WIMS Library Update Project |
Burnup benchmarks
D2O-moderated
uranium oxide lattices.
Analysis of Isotopic Composition as function of burnup
Laboratory: AECL Atomic Energy of Canada Limited (Canada)
Facility: NPD Nuclear Power Demonstration reactor
NPD is a Canadian demonstration PHWR (25 MW electrical power) shut
down on 1987. The moderator and coolant were heavy water. The fuel
was in the form of 19 natural UO2 rod CANDU type clusters.
Isotopic measurements of irradiated 19 element fuel bundles
have been done
in 1971 at the CEA in France. The measurements included a series of eight
bundles with irradiation in the range 1000-10000 MWd/TU which were analysed
by mass-spectroscopy.
Pitch (cm) | 26.035 (square) |
Coolants | D2O |
Moderator | D2O |
Number of rods | 19 (1/6/12) |
Radius of rod centers (cm) | 0.0/1.65/3.18755 |
Angular dist.from reference axis (radians) | 0.0/0.0/0.2617994 |
Fuel material | UO2-nat |
Density of fuel material (g/cm2) | 10.0704 |
Radius of fuel rods (cm) | 0.71247 |
Sheath material | Zry-2 |
Density of sheath material (g/cm3) | 6.57 |
Internal radius of sheath (cm) | 0.71505 |
Thickness of sheath (cm) | 0.04191 |
Material of pressure tube | Zry-2 |
Density of pressure Tube (g/cm3) | 6.556 |
Internal radius of pressure tube (cm) | 4.1402 |
Thickness of pressure tube (cm) | 0.4318 |
Material of calandria tube | 57S Al alloy |
Density of calandria Tube (g/cm3) | 2.68 |
Internal radius of calandria tube (cm) | 5.08 |
Thickness of calandria tube (cm) | 0.12827 |
Effective fuel Temperature (K) | 778.2 |
Effective coolant Temperature (K) | 531.7 |
Temperature of moderator (K) | 311.0 |
Experimental buckling (1/cm2) | 0.000173 |
2) NEA Burnup Credit Criticality Benchmark
LWR-Burnup credit criticality benchmark. Isotopic composition prediction
Laboratory: Pacific Northwest Laboratory, Richland, Washington (USA)
Facility: ATM-104 Approved Testing Material, Combustion Engineering (CE) 14x14This benchmark compares the computed nuclide inventories for a simple pin cell
calculation. The fuel and operating specifications are based on data given
in the references for the Combustion Engineering (CE) 14 x 14 assembly designated
as Approved Testing Material ATM-104, for a series of experiments designed to
characterize spent fuel for light water reactors. The chemical assay data measured
in these experiments are of particular value in validating the isotopic predictions
used
in burnup credit.
Data
Cell radius (cm) | 0.879346 |
Moderator | H2O |
Moderator Density (g/cm3) | 0.7569 |
Moderator Temperature (K) | 558 |
Fuel material | UO2 (3% at. U235 enrichment) |
Density of fuel material (g/cm3) | 10.045 |
Effective fuel Temperature (K) | 841 |
Radius of fuel rods (cm) | 0.47815 |
Clad material | Zry-2 |
Density of clad material (g/cm3) | 6.55 |
Internal radius of clad (cm) | 0.493 |
Thickness of clad (cm) | 0.066 |
Clad Temperature (K) | 620 |
Cycle
1 avg boron concentration (ppm) |
