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July 26, 2018 Public Stakeholder Meeting on Possible Regulatory Process Improvements for Non-Light Water Reactors, Slide Presentations
	ML18213A151
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Issue date:	07/26/2018
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Presentations for July 26, 2018 Public Meeting Regulatory Improvements for Advanced Reactors In order of discussion, the meeting included the following topics and presentations

1) NRC Slides Opening / Outline Update on NRC Activities Licensing Modernization (see #2 for industry slides)

Future Stakeholder Meetings

2) Licensing Modernization

3) Molten Salt Reactor Technology Working Group (FLIBE)

4) INL/Framatome/ANL Natural Convection Shutdown Heat Removal

Public Meeting on Possible Regulatory Process Improvements for Advanced Reactor Designs July 26, 2018 1

Telephone Bridge (888) 793-9929 Passcode: 7231346

Public Meeting

Telephone Bridge (888) 793-9929 Passcode: 7231346

Opportunities for public comments and questions at designated times 2

Introductions

Update on NRC Activities Licensing Modernization Project Technology Working Groups - MSR Prioritization Considering O&M Natural Convection Shutdown Heat Removal Policy Issues, Future Meetings, Public Discussion 3

Outline

4 Implementation Action Plans Strategy 1 Knowledge, Skills and Capability Strategy 2 Computer Codes

& Review Tools Strategy 3 Flexible Review Processes Strategy 5 Policy and Key Technical Issues Strategy 6 Communication Strategy 4 Consensus Codes and Standards ONRL Molten Salt Reactor Training Knowledge Management Competency Modeling Regulatory Roadmap

Prototype Guidance

Non-LWR Design Criteria

ASME BPVC Section III Division 5

ANS Standards 20.1, 20.2 30.2, 54.1 Non-LWR PRA Standard Siting near densely populated areas Insurance and Liability Consequence Based Security NRC DOE Workshops

Periodic Stakeholder Meetings NRC DOE GAIN MOU Identification &

Assessment of Available Codes International Coordination Licensing Modernization Project Functional Containment EP for SMRs and ONTs Environmental Reviews Potential First Movers Micro-Reactors

Reactor Kinetics and Criticality Fuel Performance Thermal Hydraulics Severe Accident Phenomena Offsite Consequences Materials Research 5

Strategy 2 - RES Contracts

NRC Staff Technology Training Fuel Qualification o TRISO (limited scope topical) o Metallic (legacy data) o MSRs Policy Resolution, Guidance Development Environmental Reviews RTR Guidance (MSR)

ASME Section III Division 5 Licensing Micro Reactors 6

NRO Contracts

7 NRO Contracts - Continued

Fuel Cycle

- Fuel facilities

- High level waste

Security

MC&A

Technology specific barrier/consequence estimates

8 Break Meeting/Webinar will begin shortly Telephone Bridge (888) 793-9929 Passcode: 7231346

Southern Company Presentation 9

Licensing Modernization

Public Meeting - August 21, 2018 Revision to LMP Guidance (NEI 18-04) o Resolution of Questions/Comments DG 1353 o Endorsing LMP Guidance o Informing Content of Applications September 30, 2018 - Draft Material to ACRS o October 30, 2018: ACRS Subcommittee o December 6-8, 2018: ACRS Full Committee o December 21, 2018: Issue DG 1353 o Early 2019: Commission paper 10 Licensing Modernization

11 Licensing Modernization Licensing Basis Events SSC Classification Defense in Depth SSCs Including Radionuclide Barriers Safety Related (SR)

SSCs Non-Safety Related SSCs with Special Treatment (NSRST)

Non-safety Related SSCs with No Special Treatment (NST)

SSCs selected for required safety functions to mitigate DBEs within F-C Target*

SSCs performing risk significant functions SSCs performing functions required for defense-in-depth SSCs performing non-safety significant functions SSCs selected for required safety functions to prevent high consequence BDBEs from entering DBE region beyond F-C target Risk Significant SSCs Non-Risk Significant SSCs

SR SSCs are relied on during DBAs to meet 10 CFR 50.34 dose limits using conservative assumptions Note that DBAs (Chapter 15) derived from DBEs

12 DG-1353 / SECY Paper Support: 7, 8, 9 Key: 4, 5, 6 Deterministic: 15 PRA: 19 Programs:

12, 13, 14, 16, 17, 18 Site/Design: 2, 3 Other: 11 Assessment: 15, 19 DID: 20*

Power Conv 10 LMP focus Informing Scope and Level of Detail in Applications

13 Related Commission Paper LBE categories - AOO, DBE, BDBE and DBAs F/C Target Figure - with demarcations between event categories, cutoff Aggregate safety goals SSC Classification scheme Defense in Depth assessments Scope and Depth of Applications o Focus on Fundamental Safety Functions o Potential radiological consequences o Mechanistic source term o Risk-Informed approach for key systems and support systems o Performance-based approach

