activation analysis of the silene experiment with origen

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Activation Analysis of the SILENE Experiment with ORIGEN/MAVRIC

Cihangir Celik, Shane W.D. Hart, Georgeta Radulescu

Scale Users’ Group Workshop

ORNL August 19, 2019

22 SCALE Users’ Group Workshop, August 19, 2019

Outline

• Overview of SILENE Experiment• Fission Source Generation

– Brief description of KENO input

• Activation Source Generation– Brief description of COUPLE and ORIGEN input– How to use KENO output– Running and parsing results

• Dose Calculation– Brief description of MAVRIC input– Running and parsing results


Description of SILENE Experiment

• Conducted at SILENE critical assembly facility in Valduc, France.

• Goal was to measure neutron activation and TLD doses– Validation of codes and

dataMiller, T. M., et al. Neutron Activation and Thermoluminescent Detector Responses to a Bare Pulse of the CEA Valduc SILENE Critical Assembly. No. ORNL/TM-2015/462. Oak Ridge National Lab.(ORNL), 2016.


Objective

• Calculate total dose for the Collimator A TLD


How?

• Separate prompt and delayed particle transport

• Use Keno for fission source generation• Use MAVRIC for prompt neutron and gamma

transport• Use ORIGEN for activation and fission product

gamma sources• Use MAVRIC for delayed gamma transport

with ORIGEN generated sources • Combine prompt and delayed dose values

Model

MAVRIC(NP)

Fluxes

Origen

MAVRIC(P)

Results

KENO(N)

KENO

Fission Source Generation


KENO Model

• KENO output large (~7000 lines)

• Need to get flux and fission source– Flux direct from KENO– Fission source from mt2msm utility

• Open and show in Fulcrum

• Show output what we need


What we need from KENO?

• Produces a few things of interest:– Eigenvalue (~1)– Neutron fluxes in every region!– Fission source spatial and energy distribution for MAVRIC

ORIGEN

Activation Source Generation


ORIGEN Model• Data needed

– Neutron flux data for each region– Region wise material compositions– Time bins– Desired gamma source energy bins

• Run COUPLE to generate flux weighted library– Use KENO region neutron fluxes to generate libraries

• Run ORIGEN to generate gamma sources– Run for each material/region– Use COUPLE generated library– Use neutron flux in subcase control

• Use integrated flux data for each time bin– May enable Bremsstrahlung in relevant mediums

• only available in H2O and UO2

• Generates– region wise activation and fission product gamma sources


COUPLE Input

• COUPLE takes the flux from KENO

• COUPLE takes XS from JEFF library

• Combines to create ORIGEN library 𝑑𝑑𝑁𝑁��⃗𝑑𝑑𝑑𝑑

= �𝑨𝑨𝜎𝜎 ,𝑛𝑛𝛷𝛷𝑛𝑛 + 𝑨𝑨𝜆𝜆�𝑁𝑁��⃗ (𝑑𝑑) + 𝑆𝑆𝑛𝑛 , over time step 𝑑𝑑𝑛𝑛−1 ≤ 𝑑𝑑 ≤ 𝑑𝑑𝑛𝑛 .

𝑎𝑎𝑖𝑖𝑖𝑖 = �𝑙𝑙𝑖𝑖𝑖𝑖 𝜆𝜆𝑖𝑖 + 𝑓𝑓𝑖𝑖𝑖𝑖 𝜎𝜎𝑖𝑖𝛷𝛷 𝑖𝑖 ≠ 𝑖𝑖

−𝜆𝜆𝑖𝑖 − 𝜎𝜎𝑖𝑖𝛷𝛷 𝑜𝑜𝑑𝑑ℎ𝑒𝑒𝑒𝑒𝑒𝑒𝑖𝑖𝑒𝑒𝑒𝑒

Decay and reaction pieces are stored separately in f33later in ORIGEN, flux magnitude folded in


