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Click to edit Master title styleClick to edit Master title
styleNSUF Resources and the Combined Materials Experimental Toolkit (CoMET)Brenden Heidrich, Ph.D.Chief Irradiation Scientist, NSUFNational Technical Director, I2
INL/MIS-18-51686
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Integrated Infrastructure Enhancement
Capabilities Data
DOE-NE and Industry Needs
Gap Analyses
Investments and
Partnerships
1. Gather Data on Nuclear Energy R&D Capabilities
2. Estimate DOE-NE R&D Directions and Industry priorities
3. Provide Gap Analysis Report for Nuclear Energy.
4. Assist funding decisions and incorporate the results into the NEID.
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NSUF Information Mgmt Resources
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Data Collection and Structure
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Nuclear Energy Infrastructure Database
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NSUF Core Facilities and Partners
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NEID Entry for the ATR
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Map Browsing Tool
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Text Search Tool for all Databases
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NSUF Resource Browser
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Nuclear Fuels and Materials Library
• Provides irradiated samples for users to access and conduct research through a competitively reviewed proposal process.
• The library includes >3500 specimens as part of the NSUF awarded research.
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NUCLEAR SCIENCE USER FACILITIES Website
SUBJECT MATTEREXPERT (SME)
Database
MY NSUFDatabase
INFRASTRUCTUREDatabase
PROJECTSDatabase
NFMLDatabase
Graphic courtesy of Kelly Cunningham
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FUELS & MATERIALSLIBRARY
Temperature
Dose (DPA)
Flux [x1014 ]
Fluence [x1020]
Environment
PLANNED
Temperature
Actual Dose (DPA)
Flux [x1014 ]
Fluence [x1020]
Environment
AS RUN DATA
PROJECT NAME
Storage FACILITY
Notes
# of Samples
Samples Remaining
Specimen Availability
Certification
Certification Code
Availability Date
Capsule
Packet
Material Name
Material Description
Dimensions
KGT #
Sample ID Code
Material Code
Specimen Type
REACTOR
REACTOR POSITION
PROJECT NAME
Project ID
CINR #
RTE #
NSUF Call
Award Date
Start Date
End Date
PI Name
Tech Lead
Facility Tech Lead
Collaborators Documentation
Project Type
INSTITUTION
FACILITY
Research Area
Material TypeProposal
PROJECT DATABASE
REACTOR
REACTOR POSITION
FACILITY
INSTITUTION
NEID
SME DATABASE
INSTITUTION
PI/SME Name
Research Area/Subject Matter
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EXPERIMENT WIZARDNuclear Science User Facilities
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NSUF Experiment Process (Simplified)
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NSUF Experiment Process (Actual)
Graphic courtesy of Kaecee Holden
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• NSUF Databases – information about Databases managed by NSUF
• User Facility References – Pages co-managed with a representative at each institution, this section provides live user guides, interactive help, and other information that the facilities would want the user to know
• Nuclear Science Tools – Links to databases, codes, and other resources that are helpful for nuclear science (END/F, EXFOR databases, IAEA tools, etc).
• Tutorial – Helps the user and content managers (i.e. for User Facility References) understand how to use the wizard tool
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Wizard Guide through NSUF Resources
Graphic courtesy of Jordan Argyle
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Wizard Guide for Experiment Design
Graphic courtesy of Jordan Argyle
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. . .
Wizard Guide to Proposal Submission
Graphic courtesy of Jordan Argyle
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• This history shows how the tool is envisioned to be used. A main path is augmented with visits to references (ATR in this History) and other tools to accomplish their work.
• The tool allows multiple content creators to simultaneously manage content for their respective areas.
• Multiple users, Tech Leads, and others can all work on an experiment at the same time, keeping all information in one place.
• The Wizard clearly communicates requirements, expectations, and suggestions to help steer applicants to create more meaningful proposals.
Wizard as a Collaboration Tool
Graphic courtesy of Jordan Argyle
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IRRADIATION TOOLKITNuclear Science User Facilities
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Testing Strategy for Novel MaterialsIrradiation Testing Hierarchy
1. Ion Beams Irradiation Facilities• Allow immediate feedback of performance• Ease of instrumentation• Ease of environmental tuning
2. Low-Power Research Reactors• Proof-of-concept (First 1% and 10% testing)• Instrumentation development (pulsing for TREAT)• Neutron radiography• Experiment modeling & validation efforts
3. High-Performance Test Reactors• Proof-of-performance• Prototypical environment
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Small Specimen Tensile Testing Challenge
• Tensile testing has long been an important method for determining the material properties of different structural steel components.
• The effect of irradiation on these steel components is of particular interest to the nuclear power industry.
• The large (E8) specimens typically used are not efficient for test reactor irradiations. They also usually require a hot cell for performing post-irradiation examination.
• Research into using small-scale tensile specimens has been of great interest in the nuclear industry for quite some time.
AlloyDose Rate 6 dpa
T=0 T=365
SA 508 112 97
R/hr @ 30cm
625 75 28
718 6.2 0.13
690 1.5 0.10
316L 3.8 0.10
Grade 91 2.3 0.09
304L 3.8 0.09
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Calculator Data Flow
• Neutron Damage Calculator Input
• Desired DPA• Material Composition
Output• Days to desired DPA• Reactor Positions
• Radioactivity Calculator Input
• Irradiation time• Material composition
Output• Radioactivity at set decay times• Gamma Dose Rate
Graphic courtesy of Kaecee Holden
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Web Application – Position Selection• Representative reactor positions for:
INL ATR ORNL HFIR MITR-II (coming soon!) BR-2 OSURR NCSU Pulstar
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Web Application – Final Results
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Radioactivity Calculator Validation• Utilizes 252-energy group
neutron flux and activation cross-sections (JEFF)
• Improvement over available online calculators and previous calculator iterations
0
0.5
1
1.5
2
2.5
3
RADI
OAC
TIVY
T (C
I/G
)
HT-9
Calculator Comparison
ORIGEN 252-group 100-group
Thermal Munich Online
Technical University of Munich, “Calculate Activation,” https://webapps.frm2.tum.de/intranet/activation/ (2017).
0.04
0.4
4
0 50 100 150 200
RADI
OAC
TIVI
TY (C
I/G
)
TIME (DAYS)
HT-9
ORIGEN 252-group WT% FF X6
• Added a safety factor to improve accuracy.
• Only neutron activation/capture reaction included
• Meta-stable states not included
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Future Work• Internal and external validation of the calculators• Build the experiment wizard & test on CINR proposals• Incorporate other tools as needed (e.g. EXSAN from LANL)
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style
Questions?
INL/MIS-18-51686