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Overview of the United States
Gas Cooled Reactor Technology Program
Thomas J. O’Connor, Director
Office of Gas Cooled Reactor Technologies
March 28 – 30, 2011
2 March 28 -30, 2011
Delivering Nuclear Solutions for America’s Energy Challenges
Mission and Program Objectives
Mission: Demonstrate high-temperature gas-cooled reactor (HTGR) technology to produce electricity and high temperature process heat via the Next Generation Nuclear Plant (NGNP) Demonstration Project
Program Objectives
Partner with industry to commercialize HTGR technology
Collaborate with the Nuclear Regulatory Commission (NRC) to establish a licensing framework for HTGRs
Draw upon the national laboratories, universities, and international community to perform the Research and Development (R&D) necessary to decrease the technical risk
3 March 28 -30, 2011 Delivering Nuclear Solutions for America’s Energy Challenges
Strategic Linkages*
Research Objective 1 (Current Fleet)
R&D techniques developed through the NGNP program can be applied to light water reactor (LWR) technology
Research Objective 2 (New Builds)
NGNP’s HTGR technology is uniquely able to provide economical electricity and high temperature process heat with zero greenhouse gas emissions while increasing energy security by reducing the reliance on imported oil
Research Objective 3 (Sustainable Fuel Cycle)
HTGRs achieve higher burn-up rates than traditional LWRs (15% fissions per initial metal atom compared to 5% for LWRs)
Research Objective 4 (Non-proliferation)
Higher burn-up rates reduce the attractiveness of used nuclear fuel
GIF Proliferation Resistance and Physical Protection criteria will be used to evaluate NGNP designs
*Nuclear Energy Research & Development Roadmap: Report to Congress
http://www.nuclear.energy.gov/pdffiles/NuclearEnergy_Roadmap_Final.pdf
4 March 28 -30, 2011 Delivering Nuclear Solutions for America’s Energy Challenges
Energy Policy Act of 2005 (P.L. 109-58)
Use Generation IV technology to
Produce electricity and/or process heat for hydrogen and other applications
Establishes phased project
Phase I - R&D
Phase II - Design and Construction
Schedule
Inform technology selection – 2011
If decision to build is made – complete by 2021
Requires Licensing by the NRC
Requires siting in Idaho
Requires cost-share
Congressional Deliverables
Initial NERAC (now NEAC) program review (April 2006)
Joint DOE/NRC Licensing Strategy (August 2008)
Select technology by September 30, 2011 (on track)
NEAC recommendation on whether Project is ready to start Phase (on-going)
5 March 28 -30, 2011 Delivering Nuclear Solutions for America’s Energy Challenges
NGNP Funding by Activities
FY 2011 (CR) - $85M
NGNP Materials Development;
$14,050; 17%
NGNP Fuel Development;
$18,300; 22%
NGNP Project Management;
$6,500; 8%
NGNP Engineering; $4,100; 5%
NGNP Process End-User
Applications; $2,800; 3%
NGNP Regulatory Affairs;
$3,600; 4%
Nuclear Energy Advanced Modeling
& Simulation (NEAMS)
(Incl. SBIR/STTR Taxes);
$1,200; 1%
Management & Integration;
$6,080; 7%
NRC Support for NGNP;
$4,500; 5%NGNP Design
Method Development;
$5,000; 6%
NGNP - SBIR / STTR;
$1,870; 2%
University Research & Education
(Incl. SBIR/STTR Taxes);
$17,000; 20%
6 March 28 -30, 2011 Delivering Nuclear Solutions for America’s Energy Challenges
NGNP Funding by Activities
FY 2006 – FY 2010 ($528.447M)
NGNP Materials Development;
$60,502; 11%
NGNP Design Method Development;
$29,049; 5%
NGNP Preconceptual Design
(FY'07 & FY'08); $31,795; 6%
SBIR / STTR &
Rescission / Reductions;
$10,102; 2%
Other NGNP Activities (Regulatory
Affairs, NRC Support, & Proj. MGMT);
$62,193; 12% NGNP Engineering / Conceptual
Design (FY'09 - Present);
$82,544; 16%
Other Technical Support
(GIF Support / Intl. Collaboration,
Tech. Integration, & VHTR Activities);
$28,330; 5%
University NERI Aw ards (Grants &
Mortgages) & University Research &
Education (incl. SBIR/STTR Taxes);
$81,825; 15%
Earmarks: VHTR Deep-Burn
& Russian GT-MHR;
$31,078; 6%
NGNP Fuel Development;
$111,029; 22%
7 March 28 -30, 2011 Delivering Nuclear Solutions for America’s Energy Challenges
