. Public meetings held July, October and December 2020.
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- Development of the staff position for an acceptable ANLWR PRA
- Identify and resolve technical and policy issues Staff - Early communication of staff views and perspectives - draft white paper Activities
- Development of trial use regulatory guide
- Engagement with internal stakeholders (management, OGC, ACRS). Engagement with external stakeholders (public, potential applicants)
- Update the action plan for ANLWR PRA Standard Endorsement 57 of 112 4
Development of Regulatory Guidance on PRA Acceptability for ANLWRs 58 of 112 5
Considerations
- Endorsements:
- ANLWR PRA standard, ASME/ANS RA-S-1.4-2021
- Peer review guidance, NEI 20-09
- Based on NEI 17-07, Rev. 2 which has been endorsed
- Approach for providing staff views:
- Draft white paper: provides staff views and perspectives, not formal staff positions
- Trial-use regulatory guide: provides formal staff position and endorsement
- Timing:
- Support near-term applicants
- Promote long-term regulatory stability 59 of 112 6
Draft White Paper
- NRC Staff Draft White Paper: Demonstrating the Acceptability of Probabilistic Risk Assessment Results Used to Support Advanced Non-Light Water Reactor Plant Licensing
- Issued January 15, 2021 - ML21015A434
- Meeting planned for February 2021 to discuss in detail 60 of 112 7
Schedule Milestone Activity 1/15/2021 Issue staff draft white paper Present staff draft white paper at Advanced Reactors 1/21/2021 Stakeholders meeting JCNRM publishes ASME/ANS RA-S-1.4-2021 Late February 2021 NRC begins review of latest available version of NEI 20-09 February/March Tentative public meeting on draft white paper and NEI 20-09 2021 June 2021 RG technically complete; start RG publication process December 2021 RG issued for trial use Revise trial-use RG to incorporate lessons learned and revision TBD to ASME/ANS RA-S-1.4 (anticipated in 2023-2024) 61 of 112 8
Advanced Reactor Stakeholder Public Meeting Break Meeting will resume at 1pm EST Microsoft Teams Meeting Bridgeline: 301-576-2978 Conference ID: 644 910 374#
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GAIN Overview NRC Advanced Reactor Stakeholder Meeting Christine King, GAIN Director January 21, 2021 63 of 112 @GAINnuclear gain.inl.gov
Mission and Vision Vision (2030)
The U.S. nuclear industry is equipped to lead the world in deployment of innovative nuclear technologies to supply urgently needed abundant clean energy, Mission both domestically and globally. Provide the nuclear energy industry with access to cutting-edge R&D, along with the technical, regulatory, and financial support necessary to move innovative nuclear energy technologies toward commercialization in an accelerated and cost-effective fashion.
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65 of 112 NRIC and GAIN are Complementary and Coordinated Efforts to Support the Nuclear Energy Industry
- Provides a capability for building
- Established in 2015 as a resource for and demonstrating reactor accelerated development of nuclear concepts innovations with lab partners
- Focused program to enable innovators nearing
- Comprehensive resource to entire nuclear demonstration stage innovation ecosystem at all development
- Provides access to sites, required upgrades, site stages services, fuel material/fabrication facilities, and demonstration process support
- Provides streamlined access to testing, MASL,
- Provides regulatory assistance related to experimental facilities, lab expertise, and demonstration legacy data
- Facilitates NRC observation/ learning
- Regulatory expertise (e.g. NRC advanced reactor licensing strategy support)
- Manages NE Vouchers 66 of 112
GAIN Goals for FY 2020-2025:
Goal #1. Provide nuclear industry entities access to financial support opportunities and national laboratory capabilities (facilities, expertise, and tools) to accelerate commercialization of innovations through research, development, demonstration, and deployment.
Goal #2. Work with industry to identify gaps, gather needs, and develop viable paths forward to inform DOE research programs and remove barriers for industry.
Goal #3. Work with industry stakeholders and NRC as means of communicating and resolving common (industry-wide) issues through regulatory interactions.
Goal #4. Facilitate the advanced nuclear industrys access to information to support their technology commercialization efforts.
