Reactor and Nuclear Systems Division (RNSD) M&S Support for Fusion Applications
Michael Dunn, Luiz Leal, Bob Grove, and Tim Valentine
The Virtual Laboratory for Technology Meeting
May 15, 2013
Outline • RNSD Organization • Nuclear Data and Fusion Evaluated Nuclear Data Library • Modeling and Simulation Capabilities • RSICC and SINBAD Database • Summary
Reactor Physics
Steve Bowman – Angie Alford1
Brian Ade Jim Banfield5 Kevin Clarno Ron Ellis Ian Gauld Andrew Godfrey Jianwei Hu4 Germina Ilas Matthew Jessee Kang-Seog Kim Jordan Lefebvre Rob Lefebvre Ivan Maldonado3 Ugur Mertyurek Josh Peterson Jeff Powers Harold Smith Adam Thompson Mark Williams Will Wieselquist Andy Worrall
Thermal Hydraulics and Irradiation Engineering
Graydon Yoder, Jr. – Charlene Patrick
Juan Carbajo Nesrin Cetiner Dave Felde Richard Howard Prashant Jain Jose March-Leuba Joel McDuffee Larry Ott David Pointer Emilian Popov Frank Riley Kevin Robb Bob Sitterson Doug Sparks2
Ken Thoms2
Dean Wang
Doug Kothe, Director
Consortium for Advanced Simulation of Light Water Reactors (CASL) Cecil Parks, Director
Sandra Poarch1, Division Secretary
Reactor and Nuclear Systems Division February 1, 2013
Advanced Reactor Systems and Safety
Gary Mays – Anita Benn Syd Ball6 Randy Belles Bruce Bevard Sacit Cetiner Don Copinger George Flanagan Richard Hale T. J. Harrison David Holcomb Robert Joseph, III Becky Moses Mike Muhlheim Mike Poore Lou Qualls Don Williams, Jr. Richard Wood
Nuclear Data and Criticality Safety
Mike Dunn – Hannah Turpin1 Goran Arbanas Doug Bowen Cihangir Celik Justin Clarity Ernie Elliott Klaus Guber Calvin Hopper2 Luiz Leal B. J. Marshall Don Mueller Lester Petrie, Jr. Marco Pigni Royce Sayer 2 Mike Westfall 6
Dorothea Wiarda
Nuclear Security Modeling
Tim Valentine – Angie Alford1
Bryan Broadhead Matthew Francis Brandon Grogan David Hooper Vincent Jodoin Thomas Miller Bruce Patton Chuck Weber
Radiation Transport
Bob Grove
– Hannah Turpin1
Hatice Akkurt Kursat Bekar Aaron Bevill5 Keith Bledsoe Charles Daily Gregory Davidson Thomas Evans Steven Hamilton Ahmad Ibrahim4 Dan Ilas Josh Jarrell Seth Johnson Scott Mosher Tara Pandya4 Douglas Peplow Chris Perfetti4 Georgeta Radulescu Igor Remec Joel Risner
NRC Projects Office
Julie Stringfield - Sandra Poarch1 Lindsey Aloisi 6
Used Fuel Research, Development, and Demonstration
John Wagner – Debbie Weaver Rob Howard
1 Dual Capacity 2 Subcontractor 3 Joint Faculty 4 Post Doc 5 Postmasters 6 Casual/Part-time 7 On Assignment
Business Management – Diane Sams Operations Management – David Drake Human Resources – Megan Scott
Support
Reactor Technology R&D Integration
Jess Gehin -Sandra Poarch1
M&S Leadership Team
Cecil Parks Steve Bowman Mike Dunn Tom Evans Jess Gehin Bob Grove Brad Rearden John Wagner
Radiation Safety Information Computational Center
Tim Valentine - Teresa Moore Janice Arwood Mark Baird