The Nuclear Heat Source
Technology Development and
Qualification Needs
Graphite Characterization,
Irradiation Testing, Modeling and
Codification
Fuel Fabrication, Irradiation, and Safety Testing
Design and Safety Methods Development and Validation
High Temperature Materials Characterization, Testing
and Codification
7
8 March 28 -30, 2011 Delivering Nuclear Solutions for America’s Energy Challenges
Fuel Qualification Program
Fission Product Transport
and Source Term
Fuel Performance Modeling
Fuel Supply
Fuel and Materials Irradiation
Post Irradiation
Examination and
Safety Testing
• Coated Particle Fuel Fabrication
• Fuel Qualification
• Analysis Methods Development and Validation
9 March 28 -30, 2011 Delivering Nuclear Solutions for America’s Energy Challenges
Graphite Materials Qualification
• Structural Graphite Development
• Material Properties
• Whole Core Models
Nuclear Graphite
ASTM Tests
Unirradiated Database
Unirradiated Properties
Whole Core Modeling
y = -9.6343x + 12.381
R2 = 0.9997
y = - 10 .3 8 8 x + 13 .53 2
R2
= 0 .9 9 71
0.0
0.5
1.0
1.5
2.0
2.5
3.0
3.5
4.0
0.95 1.00 1.05 1.10 1.15 1.20
1000/T (K-1
)
log
10 (
OR
)
Series1
Series2
Linear (Series1)
Linear (Series2)
Graphite Type A
Program Participants INL, ORNL
10 March 28 -30, 2011 Delivering Nuclear Solutions for America’s Energy Challenges
High Temperature Materials Qualification
Development of Material Properties and Design Rules
and
ASME Codification
Environmental Testing
Material Characterization
Mechanical Testing
Materials: • Pressure vessel
steels • Alloys for heat
exchangers (up to 800℃)
• Control rod sleeves and other core internals
Program Participants INL, ORNL, ANL
Ni from Watts bath plating
Cr Oxide surface layer
Al Oxide intergrowth
11 March 28 -30, 2011 Delivering Nuclear Solutions for America’s Energy Challenges
Design & Safety Methods & Validation
Design Methods and Validation
Physics, Thermal and System Safety Methods, Code Development and Application
INL’s Matched Index of Refraction (MIR) Facility to Study 3-D Flow Effects in
Plena
35.99688
Fuel hole210 X Ø 1.27
LBP hole6 X Ø 1.27
Coolant hole102 X Ø 01.5875
Inner coolant hole6 X Ø 1.27
Fuel pitch
0.740
(1.8796 cm)
Fuel handling hole
Cross-section Measurements
at LANL
Scaled Vessel Testing
Pebble and Prismatic Physics Methods
Multi-dimensional CFD Simulations
Graphite/Air Reaction Rate Testing
Integral Systems Modeling
ANL Facility to Validate VHTR Cavity Cooling System Behavior
Separate Effects & Integral Testing Under Normal & Off-Normal Conditions
12 March 28 -30, 2011 Delivering Nuclear Solutions for America’s Energy Challenges
End-user Interface
Integration of nuclear energy with non-electric end-user applications System integration, diagnostics and control
Establishing efficient and well-integrated means of transferring and
transporting nuclear energy to the end-user application at high
temperatures
Coupling nuclear reactors to large chemical customers Analysis of interaction between nuclear reactor kinetics and kinetics of industrial plant
Understanding of performance of solid electrolytic cells to produce hydrogen
Studying the feasibility of effective use of carbon feedstocks such
as biomass, fossil carbon and carbon dioxide in an integrated
nuclear system
13 March 28 -30, 2011 Delivering Nuclear Solutions for America’s Energy Challenges
VHTR activities integrated into Next Generation Nuclear Plant
Participants: Canada, China, Euratom, France, Korea, Japan, Switzerland and United States (South Africa continuing with observer status)
US Steering Committee member Carl Sink
Project Arrangements include:
Fuels and Fuel Cycle (2008)
Materials - graphites, high-temperature metals, ceramics (chaired by U.S.) (2010)
Hydrogen Production (2008)
Computational Methods, Validation and Benchmarking (chaired by U.S.) (2011)
GIF VHTR activities integrated with national programs
China – High Temperature Reactor – Pebble Bed Modular (HTR-PM)
Euratom – RAPHAEL, PUMA and EUROPAIRS Projects
Japan – High Temperature Test Reactor (HTTR)
US – Next Generation Nuclear Plant (NGNP)
South Africa – Pebble Bed Modular Reactor Demonstration Power Plant
GIF Very High Temperature Reactor