Goal #5. Contribute tailored, factual information to key stakeholders to motivate the integration of clean nuclear energy for long-term success.
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How to do Business with GAIN
- Provides Contract Mechanisms on one side and Funding Opportunities on the other
- Information applies to all the DOE national labs in their contracting discussions with industry 68 of 112
GAIN NE Voucher Awards for Round 1, FY2021
- The TerraPower voucher represents the first voucher to be awarded for work at LANL and involves characterization of the properties of plutonium chloride salt using neutron beam imaging in the LANSCE facility.
- The two vouchers to be completed at ORNL involve utilization of modeling and simulation capability in support of innovations in additive manufacturing.
Date to Remember:
NE Vouchers Round 2 2021: Close on Feb 1, 2021 iFOA Round 1 2021: Close on Feb 28, 2021 69 of 112
GAIN FY2020 Voucher Awards FY 2020 Voucher Recipient Proposal Lab Round 1 Hydromine, Inc. On-Line Lead/Water Heat Exchanger Sensor/System Feasibility PNNL Round 1 Lightbridge Cor Advanced Test Reactor experiment design for measurement of Lightbridge INL Fuel' thermophysical properties Round 2 Neutroelectric Combined effects testing of high-temperature and neutron fluence to ORNL support qualification of NE-300, a high-temp Neutron shielding Material Round 2 Oklo, Inc. Address gaps in legacy data on fuel steel interactions INL Round 3 SMR, LLC Coupled neutronic and thermal hydraulic analysis of a natural circulation ORNL based small modular reactor using VERA-CS Round 3 Ultra Safe Nuclear Corp Graphite finite element model verification ORNL Round 4 Kairos Power Pebble Bed Large Eddy Simulations for Lower Order Methods ANL Benchmarking and Uncertainty Quantification Development Round 4 Natura Resources, LLC RELAP5-3D Development and Assessment for Liquid-fuels Molten Salt INL Reactor Licensure Round 4 TerraPower, LLC Thermophysical Properties Measurements of NaCl-PuCl3 ANL 70 of 112 8
GAIN Voucher Impact - 2020 Voucher Summary
- 54 Awarded
- 27 Completed
- $18.8 M to National Labs
- Total Project Costs $23.6 M 16Nov20 71 of 112 9
GAIN Assistance on Process Improvement NE Advance Class Patent Waiver GAIN Access CRADA (in process)
- DOE forgoes taking title to patentable
- Enable an industry partner to sign an agreement inventions conceived using DOE funding with a single lab that grants them simultaneous
- Advance: Available when contract access to other labs in the complex.
negotiations begin
- Conceptually how this works:
- Class: large domestic businesses in - Industry partner with workscope that crosses DOE-NE related funding multiple labs opportunities.(note: small business have - Identify the lead lab and negotiate CRADA this with Bayh-Doyle legislation)
- Partner Labs review CRADA and sign on to
- This waiver will speed up negotiations for agreement.
iFOA and ARD awards and reduce
- Allows us single agreements across DOE Offices uncertainty in negotiations of NE and Science More info on gain.inl.gov 72 of 112 10
Legacy Documents / Industry Access Initial Fast Reactor (FR) Technology List provides access to 4250 openly published FR documents available from OSTI (December 2018)
Initial Molten Salt Reactor (MSR) Technology List provides access to 210 cataloged MSR documents available on OSTI (February 2017)
OSTI Spreadsheet of 12,000 Applied Technology (AT) Documents with abstracts provided to GAIN. List released with abstracts on February 28, 2019. Provided to TWG Chairs on March 8, 2019.
Clinch River Breeder Reactor (CRBR) Project documents. Contract initiated in Feb 2020. Scanning on hold (COVID-19). Iron Mountain will proceed as soon as possible (235 boxes + 75 reels of microfilm).
LOFT and other LWR Experiments. Fauske and Associates developed a pilot knowledge preservation activity in March 2019.
Phase II contract will proceed in FY2021.