Dan Garner Barbara Snow
SCALE Development and Maintenance
Brad Rearden Sheila Walker
John Scaglione
4 RNSD M&S Support for Fusion Applications
Integrated Nuclear Data and M&S Capabilities
5 RNSD M&S Support for Fusion Applications
RNSD Support for Fusion Evaluated Nuclear Data Library Version 3 (FENDL-3)
• Nuclear cross-section database project developed and maintained by the IAEA for fusion applications
– Includes data for neutron, gammas, charged particle, nuclear heating, and gas production reactions along with limited cross-section covariance (uncertainty) data
• IAEA initiated Coordinated Research Project (CRP) in 2008 to improve nuclear cross-section data for fusion analyses including IFMIF
• FENDL-3 is latest library developed, tested, and released through CRP—Luiz Leal (RNSD) invited member of IAEA FENDL CRP
• FENDL-3 V&V calculations are in progress both in the US and internationally—M. Sawan (Univ Wisconsin) performed detailed V&V with MCNP (example results):
– Activation analysis: FENDL-3 C/E activation foil results improved relative to FENDL-2.1 for bulk shield experiment except for tungsten data—need improved tungsten data
– Gas production: Missing D, T, He-3 reactions for several materials—need update to FENDL-3
FNG Experimental Benchmark
Radiation Transport Model
6 RNSD M&S Support for Fusion Applications
RNSD Support for Fusion Evaluated Nuclear Data Library Version 3 (FEND-3)
• ORNL Contributions to IAEA FENDL CRP – Nuclear data evaluations using ORNL-
developed SAMMY R-matrix analysis software—providing neutron cross-section evaluations with covariance data
– RNSD contributions to FENDL-3: 27Al, 55Mn, 28Si, 30Si, 46Ti, 47Ti, 48Ti, 49Ti, 50Ti, 50Cr, 52Cr, 53Cr, 54Cr
– RNSD evaluations in progress: tungsten isotopes (182W, 183W, 184W, 186W) and 56Fe
• Data assessment needs—potential collaboration with M. Sawan (Wisconsin) – Use of nuclear data covariance propagation
tools to assess nuclear data uncertainty impacts for fusion applications (e.g., ORNL-developed SCALE sensitivity/uncertainty capabilities)
– Verification of MCNP results with other transport codes (SCALE)
!"/" vs. E for 184W(n,tot.)
10 -310 -1
10 110 3
10 510 7
0 1 2 3 4 5 6
!"/" vs. E for 184W(n,tot.)
10-3 10-1 101 103 105 1070
1
2
3
4
5
6Linear Axes:Rel. Standard Dev. (%)
Logarithmic Axes:Energy (eV)
Correlation Matrix
0.00.20.40.60.81.0
0.0-0.2-0.4-0.6-0.8-1.0
Tungsten-184
7 RNSD M&S Support for Fusion Applications
Ø RNSD radiation transport methods and analyses rely upon nuclear data libraries produced by AMPX
AMPX Providing Nuclear Data Libraries for M&S AMPX Graphical User Interface
! v
s. E
for 5
4Cr(n
,tot.)
10
-31
0-1
10
11
03
10
51
07
0 2 4 6 8
10
12
14
16
"!/! vs. E for 54
Cr(n,tot.)
10-3
10-1
101
103
105
107
0
1
2
3
4
5
6
7Ordinate scales are % relative
standard deviation and barns.
Abscissa scales are energy (eV).