(VHTR) System
14 March 28 -30, 2011 Delivering Nuclear Solutions for America’s Energy Challenges
Work For Others Graphite qualification with PBMR Pty Ltd, South Africa (ORNL)*
Graphite irradiation with Japan (Toyo Tanso and Tokai Carbon, at ORNL)
Cooperative Research and Development Agreements CRADA with PBMR Pty Ltd for AGR-2 fuel irradiation in ATR (INL)*
CRADA with CEA for AGR-2 fuel irradiation in ATR (INL)
Potential CRADA with PBMR Pty for Graphite Creep and Composite Material Qualification (ORNL, under discussion)*
Bilateral Agreements Collaboration with Japan (JAEA) for HTTR test data (INL, under development)
Graphite irradiation with Japan (JAEA on behalf of Toyo Tansa, at ORNL, under development)
I-NERI:
– Korea on VHTR Air Ingress and Core Bypass (INL), on Advanced Computational Methods and SCO2 Energy Conversion (ANL)
– France on Metallic (INL) and Composite (ORNL) Materials
– Japan on use of ZrC in TRISO fuel
– Euratom (Italy on LFR (ANL, LLNL))
Congressionally-directed collaborations with Russia on gas reactors (in cooperation with NNSA)
International Organizations – IAEA, NEA/OCD
*Impact of PBMR Pty Ltd downsizing being evaluated.
Other International Collaborations
15 March 28 -30, 2011 Delivering Nuclear Solutions for America’s Energy Challenges
NGNP Licensing Path to Deployment
Overall strategy established in DOE-NRC Report to Congress
(August 2008)
Recommended Part 52 “one step” Combined License (COL) process
– Lowers licensing risk
– Increases project certainty for stakeholders
Identified initial set of priority issues
– Described process for adaptation of existing LWR rules
– Identified likely need for new or revised regulatory approaches in certain areas
Established NRC infrastructure and resource needs
Focused on steps to support NGNP deployment
– Licensing pre-application program with NRC
– NGNP license application and NRC review/approval
– Construction and plant startup with NRC oversight
NGNP Licensing Plan (2009)
Identified priority topics and described implementation plan
Defined a plan for documenting COL Application Content Guide for HTGRs
16 March 28 -30, 2011 Delivering Nuclear Solutions for America’s Energy Challenges
NGNP Licensing White Papers
White Papers submitted to NRC to date:
Defense in Depth (Dec 2009)
High Temperature Materials Qualification (June 2010)
Fuel Qualification (July 2010)
Mechanistic Source Terms (July 2010)
License Structure for Multi-Module Plants (August 2010)
Licensing Basis Event Selection (Sep 2010)
Safety Classification of Structures, Systems and Components (Sep 2010)
Emergency Planning Requirements (Oct 2010)
Additional white papers planned for near-term submittal include:
Use of PRA, including Integrated Risk for Multi-Module Facilities
HTGR Safety Basis – overview
Tritium Release Limits and Regulatory Issues
Nuclear/Industrial Island Licensing Boundary
Co-Location of HTGRs with Industrial Facilities
17 March 28 -30, 2011 Delivering Nuclear Solutions for America’s Energy Challenges
Regulatory Gap Analysis
Comprehensive review to identify “gaps” between existing LWR-
focused regulations and those needed to license HTGRs
Gap analysis is in progress and will provide regulatory
accounting of existing NRC requirements and guidance
documents applicable to HTGRs
Enable early resolution of identified gaps
Identified gaps and resolutions will be tracked to completion
Completed resolutions are then incorporated into the COLA Content Guide
for HTGRs
18 March 28 -30, 2011 Delivering Nuclear Solutions for America’s Energy Challenges
Interactions Related to SMR Licensing
NGNP project also involved with SMR community on generic
advanced reactor licensing topics
NRC documented key SMR policy, licensing, and technical challenges in its
SECY 10-0034 (March, 2010)
NGNP is identified in the SECY as the “test case” for addressing and
resolving many of the identified issues
NGNP has made a number of submittals and is in active dialogue with the
NRC in addressing the highest priority SECY items
NGNP participates in the NEI Licensing Task Force to provide input on
generic topics (annual fees, insurance liabilities, etc.)
