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NCSP IE and T&E Activities at Sandia
Nuclear Criticality Safety ProgramTechnical Program Review
Washington, D.C.March 15, 2017
Presented byGary A. Harms
Sandia National LaboratoriesSAND2017-2772 PE
Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the U.S. Department of
Energy’s National Nuclear Security Administration under contract DE-AC04-94AL85000.
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Hands-On Criticality Safety Trainingat Sandia
• Two hands-on critical experiment classes are currently offered.
• The first is part of a two-week class for Nuclear Criticality Safety Professionals, 1 week at LANL and one week at Sandia or at NCERC.
• The other is a one-week class at Sandia for Nuclear Material Managers.
• Information about the classes and how to register is at http://ncsp.llnl.gov/classMain.html
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The Classes Continue to Servea Diverse Audience
Sandia NCSP IE and T&E – p. 4
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The Sandia Classes
• The Sandia classes are a series of four experiments– Approach on fuel– Approach on moderator height– “Split table” approach– Fuel removal approach
• Lectures on various subjects are integrated with the experiments
• Remember: http://ncsp.llnl.gov/classMain.html
Sandia NCSP IE and T&E – p. 5
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Sandia Integral Experiment Requests
IER Title Sponsor CED
206 Re-establish the 4.3% Enriched Critical Experiment Capability at Sandia SNL 3B
209 7uPCX 0.855 cm Pitch, Variable Depth Pure Water Moderator SNL 3A
230 Characterize the Thermal Capabilities of the 7uPCX SNL 2
285 Titanium Cross Sections in a Thermal Application (7uPCX) SRNL
304 Temperature Dependent Critical Benchmarks ORNL 1
305 Critical Experiments with UO2 Rods and Molybdenum foils IRSN 1
306 Critical Experiments with UO2 Rods and Rhodium Foils IRSN 1
441 Epithermal HEX Lattices with SNL 7uPCX Fuel for Testing Nuclear Data ORNL 1
451 Titanium Cross Sections in a Thermal Application (BUCCX) SRNL 3B
452 Inversion Point of the Isothermal Reactivity Coefficient SNL Pre-1
Sandia NCSP IE and T&E – p. 6
SAND2017-2772 PE
Sandia Integral Experiment Requests
IER Title Sponsor CED
206 Re-establish the 4.3% Enriched Critical Experiment Capability at Sandia SNL 3B
209 7uPCX 0.855 cm Pitch, Variable Depth Pure Water Moderator SNL 3A
230 Characterize the Thermal Capabilities of the 7uPCX SNL 2
285 Titanium Cross Sections in a Thermal Application (7uPCX) SRNL
304 Temperature Dependent Critical Benchmarks ORNL 1
305 Critical Experiments with UO2 Rods and Molybdenum foils IRSN 1
306 Critical Experiments with UO2 Rods and Rhodium Foils IRSN 1
441 Epithermal HEX Lattices with SNL 7uPCX Fuel for Testing Nuclear Data ORNL 1
451 Titanium Cross Sections in a Thermal Application (BUCCX) SRNL 3B
452 Inversion Point of the Isothermal Reactivity Coefficient SNL Pre-1
Sandia NCSP IE and T&E – p. 7
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IER-285
• This experiment was done to answer a request from SRNL for integral critical experiments with titanium in a thermal system
• This experiment series was done as a set of progressive fuel-rod-replacement experiments in the 7uPCX critical assembly
• We used titanium and aluminum replacement rods• A benchmark evaluation (LEU-COMP-THERM-097) has
been published in the International Handbook of Evaluated Criticality Safety Benchmark Experiments
• We are working on a set of experiments (IER-451) with titanium sleeves on another set of fuel rods (BUCCX)
Sandia NCSP IE and T&E – p. 8
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Case 1
Fuel RodEmpty Grid Location
Fuel 1457Expt. 0Empty 0Total 1457
Sandia NCSP IE and T&E – p. 9
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Case 16
Fuel RodEmpty Grid LocationAluminum Experiment Rod
Fuel 1429Expt. 36 AlEmpty 0Total 1465
Sandia NCSP IE and T&E – p. 10
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Case 8
Fuel RodEmpty Grid LocationTitanium Experiment Rod