Correlation Matrix
0.0
0.2
0.4
0.6
0.8
1.0
0.0
-0.2
-0.4
-0.6
-0.8
-1.0
Covariance Data
Multi-group elastic scattering for hydrogen
8 RNSD M&S Support for Fusion Applications
RNSD and the RNSD Radiation Transport Group – unique capabilities for fusion neutronics
• A community of experts in all aspects of radiation transport and shielding for many applications including nuclear reactors, accelerators, irradiation/activation facilities, as well as fusion neutronics
• Experts and software tools that provide all required nuclear data; sensitivity and uncertainty analyses for all types of radiation transport applications
• Access to and ongoing development of radiation transport analysis tools on US leadership-class computing facilities and on RNSD capacity computing clusters
• Extensive collaboration with US ITER fusion neutronics efforts (Univ Wisc – Madison, UCLA, PPPL) and growing contacts with the international ITER fusion neutronics community
• Of specific interest for ITER and fusion neutronics design and analyses: – Accurately and efficiently determining nuclear responses in complex systems (nuclear heating, damage, gas
production, material and biological doses, etc.) using full-scale models and our signature analysis tools – Developing tools for accurately determining the complex, ITER shutdown dose rates (SDDR) – Providing expert assistance to others using our signature tools, expert reviews of ITER
neutronics analyses, consulting services for the ITER computer server, located at ORNL
9 RNSD M&S Support for Fusion Applications
RNSD and the RNSD Radiation Transport Group – unique capabilities for fusion neutronics
• Our signature hybrid Monte Carlo / deterministic transport methods and tools are providing solutions to previously intractable problems for ITER neutronics analyses – CADIS (Consistent Adjoint-Driven Importance Sampling)
• High-fidelity (low variance) results in local regions – FW-CADIS (Forward Weighted CADIS)
• High-fidelity results throughout entire problem spaces – MS-CADIS (Multi-Step CADIS)
• Under development (unfunded) to address the complex multi-step problem for ITER shutdown dose rate analyses
• Neutron transport è material activation / transmutation / decay è photon transport è dose rates, nuclear heating, etc.
– Implemented in our signature tools, ADVANTG (hybrid) and Denovo (deterministic transport), to provide advanced VR (variance reduction) parameters for dramatically speeding up MCNP particle simulations
10 RNSD M&S Support for Fusion Applications
Many extremely difficult ITER fusion-neutronics calculations need ADVANTG
Central plane
20° plane
Ports plugs in vacuum vessel
Prompt dose rate maps
10 days FW-CADIS/MCNP Dose rates µSv/hr
10 days analog MCNP
Solution in 25.8% of regions
Solution in 95.6% of regions
11 RNSD M&S Support for Fusion Applications
Dose rates at outboard bioshield surface
0
50
100
150
200
250
300
-‐1230 -‐730 -‐230 270 770 1270
Dose (μSv/hr)
Distance from equatorial plane (cm)
Center line 20° line
Dose rates µSv/hr
Center line
20° line Equatorial
plane
Center line
20° line
Port openings In vacuum vessel
Dose rates along two lines behind bioshield
• Factor of 1000 peaks in dose because of ports and complex inboard equipment arrangements
• These calculaEons not tractable without ADVANTG • Without this capability, the design will be significantly
over-‐ or under-‐conservaEve
12 RNSD M&S Support for Fusion Applications
RSICC’s Shielding Integral Benchmark Archival Database (SINBAD)
• Initiated in the early 1990s • Joint effort between RSICC and the Nuclear
Energy Agency Data Bank (NEADB) • Shielding benchmarks for
– Nuclear reactors (45 exps.) – Fusion devices (29 exps.) – Accelerators (23 exps.)
• Basis for validation and verification of radiation shielding codes and data
• RNSD nuclear and M&S expertise coupled with RSICC capabilities can be leveraged to improve and expand SINBAD for fusion V&V needs
• Active US participation in SINBAD is needed to maintain leadership in establishing priorities for reviews along with the OECD/NEA
13 RNSD M&S Support for Fusion Applications
OECD-NEA WPRS Structure
14 RNSD M&S Support for Fusion Applications
NEA Science Committee and Data Bank NEA Nuclear Science CommiOee
InternaEonal Working ParEes
InternaEonal Benchmarks Released by the
NEA Nuclear Data Bank
WPEC WPRS WPNCS WPFC WPMM
Expert Group on Reactor Fuel Performance
Expert Group on Radia=on Transport and Shielding
Expert Group on Reactor Physics and Advanced Nuclear Systems
Expert Group on Uncertainty Analysis in Modeling
Expert Group on Uncertainty Analysis for Cri=cality Safety Assessment
Expert Group on Assay Data for Spent Nuclear Fuel
Expert Group on Advanced Monte Carlo Techniques
Expert Group on Cri=cality Excursions Analysis
Expert Group on Burnup Credit
JEFF
EVA
EXFOR
CINDA
IFPE SINBAD IRPhE ICSBEP SFCOMPO TBD
U.S. leadership and participation in the expert groups is critical for U.S. nuclear research programs
15 RNSD M&S Support for Fusion Applications
Example SINBAD Benchmark: ITER Bulk Shield Mock-up Experiment at FNG
Measurements of neutron/photon flux spectra by TUD (K. Seidel et al.)