New Production Reactor (NPR) documents at INL Storage (125 boxes-Idaho Falls). Working with Red Ink to scan and organize files for Export/Classification Reviews. Effort is underway.
Loft Experiment Data for code validation (Box of data -INL - to be scanned & reviewed.
PBF Documents (3 boxes at INL) will be scanned and reviewed.
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Databases of Experimental Information Database Lab Status (18Jan21)
TREXR ANL https://www.trexr.anl.gov/
TREAT Experiment Relational Database External access available by application NaSCoRD SNL https://www.sandia.gov/nascord/
Sodium System & Component Reliability Database Phase II Complete - FY20.
ETTD ANL https://ettd.ne.anl.gov/
EBR-II Transient Testing Database External access available by application FIPD ANL https://fipd.ne.anl.gov/
EBR-II Metallic Fuel Irradiation Database External access available by application. Data for U-Zr fuel type employed in commercial designs being qualified in accordance with NRC approved QAPP.
FFTF PNNL https://pnnl.gov/projects/fftf/
Passive Safety Testing & Metal Fuel Irradiation Database External Access Plan Complete; will be implemented FY21.
OPTD ANL https://optd.ne.anl.gov/
Out of Pile Transient Testing Database External access available by application INL/ANL Organized effort to supplement the FIPD and FFTF EBR-II and FFTF Metal Fuel Experiment PIE Data Databases. Complete in 2021.
MSRE ORNL/EPRI Available FY-2021- under export control review Molten Salt Reactor Component Reliability Database 74 of 112 https://newton.ornl.gov/test/msre/app/
All databases will have links available at gain.inl.gov
Whats New? GAIN Workshops and Webinars - 2021 GAIN Webinar Series Focused on Multi-Industry Stakeholders Workshops Focused on Advanced Nuclear Needs and Feedback
- April 13-15. 2021: GAIN-EPRI-NEI Safeguards Program Virtual Workshop
- May 12-13, 2021: GAIN-EPRI-NEI Microreactor
- January 27, 2021: Paving the Way - A Historic Journey to Program Virtual Workshop Deployment
- February 2021: Understanding and Navigating Within the Existing Regulatory Framework
- August 24-26, 2021: GAIN-EPRI-NEI Advanced
- March 2021: Identifying and Managing Regulatory Risk on Methods for Manufacturing Qualification the Paths to Successful Deployment
- GAIN Net Zero Carbon Webinar Series
- February-March 2021: First Webinar in the Series Stay tuned for more information !!!
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GAIN Outreach Nuclear-focused Collaborators
- Nuclear Energy Institute
- Electric Power Research Institute
- Envoy Public Labs
- Third Way
- Clearpath
- Titans of Nuclear
- Generation Atomic
- American Nuclear Society
- Nuclear Innovation Alliance 76 of 112
Titans of Nuclear GAIN-NRIC Miniseries: Realizing the Nuclear Future Titans of Nuclear produces podcasts featuring interviews with experts across technology, industry, economics, policy and more.
Connect with what excites you about nuclear today and imagine nuclear tomorrow.
https://www.titansofnuclear.com/
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NE STRATEGIC VISION A thriving U.S. nuclear energy sector delivering clean energy and economic opportunities.
Advance nuclear energy science and technology to meet U.S. energy, environmental, and economic needs.
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STRATEGIC GOALS 79 of 112
Develop technologies that reduce By 2022, demonstrate a scalable hydrogen generation pilot plant.
operating costs.
By 2025, begin replacing existing fuel in U.S. commercial reactors with Expand to markets beyond electricity. accident tolerant fuel.
Provide scientific basis for continued By 2026, complete engineering and licensing activities needed to operation of existing plants. demonstrate successful deployment of a digital reactor safety system in an operating plant.
By 2030, achieve widespread implementation of accident tolerant fuel.
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By 2024, demonstrate and test a fueled microreactor core fabricated by advanced manufacturing techniques.
Reduce risk and time needed to By 2025, enable demonstration of a commercial U.S. microreactor.
deploy advanced nuclear technology. By 2027, demonstrate operation of a nuclear-renewable hybrid energy Develop reactors that expand market system.
opportunities for nuclear energy. By 2028, demonstrate two U.S. advanced reactor designs through cost-Support a diversity of designs that shared partnerships with industry.
improve resource utilization. By 2029, enable operation of the first commercial U.S. small modular reactor.