19 March 28 -30, 2011 Delivering Nuclear Solutions for America’s Energy Challenges
Licensing Path Forward
Keep NRC resources engaged with disposition of NGNP priority
topics, including common understanding of technology issues
Continue R&D collaborations with NRC
Conduct Generic Site Hazards Assessments
Complete Regulatory Gap Analysis that will serve as basis for
creation of a license application form and content guide
Begin development of COLA Content Guide
Continue to support HTGR workshops and industry advanced
reactor forums addressing licensing topics
Implement NRC approved Appendix B Quality Assurance Program
Preliminary design detail is needed to address Content Guide open
items and develop license application documents
20
ANS 53.1 – Nuclear Safety Design
Standard for Modular Helium Cooled
Reactor (MHR) Plants
ANS 53.1 provides a process to:
Develop MHR top level nuclear regulatory safety criteria
Identify safety functions, top level design criteria, licensing basis events,
design basis accidents and methods for performing safety analyses
Determine safety classification of structures, systems, and components
(SSCs)
Identify safety-related SSCs special treatment requirements and defense-
in-depth (DID) provisions
Demonstrate adequacy of DID by applying a risk-informed approach
MHR vendors, NGNP and NRC staff involved in development of
standard
Endorsement is expected in FY2011
March 28 -30, 2011
Delivering Nuclear Solutions for America’s Energy Challenges
21
SC-MHR Demonstration Plant Configuration and
Key Design Parameters
• SC-MHR produces steam at 585°C and 16.5 MPa
• Steam conditioned to user requirements via topping cogeneration
– Representative process steam conditions assumed, 4.6MPa at ~400°C
• Nominal reactor outlet temperature (ROT) of 725°C
– Optimum ROT for selected steam conditions from standpoint of
plant cost, safety, and investment risk
Insert Photo or Image (not chart – space too small)
22
General Arrangement of SC-MHR Demonstration
Plant
Insert Chart, Photo or Image
• Plant is physically separated into
the NI and Energy Conversion Area
(ECA)
• Separation allows ECA to be
constructed and operated per non-
nuclear standards
• NI includes the SRM and non-safety
related SSCs, including systems
that would be shared in a multi-
SRM plant
• ECA includes SSCs for feedwater
supply and steam utilization, plus
the supporting systems and plant
facilities commonly referred to as
the Balance of Plant
23
General Arrangement of 4-Module SC-MHR
Reference Commercial Plant
Insert Chart, Photo or Image
• Reference commercial plant
includes four SRMs
• SRMs can be constructed and
commissioned sequentially or in
parallel
It is expected that the Demonstration
Plant will be expanded to the first-of-a-
kind, reference four-module commercial
plant by sequential addition of SRMs
24 March 28 -30, 2011 Delivering Nuclear Solutions for America’s Energy Challenges
Nuclear Energy Advisory Committee
(NEAC) Review
EPAct 2005 requires a review of NGNP Project by the NEAC prior to proceeding to final design and licensing (Phase 2)
Evaluate Conceptual Design deliverables, R&D results achieved to date, status of NRC licensing activities, impacts on greenhouse gas emissions and business models
Reviews:
Market Case / Design Requirements - September 30/October 1
Licensing / Program Plan/ Partnership - November 15/16
Pebble and Prismatic Designs - February 22/23
R&D - April
Recommendation Report expected in May 2011
25 March 28 -30, 2011 Delivering Nuclear Solutions for America’s Energy Challenges
Forming the NGNP Partnership
Forming a Cost-shared Public-Private Partnership
Market Research Conducted
– Letter sent out to HTGR industry community to solicit feedback on formation of
the partnership
Draft Funding Opportunity Announcement
– Planned for Spring 2011
– Will incorporate feedback from Market Research
Final Funding Opportunity Announcement
– Planned for Summer 2011
Preliminary thoughts
Cooperative Agreement
– Base Award to develop business plan, decision points/criteria, control of
Intellectual Property, cost share, etc
– Option #1: Preliminary Design
– Option #2: License Application Submittal
– Option #3: Construction
26 March 28 -30, 2011 Delivering Nuclear Solutions for America’s Energy Challenges
NGNP Path Forward
Continue Research and Development in materials, fuels, code validation experiments and end user interface analysis
Continue licensing efforts with the Nuclear Regulatory Commission
Complete NEAC Review
Establish Cost-shared Public-Private Partnership
Timing of Secretarial Decision influenced by NEAC Recommendation and status of Cost-shared Public-Private Partnership
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