Molten Salt Reactors FLIBE Presentation 14 Technology Working Groups

15 Lunch Meeting/Webinar will begin at 1:00pm Telephone Bridge (888) 793-9929 Passcode: 7231346

NEI Discussion 16 Prioritization - O&M

17 Break Meeting/Webinar will begin shortly Telephone Bridge (888) 793-9929 Passcode: 7231346

INL ANL Framatome 18 Natural Convection Shutdown Cooling

19 Future Stakeholder Meetings Topics ?

Sept 13 TWG - Fast Reactors, Metallic Fuel Prioritization of Issues Considering Capital Costs Seismic Isolators Licensing Modernization/DG 1353 Oct 25 TWG - HTGRs Licensing Modernization/DG 1353 Dec 13

20 ACRS Schedule (tentative)

Date Committee Topic June 19 Sub RIPB Guidance Aug 22 Sub EP Rulemaking Oct Full EP Rulemaking Oct 30 Sub RIPB Guidance Dec 6 Full RIPB Guidance 2019

??

21 Public Comments / Questions

Licensing Modernization Project (LMP) Guidance Document Update Jason Redd, PE July 26, 2018

2 LMP Guidance Document Introduction

The LMP Guidance Document represents a framework for the efficient licensing of advanced non-light water reactors (non-LWRs).

It is the result of the LMP led by Southern Company and cost-shared by the U.S.

Department of Energy (DOE).

The LMP prepared this document for establishing licensing technical requirements to facilitate risk-informed and performance-based (RIPB) design and licensing of advanced non-LWRs.

Such a framework acknowledges enhancements in safety achievable with advanced designs and reflects current states of knowledge regarding safety and design innovation, creating an opportunity for reduced regulatory complexity with increased levels of safety.

3 LMP Guidance Document Recent Activities

April - First table top demonstration of the LMP RIPB processes on a current advanced non-LWR design completed. Lessons learned and best practices identified during this demonstration were incorporated into the LMP Guidance Document.

June 5 NRC Public Workshop discussing LMP Guidance Document (Working Draft M). [ML18150A344 - LMP Guidance Document][ML18177A462 - meeting summary]

June 18 - LMP members delivered a training opportunity on the LMP RIPB process for NRC Staff at the White Flint offices.

The Staff posed many excellent questions during this training opportunity and provided constructive feedback which is being addressed in ongoing updates to the LMP Guidance Document.

4 LMP Guidance Document Recent Activities

June 19 - The LMP Guidance Document (Working Draft M) was reviewed and discussed by the Advisory Committee on Reactor Safeguards (ACRS) Future Plants Subcommittee.

As with the Staff, the ACRS FPS engaged in a robust discussion of the LMP Guidance Document and provided feedback to both the LMP team and the NRO Staff. Likewise, this feedback is being addressed in ongoing updates to the LMP Guidance Document.

5 LMP Guidance Document Upcoming Meetings and Milestones

August 21 - NRC Public Workshop on LMP Guidance Document. Agenda focused on resolution of June NRC and ACRS comments.

September 13 - NRC advanced reactors stakeholder meeting. LMP team to provide update on LMP progress to date.

October 30 - ACRS Future Plants Subcommittee meeting to review and discuss the working draft of the LMP Guidance Document, draft NRC SECY, and draft NRC Regulatory Guide addressing the LMP Guidance Document.

December 6 Full ACRS meeting to review and discuss the working draft of the LMP Guidance Document, draft NRC SECY, and draft NRC Regulatory Guide addressing the LMP Guidance Document.

6 LMP Guidance Document Upcoming Opportunities for Industry and Public Participation

August 21 - NRC Public Workshop on LMP Guidance Document. Agenda focused on resolutions of June NRC and ACRS comments.

Proposed comment resolutions will be shared with NEI ARRTF in advance; a full revision of the LMP Guidance Document will not be performed for this workshop.

September 9 - Updated LMP Guidance Document working draft incorporating NRC and ACRS FPS feedback distributed to NEI ARRTF for two week review and comment cycle supporting September 28 submittal of updated document to ACRS FPS Chair for review.

TBD - By 2Q19 we expect between four and six designs to have exercised the LMP RIPB processes on their designs to obtain potential insights. The LMP team is interested in demonstrating the LMP RIPB processes with additional vendors.

Anytime - The LMP team always welcomes questions, comments, and feedback.

Please contact me at jpredd@southernco.com or 205-992-6435.

Questions?

Molten-Salt Reactor Technology Matthew Lish Flibe Energy Nuclear Regulatory Commission July 26, 2018

Coolant Choices for a Nuclear Reactor atmospheric high-pressure pressure operation operation moderate temperature (250-450C) high temperature (650-900C)

Metal Water Salt Gas

Molten Salt Reactor Design Space Thermal Fast Uranium Thorium LFTR TMSR-LF SCIFR ThorCon IMSR WAMSR MSFR MCFR Moltex Elysium Neutron Spectrum Fuel Type

Gen-4 Molten Salt Reactor Concept

The MSRE successfully operated for over 20,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, from 1965-1969.

Oxygen is very electronegative and forms strong bonds with metals, however "uorine, and only "uorine, is even more electronegative.