By 2035, demonstrate 81 of 112 at least two additional advanced reactor designs through partnerships with industry.
Address gaps in the domestic nuclear By 2021, begin procurement process for establishing a uranium fuel supply chain. reserve.
Address gaps in the domestic nuclear By 2022, demonstrate domestic HALEU enrichment.
fuel cycle for advanced reactors.
By 2023, make available up to five metric tons of HALEU from non-Evaluate options to establish an defense DOE material.
integrated waste management system.
By 2030, evaluate fuel cycles for advanced reactors.
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Gateway for Accelerated Innovation in Nuclear
- Accelerated must match advanced nuclear developer pace and reflect the market window (next 5-10 years).
- Innovation is not just about technology. Be creative in all spaces with a bias to taking risks.
- Focus on initiating and completing projects that support commercial deployment.
Questions? Reach out to gain@inl.gov (or one of our team members.)
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@GAINnuclear gain.inl.gov
GAIN Organization 84 of 112
Overview of Advanced Reactor Tim Beville - Director, Advanced Reactor Demonstration Program Demonstration Program Office of Nuclear Energy January 21, 2021 85 of 112
Topics to be Covered
- Advanced Reactor Demonstration Program (ARDP) Overview
- Advanced Reactor Demonstration Funding Opportunity Announcement (FOA) Overview
- Announced ARD FOA Awards
- Summary/Questions 86 of 112 2 energy.gov/ne
Advanced Reactors: U.S. Landscape
- Dozens of U.S. companies are working on advanced nuclear projects for a wide array of capabilities to meet the energy needs of the future
- Light water-cooled advanced small modular reactors
- Advanced sodium-, gas-, lead-, molten salt-cooled reactors
- Significant levels of private sector investment
- Motivation for advanced reactor development
- Potential for improved safety and operational capability
- Various options for future commercial, limited-grid and remote applications
- Potential for improved nuclear resource utilization and reduced nuclear waste
- Flexible operation to support the national grid of the future containing many energy-source options 87 of 112 3 energy.gov/ne
Advanced Reactor Demonstration Program
- Established in fiscal year (FY) 2020 budget language ($230 million (M))
- Focuses DOE and non-federal resources on actual construction of real demonstration reactors
- Establishes ambitious timeframe for demonstration reactors - five to seven years from award, including design, licensing, construction and start of operations
- Program also addresses technical risks for less mature designs
- Desired outcomes:
- Support diversity of advanced designs that offer significant improvements to current generation of operational reactors
- Enable a market environment for commercial products that are safe and affordable to both construct and operate in the near- and mid-term
- Stimulate commercial enterprises, including supply chains
- Overall FY21 budget for ARDP activities $250 M 88 of 112 4 energy.gov/ne
ARDP Program Elements
- Advanced Reactor Demonstrations (Demos)
- Cost-shared partnerships with industry (up to 50 percent (%) government, not less than 50% industry) to build two advanced demonstration reactors with significant improvements compared to current generation of operational reactors
- Demos to be constructed and operational in a 5-7 year window after award
- $160 M appropriated for fiscal year (FY) 2020 ($80 M per award)
- $160 M appropriated for FY 2021 ($80 M per award)
- Risk Reduction (RR) for Future Demonstrations
- Cost-shared research and development (R&D) activities with industry (up to 80% government, not less than 20% industry) to address technical risks in advanced reactor designs to support potential future advanced reactor demonstrations 5
- $30 M appropriated for FY 2020 (up to 5 awards)
- $40 M appropriated for FY 2021 (To be distributed among awards based on agreed-upon cost requirements) 89 of 112 5 energy.gov/ne
ARDP Program Elements (cont.)