One-Group Cross Sections

𝑅𝑅 = 𝑁𝑁�0

∞𝜎𝜎 𝐸𝐸 Φ E 𝑑𝑑𝐸𝐸reaction

rate

multi-group weighting

function wg

≈ 𝑁𝑁�𝑔𝑔

𝜎𝜎𝑔𝑔Φ𝑔𝑔

=𝑁𝑁Φ∑𝑔𝑔 𝜎𝜎𝑔𝑔𝑒𝑒𝑔𝑔

∑𝑔𝑔𝑒𝑒𝑔𝑔

= 𝑁𝑁Φ𝜎𝜎

flux magnitude Φ (n/cm2s)

number density N

multi-group approximation


ORIGEN Input

• Uses SON input format (not FIDO! )

• Statements include:– Key=value pairs– { blocks }– [ arrays ]

• Stacked cases


ORIGEN Case

• Want to mimic the pulse

• Need to save spectra for use in MAVRIC

• Material taken from KENO

• Save concentrations at all time steps


ORIGEN Output

• Can have plots / text• Spectrum /

concentrations• Lots of options to control

MAVRIC

Dose Calculation


MAVRIC Model

• Data needed– Generated ORIGEN gamma sources– Material and geometry definitions

• Run MAVRIC to calculate the dose– Gamma-only simulation– All gamma sources can be put in a single MAVRIC model– Use region tallies for detector regions

• Generates– Contribution from the activation and fission product gammas to detector

• Add delayed responses to prompt for total dose


MAVRIC Model

• Multiple source definitions– fission neutrons from KENO– decay and activation gammas from ORIGEN

• Multiple response definitions– 115In (n, ɣ) 116In, 115In (n, n’ ɣ) 115mIn, 197Au (n, ɣ) 198Au, 59Co (n, ɣ) 60Co,

54Fe (n, p) 54Mn, 56Fe (n, p) 56Mn, 55Mn (n, ɣ) 56Mn, 58Ni (n, p) 58Co,24Mg (n, p) 24Na

• Variance reduction via CADIS/FW-CADIS method • Multiple region tallies

– optimize for TLD (Al2O3)


MAVRIC ModelTLD

Ti In Au Ni

Co Mg Fe

Foil holder

Collimator ATLD


Adjoint FluxTLD


MAVRIC Output

Reaction Activity(Bq/g)

Rel.Uncert.

C/E

59Co (n, ɣ) 60Co 7.31e+01 0.03 1.11115In (n, ɣ) 116In 9.18e+06 0.03 1.01115In (n, n’ ɣ) 115mIn 7.64e+03 0.02 0.9554Fe (n, p) 54Mn 2.16e-01 0.02 1.0556Fe (n, p) 56Mn + 55Mn (n, ɣ) 56Mn

2.39e+03 0.03 1.03

24Mg (n, p) 24Na 7.79e+01 0.03 1.2858Ni (n, p) 58Co 1.44e+01 0.02 1.00

Dose(Gy)

Rel.Uncert.

C/E

TLD 4.97e+00 0.09 0.75

Collimator A

• Benchmark results were in good agreement– Gamma dose underestimated persistently


MAVRIC Output

• Measured gamma dose 6.61 Gy• Prompt gamma dose 4.97 Gy• Delayed gamma dose ~0.95 Gy (practically all from fuel)• Delayed gamma dose ~20% of prompt & ~14% of measured

Region

T= 30 s T= 3 h TotalDose(Gy)

Rel.Uncert.

Dose(Gy)

Rel.Uncert.

Dose(Gy)

Rel.Uncert.

Fuel 9.50e-01 0.004 0.00e00 0.000 9.50e-01 0.004

Foils 2.12e-05 0.006 9.49e-06 0.003 3.07e-05 0.004

Other 7.65e-04 0.010 4.25e-04 0.012 1.19e-03 0.008

Total 9.51e-01 0.004 4.34e-04 0.012 9.51e-01 0.004

Collimator A - TLD

Q & A

• Questions?

activation analysis of the silene experiment with origen

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