Free energy differences (oxides/chlorides) at 1000 K Ba Ce Cs Gd La Nd Pr Pu Sr Th U

Zr 150 100 50 0

50 Free Energy Differences Alkaline "ssion products are stable in chloride salt, and will not volatilize if introduced to air. Actinides may form oxides in air, but will not volatilize.

Free energy differences (oxides/"uorides) at 1000 K Ba Ce Cs Gd La Nd Pr Pu Sr Th U

Zr 200 150 100 50 0

Free Energy Differences In "uoride form all actinides and alkaline "ssion products, most notably cesium and strontium, remain in "uoride salt form in the presence of air, do not form volatile species. In molten salts, the "rst barrier to "ssion product release is the chemical form of the fuel salt, rather than the mechanical integrity of the fuel pin.

MSR Material Compatibility Through proper material choices, molten-salt reactors can operate in a state of fundamental chemical equilibrium. This was demonstrated by the MSRE with FLiBe salt, graphite, and Hastelloy-N alloy. This is very different than the environment inside PWRs.

Conclusions MSRs feature circulating fuel dissolved in stable form in the coolant.

Molten salts chemically bind most "ssion products, but do not retain noble gas "ssion products at all, thus the standard operating approach for noble gases should bound potential accidents.

Properly chosen materials operate in chemical equilibrium with the coolant without stored energy terms or driving forces for radionuclide release.

Off-gas treatment and sequestration is of paramount importance.

Regulatory Framework Development Passive Heat Removal Jim Kinsey Idaho National Laboratory July 26, 2018

=

Background===

Reactor technologies and associated designs address a set of fundamental safety functions

The LWR-based operating fleet generally relies on a group of interrelated active systems for the heat removal function, as reflected in the GDCs:

- Residual heat removal

- Emergency core cooling

- Containment heat removal

- Cooling water systems Fundamental Safety Functions Reactivity Control Heat Removal Radionuclide Retention

NRC Advanced Reactor Policy (2008 - Excerpts)

Commission policy encourages:

Use of inherent or passive means of reactor shutdown and heat removal

Longer time constants

Simplified safety systems which reduce required operator actions

Minimizing the potential for severe accidents and their consequences

Safety-system independence from balance of plant

Incorporation of defense-in-depth philosophy by maintaining multiple barriers against radiation release and by reducing the potential for consequences of severe accidents

Using existing technology or technology that can be satisfactorily established by commitment to a suitable technology development program 3

Regulatory Framework - Areas of Focus The Regulatory Framework consists of four key parts that are the areas of focus:

What are the rules?

1)

Establish Commission policy on advanced non-LWR topics 2)

Develop adaptations and updates to NRCs existing LWR-based rules and regulatory guidance

What are the technology-specific technical requirements for implementing those rules?

3)

Define requirements based on testing and R&D (fuel performance, high temperature materials, heat removal, etc.)

What is the process for predictable and timely NRC review of a license application?

4)

Establish method for incremental and frequent NRC feedback on specific technology development and early design efforts (staged licensing review)

Passive Heat Removal System Testing

NRCs Non-Light Water Reactor Near Term Implementation Action Plans highlight the need to establish Decision Criteria as a key part of the framework

- Criteria must be established for non-LWRs that allow the NRC to reach a safety, security, and environmental finding for a particular technology and design.

Todays presentation material will summarize DOE Advanced Reactor Technology Program testing underway to gather representative performance data to inform passive heat removal system design and modeling efforts

- Core heat removal path to Ultimate Heat Sink

- Passive system doesnt rely on active components

- Informs reactor developers, future license applicants, and NRC 5

Support of Regulatory Framework Development Resolve Commission Policy Issues Staged NRC Reviews Establish Licensing Technical Requirements Pre-Application Efforts Application Review Risk Adapt LWR-based Regulatory Requirements

7

Matthew Miller Regulatory Process Improvements for Advanced Reactor Designs NEI - Washington, DC.

July 26, 2018 Reactor Cavity Cooling System

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All rights reserved p.2 Reactor Cavity Cooling System - M. Miller - July 26, 2018 Topics Overall SC-HTGR Description SC-HTGR RCCS Description SC-HTGR RCCS Pre-Conceptual Performance Importance of RCCS R&D Conclusions

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All rights reserved p.3 Reactor Cavity Cooling System - M. Miller - July 26, 2018 Overall SC-HTGR Description Key Features Prismatic block annular core Conventional steam cycle Modular reactors Inherent safety characteristics Passive decay heat removal Large thermal inertia Negative reactivity feedback Minimal reliance on active safety systems Sized to minimize steam production cost (625 MWt)

Fully embedded reactor building Reactor Circulator Steam Generator

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All rights reserved p.4 Reactor Cavity Cooling System - M. Miller - July 26, 2018 Permanent Reflector Metallic Core Barrel Control Rods Reserve Shutdown Channels Replaceable Reflector Fuel Columns Overall SC-HTGR Description Annular Core Arrangement