- National Reactor Innovation Center (NRIC)
- Empower innovators with access to facilities, sites, materials, and expertise to enable demonstration of at least two advanced reactor technologies
- Support advanced reactor regulatory readiness for demonstrations
- Develop enduring demonstration support infrastructure
- Establish methods for efficient coordination among national laboratories Recent Activities:
- Establishing NRIC through planning and engagement with industry, NRC, national laboratories, and other key stakeholders
- Performed gap assessment for demonstration capabilities
- Developing a demonstration resource network, such as experimental facilities, test beds, and demonstration site identification and preparation
- $20 M appropriated for FY 2020; $30 M for FY 2021 90 of 112 6 energy.gov/ne
ARDP Program Elements (cont.)
- Advanced Reactor Regulatory Development
- National laboratory-led R&D to resolve technical challenges with licensing advanced reactors
- Supporting efforts with NRC and industry stakeholders to develop cross-cutting advanced reactor licensing frameworks
- Licensing Modernization Project (LMP)
- Technology-Inclusive Content of Application Project (TICAP)
- Focused R&D to address technology-specific regulatory challenges for NE advanced reactor campaigns
- $15 M appropriated for FY 2020; $15 M for FY 2021
- Advanced Reactor Safeguards
- Applies laboratory R&D to address near term challenges that advanced reactor vendors face in meeting domestic requirements for U.S. builds.
- Project focus areas - Materials Accountancy, Physical Protection, Gen-IV &
IAEA Interface
- $5 M appropriated for FY 2020; $5 M for FY 2021 91 of 112 7 energy.gov/ne
Advanced Reactor Demonstration FOA
- Advanced Reactor Demonstration FOA solicited applications under 3 funding pathways aligned with different technology maturity levels:
- Advanced Reactor Demonstration (Demos) awards
- Cost-shared demonstration of two reactor designs that have potential to be operational in five to seven years following award finalization
- Risk Reduction for Future Demonstration (Risk Reduction) awards
- Support for 2-5 additional, diverse advanced reactor designs that have potential to be operational in ten to twelve years following award finalization
- Advanced Reactor Concepts-20 (ARC-20) awards
- A new solicitation (to be known as ARC-20) for at least 2 new public-private partnerships focused on advancing reactor designs moving toward demonstration phase
- Not formally part of ARDP; funded under separate budget line. Included in ARD FOA to allow developers to select best pathway.
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Advanced Reactor Demonstration and Risk Reduction Pathway Merit Review
- Two sets of reviewers: non-federal subject matter experts (SMEs) and federal merit review panel (MRP).
- Congressional language that established the Advanced Reactor Demonstration Program directed the selection of projects be advised by subject matter experts:
- Electric utility that operates a nuclear power plant
- High-temperature process heat users (e.g., hydrogen production, industrial processing)
- Design, manufacturing and operation of nuclear reactors
- Finance industry with background in nuclear field
- Non-federal SMEs independently reviewed applications and provided individual feedback.
- Federal MRP members individually reviewed applications and then developed consensus recommendations, taking SME input into account.
- Coordinated with NRC on applicant proposed licensing strategies and schedules 93 of 112 Competition and Source Selection Information - Not for Public Release 9 energy.gov/ne
Demonstration Pathway Selected Technologies
- TerraPower LLC - Natrium Reactor
- Sodiumcooled fast reactor that leverages of decades of development, including fuel
- High temperature reactor coupled with thermal energy storage for flexible electricity output
- New metal fuel fabrication facility
- Visit: https://natriumpower.com/
- X-energy - Xe-100 reactor
- High temperature gas-cooled reactor that leverages decades of development and robust fuel form
- Provides flexible electricity output and process heat for a wide range of industrial heat applications
- Commercial scale TRISO fuel fabrication facility
- Visit: https://x-energy.com/ 94 of 112 10 energy.gov/ne
Risk Reduction Pathway Selected Technologies Commercial Target Prime Risk Reduction Project Key Reactor Applicant Deliverables Kairos KP-FHR Type and Fuel KP-FHR - 140 Mwe Kairos Design, construction and operation of thermal spectrum fluoride Power. Hermes reduced-scale test reactor salt-cooled MSR, TRISO LLC (precursor to commercial-scale KP-FHR) annular pebble fuel eVinci - 4.5 MWe heat WEC eVinci Technical risk reduction for moderator Westing- pipe-cooled microreactor, design, wick manufacturing, refueling and house TRISO UCO compact licensing.