Fuel 1573Expt. 36 TiEmpty 0Total 1609
Sandia NCSP IE and T&E – p. 11
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Case 18
Fuel RodEmpty Grid Location
Fuel 1037Expt. 0Empty 172Total 1209
Sandia NCSP IE and T&E – p. 12
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Case 19
Fuel RodEmpty Grid LocationAluminum Experiment Rod
Fuel 1097Expt. 36 AlEmpty 136Total 1269
Sandia NCSP IE and T&E – p. 13
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Case 24
Fuel RodEmpty Grid LocationTitanium Experiment Rod
Fuel 1485Expt. 36 TiEmpty 136Total 1657
Sandia NCSP IE and T&E – p. 14
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A comparison of the neutron spectrain the titanium rods
1 10 9 1 10 8
1 10 7 1 10 6
1 10 5 1 10 4
1 10 3 1 10 2
1 10 1 1 100
1 101 1 102
0 100
1 10 3
2 10 3
3 10 3
4 10 3
5 10 3
0.80 cm Pitch1.60 cm Pitch
Energy (MeV)
Nor
mal
ized
Let
harg
y Fl
ux
Sandia NCSP IE and T&E – p. 15
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A comparison of the capture ratein the titanium rods
1 10 9 1 10 8
1 10 7 1 10 6
1 10 5 1 10 4
1 10 3 1 10 2
1 10 1 1 100
1 101 1 102
0 100
5 10 3
1 10 2
1.5 10 2
0.80 cm Pitch1.60 cm Pitch
Energy (MeV)
Nor
mal
ized
Ti C
aptu
re R
ate
Sandia NCSP IE and T&E – p. 16
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The bottom line in the LCT097 evaluation
• 24 benchmark configurations– 17 at 0.8 cm pitch
• 1 with no experiment rods• 8 with aluminum experiment rods• 8 with titanium experiment rods
– 7 at 1.6 cm pitch• 1 with no experiment rods• The remainder with 36 Ti + Al experiment rods• 0, 4, 9, 16, 25, 36 titanium experiment rods
• Benchmark model keffs from 0.9991 to 0.9998• Overall uncertainties in keff of 0.0007 to 0.0011
Sandia NCSP IE and T&E – p. 17
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MCNP6.1.1 + ENDF/B-VII.0 Calculation of Benchmark Models
Expt. Ti 0 4 9 16 25 36 36 36 36 0 0 0 0 0 0 0 0 0 0 4 9 16 25 36 Ti Expt.Rods Al 0 0 0 0 0 0 0 0 0 4 9 16 25 36 36 36 36 0 36 32 27 20 11 0 Al Rods
Case 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 Case
Increasing TiIncreasing Al
Pitch Ti
Pitch Al
Ti Al
1.60.8
1.13 1.6 2.4
1.13
1.6
2.40.8
Experiment Rod Pitch (cm)
0 5 10 15 20 250.002
0.0015
0.001
0.0005
0
0.0005
0.001ENDF/B-VII.0
Case Number
Rea
ctiv
ity O
ffset
Sandia NCSP IE and T&E – p. 18
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Add ENDF/B-VII.1 cross sections
Expt. Ti 0 4 9 16 25 36 36 36 36 0 0 0 0 0 0 0 0 0 0 4 9 16 25 36 Ti Expt.Rods Al 0 0 0 0 0 0 0 0 0 4 9 16 25 36 36 36 36 0 36 32 27 20 11 0 Al Rods
Case 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 Case
0 5 10 15 20 250.002
0.0015
0.001
0.0005
0
0.0005
0.001ENDF/B-VII.0ENDF/B-VII.1
Case Number
Rea
ctiv
ity O
ffset Increasing Ti
Increasing Al
Pitch Ti
Pitch Al
Ti Al
1.60.8
1.13 1.6 2.4
1.13
1.6
2.40.8
Experiment Rod Pitch (cm)
Sandia NCSP IE and T&E – p. 19
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The experiments test changes to the Ti cross sections
0.05 0.04 0.03 0.02 0.01 00.0005
0
0.0005
0.001
0.0015ENDF/B-VII.0ENDF/B-VII.1
Titanium Reactivity
Tita
nium
to A
lum
inum
Rea
ctiv
ity D
iffer
ence
The 48Ti capture cross section was increased about 6% between ENDF/B-VII.0 and ENDF/B-VII.1
Sandia NCSP IE and T&E – p. 20
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Sandia Integral Experiment Requests
IER Title Sponsor CED
206 Re-establish the 4.3% Enriched Critical Experiment Capability at Sandia SNL 3B
209 7uPCX 0.855 cm Pitch, Variable Depth Pure Water Moderator SNL 3A
230 Characterize the Thermal Capabilities of the 7uPCX SNL 2
285 Titanium Cross Sections in a Thermal Application (7uPCX) SRNL
304 Temperature Dependent Critical Benchmarks ORNL 1
305 Critical Experiments with UO2 Rods and Molybdenum foils IRSN 1
306 Critical Experiments with UO2 Rods and Rhodium Foils IRSN 1
441 Epithermal HEX Lattices with SNL 7uPCX Fuel for Testing Nuclear Data ORNL 1
451 Titanium Cross Sections in a Thermal Application (BUCCX) SRNL 3B
452 Inversion Point of the Isothermal Reactivity Coefficient SNL Pre-1