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All rights reserved p.5 Reactor Cavity Cooling System - M. Miller - July 26, 2018 Overall SC-HTGR Description Passive Heat Removal Considerations Passive cooling is a key characteristic of modular HTGRs Loss of forced circulation Loss of all coolant No power or system actuation required Passive cooling capability is inherently determined by fundamental HTGR design characteristics Reactor geometry Reactor materials Reactor power level Reactor operating temperature Passive reactor cavity cooling These fundamental characteristics must be established early in the design process (before detailed safety analyses are available)

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All rights reserved p.6 Reactor Cavity Cooling System - M. Miller - July 26, 2018 Overall SC-HTGR Description SC-HTGR Passive Cooling Design SC-HTGR is in Conceptual Design phase Scoping evaluations of passive cooling design important at this design stage Depressurized Loss of Forced Circulation (DLOFC) is used as representative limiting event (aka Depressurized Conduction Cooldown or DCC)

Maximum fuel temperature Maximum vessel temperature Scoping criteria established to screen results Results (fuel temperatures) depend primarily on reactor configuration, power level, and initial conditions RCCS important to maintaining vessel and concrete temperatures

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All rights reserved p.7 Reactor Cavity Cooling System - M. Miller - July 26, 2018 Overall SC-HTGR Description Reactor Cavity Cooling System Design Considerations Modular HTGR designers have considered a variety of RCCS configurations Air-cooled Water-cooled (various different concepts)

Natural circulation Active cooling Various tradeoffs must be addressed in selecting configuration Functionality (normal operation and accidents)

Robustness Passive cooling duration (unlimited or n days)

Physical interfaces External hazards Constructability and cost Framatome SC-HTGR utilizes a water cooled RCCS design.

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All rights reserved p.8 Reactor Cavity Cooling System - M. Miller - July 26, 2018 Topics Overall SC-HTGR description SC-HTGR RCCS Description SC-HTGR RCCS Pre-Conceptual Performance Importance of RCCS R&D Conclusions

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All rights reserved p.9 Reactor Cavity Cooling System - M. Miller - July 26, 2018 SC-HTGR RCCS Description SC-HTGR RCCS System Functions Safety Functional Requirements Maintain reactor pressure vessel mean wall temperatures within ASME limits during all DBE Maintain reactor cavity concrete temperatures within acceptable limits during all DBE Normal Operation Functional Requirements Maintain acceptable reactor pressure vessel mean wall temperatures limits during power operation, startup and shutdown, and AOOs Maintain acceptable reactor cavity concrete temperatures during power operation, startup and shutdown, and AOOs Cooling vessel supports at building interface Local thermal protection strategy being developed as design progresses Vessel supports are not at hottest location RCCS role for supports still to be defined

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Reactor Cavity Cooling System Safety-related heat removal system Passive cooling of vessel and surrounding cavity (operates continuously)

Active cooling of water storage tank during normal operation (non-safety)

Initial RCCS analysis and design focused on cavity natural circulation loop Building integration Component sizing Performance evaluation Water Storage Tank Natural Convection Flow Forced flow Reactor Vessel Red shows safety-related cooling loop.

Black shows non-safety related.

One of two redundant loops shown.

Cooling Panel

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All rights reserved p.11 Reactor Cavity Cooling System - M. Miller - July 26, 2018 SC-HTGR RCCS Description SC-HTGR RCCS Design Elements RCCS includes redundant and separate loops RCCS panel collects heat and transfers it to water loop (panel cross section shown)

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Reactor Silo (below grade)

Refueling operating floor (grade level)

Reactor Steam Generators

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Natural circulation in cavity loop Active cooling of water tanks Active Accident System Operation Two loop operation Variable heat load (~2.1 MWt max.)

Natural circulation in cavity loop Active cooling of water tanks Passive Accident System Operation Two loop operation Variable heat load (~2.1 MWt max.)

Natural circulation in cavity loop Evaporation from water tanks DBA System Operation Single loop operation Variable heat load (~2.1 MWt max.)

Natural circulation in cavity loop Evaporation from water tanks

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All rights reserved p.14 Reactor Cavity Cooling System - M. Miller - July 26, 2018 SC-HTGR RCCS Description Key RCCS Technical Requirements Passive cooling during accidents Water heat sink cooling Active secondary cooling during normal operation Evaporation cooling during accidents (assume active cooling and power supply not available)

No change in component state for accident cooling Cavity cooling natural circulation for normal operation and accidents Redundant independent loops Required water inventory refill interval Single loop operation: 7 days Two loop operation : 14 days Continuous performance monitoring Must accommodate reactor building structural interfaces

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All rights reserved p.15 Reactor Cavity Cooling System - M. Miller - July 26, 2018 Topics Overall SC-HTGR description SC-HTGR RCCS Description SC-HTGR RCCS Pre-Conceptual Performance Importance of RCCS R&D Conclusions

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Normal operation Subcooled natural circulation Steady system temperatures (controlled by active tank cooling)

Initial heatup conditions Subcooled natural circulation, but Gradually increasing loop temperatures

Approaching saturation conditions Downcomer and lower riser subcooled Saturation reached in heated riser panels Boiling occurs in hot part of riser Very low quality two phase natural circulation

Saturation conditions Tank at saturation condition Downcomer single phase flow Low quality two phase natural circulation