HALEU fuel BANR - 50 MWt Maturation of technology, including the BWXT BANR BWXT transportable microreactor development of UN TRISO fuel, to improve HTGR with UN TRISO the commercial viability of BANR SMR-160 - 160 MWe LW-Early stage design, engineering, and Holtec cooled natural circulation Holtec SMR-160 licensing activities for the SMR-160.
PWR Molten Chloride Fast Design, construction and operation of Southern Reactor -180 MWt pool-Molten Chloride Reactor Experiment Company type MSR fast reactor with (MCRE) liquid salt fuel TerraPower MCFR 95 of 112 11 energy.gov/ne
ARC-20 Pathway Selected Technologies Commercial Target Prime ARC-20 Project Key Reactor Applicant Deliverables Type Advanced Conceptual and preliminary ARC-100 100 MWe pool Advanced Reactor Concepts design of a seismically isolated Reactor type sodium-cooled fast advanced sodium-cooled reactor Concepts reactor facility Conceptual design of the GA-GA-EMS 50 MWe EMS 50 MWe FMR, increase General gas-cooled fast TRL on systems and Atomics modular reactor components, develop prelim. cost estimates General Atomics Modular Integrated Gas- Conceptual design for MIGHTR cooled and support for future MIT High Temperature commercialization as a safe and Reactor (MIGHTR) cost-competitive HTGR concept MIT 96 of 112 12 energy.gov/ne
Summary The Advanced Reactor Demonstration Program:
- Supports a diversity of U.S. advanced reactor designs for near-term or mid-term commercial demonstration
- Employs innovative technologies and fuel cycles to improve economic competitiveness, safety, and resiliency of nuclear energy systems
- Ensures nuclear energy continues to serve as a resource capable of meeting the Nation's energy, environmental and energy security goals
- Will require continued coordination with NRC to meet aggressive deployment schedules 97 of 112 13 energy.gov/ne
Questions?
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NRC Review and Endorsement of ASME BPVC Section III, Division 5 -
Update Jordan Hoellman, Project Manager Advanced Reactor Policy Branch Office of Nuclear Reactor Regulation Jeff Poehler, Sr. Materials Engineer Component Integrity Branch Office of Nuclear Regulatory Research 99 of 112
Purpose
- Provide status of NRCs review and endorsement of 2017 ASME BPVC Section III, Division 5, High Temperature Materials
- Provide status of contractor reports supporting NRCs review 100 of 112 2
Background
- NRC Staff is developing two guidance documents related to review/endorsement of ASME Section III-Division 5 and associated code cases.
- NUREG - Technical Review of the 2017 Edition of ASME Section III, Division 5, High Temperature Reactors
- Document the staffs technical evaluation of the 2017 Edition of Section III, Division 5 and associated Code Cases for acceptability and endorsement.
- Regulatory Guide (RG) - Acceptability of ASME Section III, Division 5, High Temperature Reactors (DG-1380)
- Describes an approach that is acceptable to the NRC staff to meet regulatory requirements for components constructed in elevated temperature environments that are subject to time-dependent material properties and failure modes.
- Will contain any conditions arising from staffs review.
- The regulatory guide will update the guidance of RG 1.87.
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Overview
- Staff is finalizing the draft NUREG and draft regulatory guide.
- Conditions are likely in the areas of general requirements, mechanical design, metallic materials properties, and graphite design and materials.
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Status of Contractor Reports
- See NRCs Advanced Reactor Public Website: https://www.nrc.gov/reactors/new-reactors/advanced.html#endorev
- All reports are final and publicly available (except ANL)
- PNNL - (ML20269A145)
- ORNL - (ML20269A125)
- NUMARK/EMC2 -
o Metallic Appendices HBB-T, HBB-II, HCB-I, HCB-II, and HCB-III (ML20349A003) o Graphite Materials (ML20358A145) o Code Cases N-861 and N-862 (ML20349A002)
- ANL - ANL input is being finalized.
o Input provides historical context and perspective on materials properties.