• Mock-up of ITER inboard blanket/shield system with thickness of 94 cm (alternating plates of SS-316 and of Perspex).
• Backed by 30 cm thick block of alternating SS-316 and Cu plates simulating TF-coil.
• Neutron and photon flux spectra measured at positions A (41.4 cm) and B (87.6 cm)
• Neutron spectra measured in the energy range between about 20 keV and 15 MeV.
– A set of gas-filled proportional counters and a stilbene scintillation spectrometer used in the energy range up to 3 MeV.
– NE-213 scintillation spectrometer for energy range 1 to 15 MeV.
• Photon flux spectra measured with NE-213 spectrometer above 0.2 MeV.
Position A 41.4 cm Position B
87.6 cm
K. Kondo, U. Fischer, et al.. FENDL-3 Benchmarking
16 RNSD M&S Support for Fusion Applications
0.01 0.1 1 10 2010-7
10-6
10-5
Neu
tron
flux
(/cm
2 /leth
argy
/s.n
.)
Neutron energy (MeV)
Expt. FENDL-3/SLIB4 FENDL-2.1 JEFF-3.1.1 ENDF/B-VII.0 JENDL-4.0
Position A (41.4 cm)
Neutron spectra (ITER bulk shield expt.)
Position B (87.6 cm) Position A (41.4 cm) 0.01 0.1 1 10 20
10-10
10-9
10-8
Neu
tron
flux
(/cm
2 /leth
argy
/s.n
.)
Neutron energy (MeV)
Expt. FENDL-3/SLIB4 FENDL-2.1 JEFF-3.1.1 ENDF/B-VII.0 JENDL-4.0
K. Kondo, U. Fischer, et al.. FENDL-3 Benchmarking
17 RNSD M&S Support for Fusion Applications
Benefits of an Evaluated SINBAD • An Evaluated SINBAD provides several benefits to the
fusion community: - Ability to leverage the database tools being developed by the OECD-
NEA - Provide standardized set of benchmark descriptions for validating
computational tools and nuclear data - Ensure historical knowledge gaps are accurately documented and
addressed while retired experimenters are still available - Provide guidance for collection and evaluation of future experiments
to ensure that adequate data are collected for benchmarking purposes
- Engage universities to conduct benchmark evaluations • Engages the next generation of fusion scientists • Makes optimal use of the limited fiscal resources
18 RNSD M&S Support for Fusion Applications
Summary • ORNL/RNSD has demonstrated support fusion R&D in 3 primary focus areas:
– Nuclear data and IAEA CRP efforts to develop and deploy FENDL-3 – State-of-the-art radiation transport capabilities and analyses (e.g., hybrid MC/
Deterministic) – SINBAD benchmark database management in addition to contributions and V&V analyses
• Continued R&D needed in the 3 focus areas – Nuclear Data
• Continued participation in IAEA FENDL CRP to provide improved nuclear data evaluations • V&V and uncertainty propagation to assess nuclear data uncertainty impact in fusion analyses—
identify target nuclear data accuracies needed for improved nuclear data
– Use and improvement of radiation transport M&S capabilities to solve problems that are not tractable with standard Monte Carlo analysis capabilities • Example analyses: nuclear heating, radiation damage, gas production, material/biological dose
– SINBAD database developed and maintained per QA plan • Define consistent format for documenting experiment and evaluation of uncertainties • Provide standardized format consistent with other benchmark databases (e.g., ICSBEP) • Focus on data improvements needed for fusion applications