Tank empty Circulation blocked (stagnant loop)

Downcomer single phase Pool boiling in hot leg Water gradually boils out of panels

Refill water tank (stagnant loop)

Water goes down downcomer, collects in bottom of loop, rises in hot leg riser and panel inlet Flashing occurs when water reaches heated sections Depending on geometry, may have to purge trapped gases

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All rights reserved p.17 Reactor Cavity Cooling System - M. Miller - July 26, 2018 SC-HTGR RCCS Pre-Conceptual Performance RCCS Operating Modes and TD States Thermodynamic State Normal Operation Initial Heatup Approach Saturation Conditions Saturation Conditions Tank Empty Refill Empty Loop Operating Mode Normal Plant Operation Active Accident System Operation Passive Accident System Operation DBA System Operation System Dryout and Long-Term Recovery (outside design envelope)

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All rights reserved p.18 Reactor Cavity Cooling System - M. Miller - July 26, 2018 SC-HTGR RCCS Pre-Conceptual Performance Preliminary Performance Characteristics For subcooled operation Cold leg P is ~80% of total P System T is ~10-20°C For saturated operation Cold leg P is less than 50% of total P System return quality is < 1% (but still significant void fraction)

Stability not expected to be concern for overheating/burnout Dynamic structural loading must be addressed Panel performance (conduction heat transfer)

Large temperature variations for single loop operation (especially w/ SS)

RPV cooling not particularly sensitive to panel temperature variations Thermal stresses in panel are detailed design challenge to be addressed Impact of large panel temperature variations on concrete surfaces and necessary thermal protection still to be evaluated

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All rights reserved p.19 Reactor Cavity Cooling System - M. Miller - July 26, 2018 SC-HTGR RCCS Pre-Conceptual Performance Nominal DLOFC Results 200 300 400 500 600 700 800 900 1000 1100 1200 1300 1400 0

100 200 300 400 500 Temperature (C)

Time (hr)

Max. Fuel Avg. Fuel Max. Core Barrel Max. RPV

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100 200 300 400 500 RCCS Heat Load (MWt)

Time (hr)

Conservative RPV Case Conservative Fuel Case Nominal Case

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Scoping Criterion Fuel peak temperature 1332°C 1635°C 1650°C Core Barrel peak temperature 720°C 784°C 800°C RPV peak temperature 440°C 482°C 538°C Duration RPV above 371°C 305 hr 446 hr 750 hr Duration RPV above 427°C 96 hr 233 hr 250 hr All scoping criteria satisfied Safety functions are not impaired Components remain within design limits Meeting these criteria provides confidence that final design will be successful

Different conservative case for each Figure of Merit

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All rights reserved p.22 Reactor Cavity Cooling System - M. Miller - July 26, 2018 Topics Overall SC-HTGR description SC-HTGR RCCS Description SC-HTGR RCCS Pre-Conceptual Performance Importance of RCCS R&D Conclusions

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All rights reserved p.23 Reactor Cavity Cooling System - M. Miller - July 26, 2018 Importance of RCCS R&D Need for RCCS R&D Provide data to qualify RCCS analysis tools Provide data to address specific design issues Provide confidence in overall system concept Designer perspective:

Basic performance of buoyancy-driven natural circulation loop is well understood Basic performance of radiation heat transfer from RPV to RCCS is well understood Main areas of interest are with specific details Impact of specific design details on system performance Dynamics associated with two phase operating modes

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All rights reserved p.24 Reactor Cavity Cooling System - M. Miller - July 26, 2018 Importance of RCCS R&D Points of Interest Impact of riser panel tube dimensions on system performance and dynamic stability Need for inlet orificing (at riser tube inlets from bottom header)

Dynamic performance characteristics Impact of system piping details due to building interface issues, etc.

Impact of panel riser tube discontinuities RCCS Designer Input Report 12-9239789-000

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All rights reserved p.25 Reactor Cavity Cooling System - M. Miller - July 26, 2018 Topics Overall SC-HTGR description SC-HTGR RCCS Description SC-HTGR RCCS Pre-Conceptual Performance Importance of RCCS R&D Conclusions

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All rights reserved p.26 Reactor Cavity Cooling System - M. Miller - July 26, 2018 Conclusions SC-HTGR being developed for a variety of process heat, electricity, and cogeneration markets Reactor Cavity Cooling System (RCCS) is only safety-related heat removal system for SC-HTGR Preliminary analytical assessments indicate RCCS maintains acceptable system temperatures Reactor cavity wall (normal operation and accident)

Reactor vessel (accident)

Basic behavior of natural circulation system and radiation heat transfer well understood RCCS R&D needed to Provide data to qualify design and safety analysis evaluation models Provide data to address specific system characteristics Provide confirmation of overall system concept

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All rights reserved p.28 Reactor Cavity Cooling System - M. Miller - July 26, 2018 Wrap-up Industry is working with the national labs to develop testing and the associated test plans to support design validation Industry needs the data developed in the national labs to support future license applications and submittals:

Demonstrate basic concept feasibility Provide insights on detailed design issues for RCCS designers Generate data required to validate general computational methods for RCCS analysis Current data gathering and proposed test plans are expected to meet the necessary quality requirements specified by industry standards and the regulator

Natural convection Shutdown heat removal Test Facility (NSTF) Overview Darius D. Lisowski Nuclear Science & Engineering Division - Argonne National Laboratory presented at:

Nuclear Regulatory Commission July 26th 2018 Washington, DC. USA.