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Contractor Assignments
- Elevated Temperature Metallic Components
- Design, Fabrication, Examination, Testing (HBB; HCB; HGB-3000, -4000, -5000, -6000),
- Rules for Strain, Deformation, and Fatigue Limits (Mandatory Appendix HGB-I)
- Rules for Construction of Core Support Structures Without Explicit Consideration of Creep and Stress-Rupture (Mandatory Appendix HGB-II)
- Rules for Buckling and Instability (Mandatory Appendix HGB-III)
- Rules for Time-Temperature Limits (Mandatory Appendix HGB-IV)
- Materials (HBB; HCB; & HGB-2000)
- Tables and Figures (Mandatory Appendix HBB-I)
- Guidelines for Restricted Material Specifications (Non-Mandatory Appendix HBB-U) 104 of 112 6
Contractor Assignments
- Elevated Temperature Metallic Components (continued)
- NUMARK/EMC2
- Rules for use of SA-533 Type B (Mandatory Appendix HBB-II)
- Rules for Strain, Deformation, and Fatigue Limits (Nonmandatory Appendix HBB-T)
- Rules for Stress Range Reduction Factors (Mandatory Appendix HCB-I)
- Rules for Allowable Stress Values for Class B Components (Mandatory Appendix HCB-II)
- Rules for Time-Temperature Limits (Mandatory Appendix HCB-III)
- Graphite
- NRC Staff (General Requirements)
- NUMARK/EMC2 (Technical Requirements)
- Code Cases N-861 and N-862
- NUMARK/EMC2 (All aspects) 105 of 112 7
General Requirements
- HAA & HAB (General Requirements) will contain several conditions to ensure consistency with the 2017 Edition of NCA, Division 1 and address oversights that were corrected in the 2019 Edition of Division 5 106 of 112 8
Mechanical Design
- Staff has reviewed portions of PNNL and NUMARK reports related to the design of mechanical SSCs, as well as related Division 5 Articles.
- The staff is considering some conditions and recommendations on design, some of which are already included in 10CFR50.55a and in Section III Mandatory Appendix XII, and some from RG 1.87 Rev. 1 107 of 112 9
Metallic Materials
- Independent analysis of materials allowable stresses and other materials properties by ORNL and NUMARK implied some Division 5 values are nonconservative.
- NRC staff is considering these findings in a holistic manner, including how these properties are used, inherent conservatism of the Division 5 design rules, and historical context.
- Some conditions on allowable stresses are likely for reasonable assurance of safe designs.
- Input from ANL provides historical context and perspective on materials properties.
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Graphite Materials and Design
- Numark Associates Inc. provided a technical assessment of Subsection HH, Class A Nonmetallic Core Support Structures, Subpart A, Graphite Materials.
- Staff has completed the review of the above report and all applicable sections of ASME Section III, Division 5 and obtained clarifications and feedback from NRC contractors (Numark and INL) in order to come up with the conclusions identified in the NUREG.
- The staff's deliberations and independent review of the code requirements will take into account the holistic design of graphite core support structures.
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INL Expert Assistance
- INL is providing on-call technical expertise related to NRCs endorsement of ASME BPVC Section III, Division 5.
- Providing the review team with the technical basis and historical perspective on ASME BPVC Section III, Division 5.
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Current Status - Next Steps
- The NRC has shared NRC contractor comments with the ASME Code committees
- At the current time, we have not found any issues that would be show stoppers
- Incorporate SSC classification guidance for high temperature reactors (similar to RG 1.26) into draft RG 111 of 112 13
Future Meeting Planning 2021 Tentative Schedule for Periodic Stakeholder Meetings January 26, 2021 (Part 53 - Options for Fusion)
February 2, 2021 (ACRS - Advanced Reactor Fuel Qualification)
February 4, 2021 (Part 53)
February 18, 2021 (ACRS - Part 53)
February 25, 2021 (Periodic (AM), TICAP/ARCAP (PM))
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