331 |
Operating history data for isotopic calculation
OPERATING CYCLE | BURN
[days] |
DOWN
[days] |
BORON [% cycle 1] |
1 | 306.0 | 71.0 | 100.0 |
2 | 381.7 | 83.1 | 141.9 |
3 | 466.0 | 85.0 | 152.3 |
4 | 461.1 | 1870.0 | 148.8 |
BURN is the fuel irradiation time
DOWN is the downtime between
cycles except for cycle 4 where it
includes the decay time from reactor to measurement (cooling time)
BORON is the cycle-average
boron concentration as a percent of
the cycle 1 concentration
Specific power
OPERATING CYCLE |
Specific
Power [Kw/kgU] |
||
Sample 1 | Sample 2 | Sample 3 | |
1 | 17.24 | 24.72 | 31.12 |
2 | 19.43 | 26.76 | 32.51 |
3 | 17.04 | 22.84 | 26.20 |
4 | 14.57 | 18.87 | 22.12 |
Cumulative Burnup [GWd/MTU] |
27.35 | 37.12 | 44.34 |
Initial fuel number densities
Nuclide | Number
Density atoms/(barn.cm) |
U-234 | 6.15165E-06 |
U-235 | 6.89220E-04 |
U-236 | 3.16265E-06 |
U-238 | 2.17104E-02 |
C-12 | 9.13357E-06 |
N-14 | 1.04072E-05 |
O | 4.48178E-02 |
Cycle 1 coolant number densities
Nuclide | Number
Density atoms/(barn.cm) |
H-1 | 5.06153E-02 |
O-16 | 2.53076E-02 |
B-10 | 2.75612E-06 |
B-11 | 1.11890E-05 |
LWR-Pu
recycling benchmarks
These numerical benchmarks compare the computed nuclide inventories for simple
pin
cell calculations, for two cases:
A) highly degraded plutonium, and
B) normal recycled plutonium.
Reference results Isotopic concentrations (mg/g fuel) on the fuel pin for:
U-234, U-235,U-236, U-238, Np-237, Pu-238, Pu-239, Pu-240,
Pu-241,Pu-242, Am-241,
Am-242m,Am-243, Cm-242, Cm-243, Cm-244, Cm-245, Mo-95, Tc-99, Ru-101,
Rh-103,
Pd-105, Pd-107,Pd-108, Ag-109, Xe-131, Xe-135, Cs-133, Cs-135, Nd-143, Nd-145, Pm-147,
Pm-148m,Sm-149, Sm-150, Sm-151, Sm-152, Eu-153, Eu-154, Eu-155,
for cases A and B, at 50 GWd/MTU burnup.
Calculated ParametersIsotopic
concentrations (mg/g fuel) on the fuel pin for:
U-234, U-235,
U-236, U-238, Np-237, Pu-238, Pu-239, Pu-240, Pu-241,Pu-242, Am-241,
Am-242m, Am-243, Cm-242, Cm-243, Cm-244, Mo-95,
Tc-99, Ru-101, Rh-103, Pd-105,
Pd-107, Pd-108, Ag-109, Xe-131, Xe-135, Cs-133, Cs-135, Nd-143, Nd-145, Pm-147,
Pm-148m, Sm-149, Sm-150, Sm-151, Sm-152, Eu-153,Eu-154, Eu-155
for cases A and B, at 50 GWd/MTU burnup.
Data
Pitch (cm) |
1.3133 (square) |
Moderator |
H2O(+Bnat) |
579 |
|
Fuel material |
UO2-PuO2 |
Effective fuel Temperature (K) |
933 |
Radius of fuel rods (cm) |
0.4095 |
Clad material |
Zr |
0.043248 |
|
Radius of clad (cm) |
0.4750 |
Clad Temperature (K) |
579 |
Nuclide
|
Number
Density
atoms/(barn.cm) |
|
A
|
B
|
|
U-234
|
-
|
2.4626E-07
|
U-235
|
1.4456E-04
|
5.1515E-05
|
U-238
|
1.9939E-02
|
2.0295E-02
|
Pu-238
|
1.1467E-04
|
2.1800E-05
|
Pu-239
|
1.0285E-03
|
7.1155E-04
|
Pu-240
|
7.9657E-04
|
2.7623E-04
|
Pu-241
|
3.3997E-04
|
1.4591E-04
|
Pu-242
|
5.6388E-04
|
4.7643E-05
|
O
|
4.5851E-02
|
4.3100E-02
|
Nuclide | Number
Density atoms/(barn.cm) |
H-1 | 4.7716E-02 |
O-16 | 2.3858E-02 |
B-nat | 1.98606E-05 |