Introduction

GenIV initiative defines 8 technological goals, of which 3 are safety related:

S&R 1 - System operations will excel in safety and reliability S&R 2 - Very low likelihood and degree of reactor core damage S&R 3 - Eliminate the need for offsite emergency response

The reactor cavity cooling system (RCCS) has emerged as a leading concept for meeting these goals Possibility to provide simple and fully passive means of decay heat removal Offers a high level of performance with relative simplicity in design Has been under consideration since 1950s

Multi-institutional effort has brought together federal, industry, national laboratories, universities, and countries.

NEI/NRC, July 2018 Argonne National Laboratory 2

NSTF at Argonne (legacy)

Original NSTF built to provide confirmatory data for the GE PRISM RVACS design

Successfully operated through the late 1980s NEI/NRC, July 2018 Argonne National Laboratory 3

NSTF at Argonne (legacy)

NEI/NRC, July 2018 Argonne National Laboratory 4

Beginning in 2010, the aging facility was revisited

Several design aspects were re-used, however focus shifted to include features of newer high temperature gas-cooled reactors

Many components were updated to latest technologies

NSTF at Argonne (present)

The Natural Convection Shutdown Heat Removal Test Facility (NSTF) was initiated in FY2010 in support of DOE programs NGNP, SMR, and now ART

- Program is compliant to Nuclear Quality Assurance (NQA)-1 2008/2009a

The top-level objectives of the NSTF program are:

1. examine passive safety features for future nuclear reactors

2. provide a user facility to explore alternative concepts

3. generate benchmark data for code V&V

Concurrent collaborations for a broader scope Experimental facilities at multiple scales (1/2, 1/4, etc.) for both air and water designs Complimenting CFD modeling and 1D systems level analysis Collaborating towards the development of a central data bank for the RCCS concept NEI/NRC, July 2018 Argonne National Laboratory 5

NSTF Quality Assurance

Regular audits, or assessments, maintain compliance to NQA-1 Following requirements of ASME NQA-1 2008 with 2009 addendum Small team of dedicated individuals with strong management support Primary purpose is generating and packaging high-quality data

Audit frequency Management assessments are conducted by Argonne leadership every 3 - 9 months Internal audits by NQA-1/ASQ certified staff every 12 - 18 months External audits by NQA-1 certified consultants every 18 - 24 months or after major programmatic changes

Compliance status All required ASTM-NQA-1-2008/1a-2009 criteria are addressed and compliant. The overall effectiveness rating of the ANL NTSF Program is Effective. - ASMT 2018-022

Program will maintain NQA-1 compliance through entire active program period NEI/NRC, July 2018 Argonne National Laboratory 6

NSTF Project Documentation

We document all aspects of the project and engineering details of our facility 80+ documents on programmatic structure, technical specifications, procurement reports, etc.

300+ engineering drawings of facility design (machine shop delivery)

Published report on scaling studies and preparation tasks RCCS Studies and NSTF Preparation Air-Cooled Option - ANL-GenIV-142 (2010)

Progress Report on Water Conversion of the NSTF - ANL-ART-69 (2016)

Compiled technical document outlining test matrix for air & water installations NSTF Data Test Matrix and Operating Parameters - ANL-NSTF-000000-TECH-010-R1 (2014, 2015)

Water-based NSTF Data Quality Testing Objectives - ANL-NSTF-000000-TECH-021-R (2017)

Published detailed design report that provides key dimensions of significant features and components of NSTF Design Report for the 1/2 Scale Air-Cooled RCCS Tests in the NSTF - ANL-SMR-8 (2014)

Water NSTF Design, Instrumentation, and Test Planning - ANL-ART-98 (2017)

Active contributions to scientific community Regular attendance and publication in conferences, journal submissions in-review NEI/NRC, July 2018 Argonne National Laboratory 7

High-Level Status of NSTF Program NEI/NRC, July 2018 Argonne National Laboratory 8

Constructed and assembly of air NSTF Preparation and scaling studies Air based test campaign Design and fabrication of air NSTF New construction begins in Bldg. 308 2010 Air disassembly Water based test campaign Construction and assembly of water NSTF Shakedown and benchmark activities Data quality testing on water NSTF 2019+

Air testing conclusion 2016 Shakedown testing on air NSTF 2013 Disassembly of legacy NSTF 2008 Program initiated 2005 New water assembly 2017 - 2018 Facility checkout

NEI/NRC, July 2018 Argonne National Laboratory 9

(Air) Facility Overview F. Chimney ductwork E. Outlet plenum D. Riser ducts (7.5-m)

C. Heated cavity B. Inlet plenum A. Inlet downcomer

(Air) Facility Overview NEI/NRC, July 2018 Argonne National Laboratory 10 Fan Loft Heated Sections (22 ft.)

Inlet Plenum Exit Plenum Exhaust thru. roof

Matrix Testing Procedures

All matrix tests are performed with strict procedures and are documented in full Test procedure (20+ pages)

Engineering drawings of all instrumentation positions Channel listing for all instruments (NIST calibrated) into data acquisition Software configuration listing Archived computer software (e.g. LabVIEW.vi)

Full data sets saved in raw format (e.g. original voltage signals for flow instruments)

Facility and instrument check outs are performed prior and after each test, verifying working measurements and physical connections

If a completed test meets the stated test objective, it is suggested for classification as Type-A data and is followed by a Preliminary test acceptance report (PTAR)

Those tests that do not meet objective may be classified as Trending NEI/NRC, July 2018 Argonne National Laboratory 11

Completed Air Testing Parameters

1. Shakedown/Calibration/Isothermal Characterization

2. Baseline testing (QR = 1, T = 1)

3. Scaling verification Integral power variation Reduced physical scale

4. Heated profile shaping

5. GA-MHTGR accident scenario Full time history of decay power profile

6. Performance testing Single chimney configuration Forced flow operation Blocked riser channels (incrementally block up to 6 out of 12 ducts)

Adjacent chimney roles (N. vertical stack inlet, S. vertical stack outlet)

7. Repeatability / Weather Repeat tests performed at baseline, GA-MHTGR accident scenario Repeat tests performed in unfavorable or varied weather conditions Regular repeats of baseline case NEI/NRC, July 2018 Argonne National Laboratory 12

GA-MHTGR Accident Scenario NEI/NRC, July 2018 Argonne National Laboratory 13 Preliminary Safety Information Document for the Standard MHTGR, HTGR-86-024, Vol. 1, Amendment 13, U.S. Department of Energy, (1992)

GA-MHTGR Accident Scenario NEI/NRC, July 2018 Argonne National Laboratory 14

GA-MHTGR Weather Influences NEI/NRC, July 2018 Argonne National Laboratory 15

Influences of Wind NEI/NRC, July 2018 Argonne National Laboratory 16

Summary of Accepted Air-Based Test Runs NEI/NRC, July 2018 Argonne National Laboratory 17

Air-based Program Summary

Air-based testing program officially concluded on July 5th 2016 Final modeling report documented in ANL-ART-46 (M2AT-16AN1702078)

Final project report documented in ANL-ART-47 (M2AT-16AN1702077)

Formal internal audit for all 18 elements of NQA-1 2008 June 29th 2016

All program requirements were completed High level program objectives drafted in 2005, prior to facility design and assembly Experimental objectives drafted in 2013, prior to testing campaign Items identified during early 2016 data review meeting, prior to testing conclusion

Attendees included the DOE, NRC, INL, AREVA, GA, and US Universities

Stenographer hired and transcribed full meeting minutes

Program accomplishments 33-month testing campaign duration 2,250 active hours of heating 27 conducted tests (16 accepted)

Multiple baseline repeats, GA-MHTGR accident scenario, blocked risers, power variations, azimuthal and cosine skew, adjacent chimney roles, meteorological variations, I-NERI test series 24 publications since inception (numbered reports, journals, and conference)

NEI/NRC, July 2018 Argonne National Laboratory 18

Water based transformation & Design study

Water-cooled NSTF is based on concept design for Framatomes water based RCCS DOE sponsored HTGR Technology Economic/Business Analysis and Trade Studies RCCS team performed scaling studies, geometric simulations, thermal and stress calculations, tank depletion time estimates, steam quality/flow rate determinations, etc.

Close collaboration with Frametome, whose RCCS included as part of their 625 MWt SC-HTGR served as the primary design basis for incorporation into the NSTF RCCS Designer Input Report, Technical Data Record, 12-9239789-000, AREVA Design Proposal for the Water-Based NSTF Test Section and Network Piping Argonne National Laboratory, Technical Report, ANL-NSTF-000000-TECH-016-R0, ANL Water-Cooled RCCS R&D Designer Observation Report, Technical Data Record, 12-9237246-000, AREVA Design Proposal for the Water-Based NSTF Test Section and Network Piping Argonne National Laboratory, Technical Report, ANL-NSTF-000000-TECH-016-R1, ANL

Participation from Framatome, INL, DOE, NRC, and US Universities Design review meeting held at Argonne in February of 2015 Test planning and program readiness meeting held March of 2018 Consensus reached on a design and test plan that reflects a representative yet bounding configuration for future implementation into a full scale design

The final facility meets ANL/DOE project goals, and will provide industry with data suitable for characterizing the RCCS of their full scale HTGR design NEI/NRC, July 2018 Argonne National Laboratory 19

Air / Water Comparison NEI/NRC, July 2018 Argonne National Laboratory 20 Air, 2010 - 2016 Water, 2017+

Water Facility Overview

1/2 axial scale Total height of 18 m (59-ft)

Heated length of 6.7 m (22-ft)

Natural circulation boiling water test loop Operating modes of natural or forced

4,260 liter water storage tank H/D ratio of 2.0, rated to 2 bar over pressure

Heat transfer panel:

Eight riser tubes and ten heat transfer panels 316L stainless tubes, 1018 carbon fins Full penetration HLAW weld to risers

Network piping: 4.0 Sch. 40, 316L stainless NEI/NRC, July 2018 Argonne National Laboratory 21

Cooling Panel Design NEI/NRC, July 2018 Argonne National Laboratory 22 Material k (W/m-K)

(-)

Fin 1018 carbon 51.9

> 0.8 Pipe 316L stainless 16.2

< 0.3

Cooling Panel Installation NEI/NRC, July 2018 Argonne National Laboratory 23 Assembled panel staged for 180° flip Panel hoisted vertical prior to install Installed test section, view in heated cavity Bead blasted cooling panel surface

Water Instrumentation NEI/NRC, July 2018 Argonne National Laboratory 24 Electromagnetic flow meters Gamma densometer Measurement Sensor Location Qty.

Mfg.

Model Range Flowrate Magnetic Inlet header x1 Krohne Optiflux 4000

+/-5kg/s Flowrate Magnetic Inlet riser x8 Krohne Optiflux 4000

+/-1kg/s Static head Strain Inlet header x1 Rosemount 3051S 0 - 10bar Steam pressure Strain Gas space x1 Rosemount 3051S 0 - 2barabs P

Strain Chimney x2 Rosemount 3051S

+/-6kPa P

Strain Risers x3 Rosemount 3051S

+/-62kPa Liquid level Strain Tank x1 Rosemount 3051S 0 - 3m Void fraction Optical Chimney x2 RBI Twin-tip 0 - 100%

Void fraction

-Density Chimney x1 ThermoFisher DensityPRO 0 - 100%

Temperature RTD Fluid x4 Omega UP1/10DIN 0 - 250°C Temperature T-type TC Fluid x128 ARi T-31N 0 - 400°C Temperature K-type TC Test section x24 ARi T-31N 0 - 600°C Temperature K-type TC Strain x286 ARi Silica20AWG 0 - 600°C Temperature DTS Test section x20 LUNA ODiSI-A 0 - 300°C Water pH pH meter Inlet header x1 Emerson RBI547 0 - 14pH TrDO O2 Amperometric Inlet header x1 Emerson 499A 0.1ppb-20ppm Conductivity Magnetic Inlet header x1 Krohne Optiflux 4000 1 - 6000S/cm

Path forward for Water Testing

Basis and detail of test planning included in ANL-ART-98 (M2, August 2017)

Checkout activities are in-progress

Test planning & review meeting has been held prior to initiating matrix testing Invitation included programs to key players

External audit of program and test procedures prior to initiating matrix testing Completed without any findings

Baseline testing to begin by FY2019

Continue communication with industry & NRC NEI/NRC, July 2018 Argonne National Laboratory 25

Water Program Timeline NEI/NRC, July 2018 Argonne National Laboratory 26 Fiscal Year 2015 2016 2017 2018 2019 2021 2022 2023 Discussion, Preparation, Scaling Test Section Design Network & Tank Design M&E Procurement Air-based Disassembly Fabrication & Construction Installation & Assembly Checkout Activities (Phase )

Characterization (Phase )

Baseline Testing (Phase )

Parametric Studies (Phase )

Maintenance Accident Testing (Phase )

Geometric Variations (Phase )

Data Review Period Final Report Design and Review Purchasing and Construction Checkout and Maintenance Experimental Testing

Global Scaling and Verification Analysis Working Fluid Studies (air / water)

Computational Modeling Realization of Full Scale Deployment of the RCCS NEI/NRC, July 2018 Argonne National Laboratory 27 1D System 3D CFD Scaled Experiments 1/2 scale 1/4 scale Sep. Effects

Acknowledgments NEI/NRC, July 2018 Argonne National Laboratory 28 Argonne Project Personnel Project Manager Mitch Farmer Facility Manager Darius Lisowski Lead Experimenter Qiuping Lv Principal Investigator Darius Lisowski Quality Assurance John Woodford Roberta Reil Facility Designer Dennis Kilsdonk Test & Instrumentation Nathan Bremer Steve Lomperski Laboratory Technical Tony Tafoya Art Vik Dave Engel Bruce Herdt Program Sponsors Federal Alice Caponiti Diana Li Technical Diane Croson Guidance / Consultation External Guidance Steve Reeves Hans Gougar Jim Kinsey Lew Lommers Sud Basu Mike Salay Internal Guidance Bob Hill Chris Grandy Derek Kultgen Analysis Support Team Computer Models R. Hu M. Bucknor A. Kraus Q. Lv T. Lee Notable Mentions Project Manager Tom Wei (retired)

Modeling David Pointer Elia Merzari Summer Students Skyer Perot Jordan Cox James Schneider Daniel Nunez David Holler This work was supported by the U.S. Department of Energy Office of Nuclear Energy, Office of Advanced Reactor Concepts under contract number DE-AC02-06CH11357

Questions?

NEI/NRC, July 2018 Argonne National Laboratory 29 http://www.ne.anl.gov/capabilities/rsta/NSTF

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