WIMS Library Update Project |
International Reactor Physics Experiments (IRPhE)
Heavy water benchmarks:
ˇ MINOR Single rods of natural uranium metal in several square lattice pitches. In this series four different fuel rods were used with different fuel radii and with cladding made of different types of aluminum alloys.
ˇ SRLUR Single rods of natural uranium metal in aluminum cladding in four different hexagonal lattices.
ˇ NORAHW Single rods of 3% enriched UO2 fuel in stainless steel cladding in five different square lattice pitches.
ˇ WLRX Clusters of 19 rods made of 1.1% enriched UO2 fuel in aluminum cladding closed in single aluminum housing. Three different lattice pitches have buckling values reported.
ˇ DIMPSGHW Clusters of 90 rods made of 1.14% enriched UO2 fuel in aluminum cladding closed inside pressure and calandria tubes. Benchmarks with five different types of coolant were performed. (Unreliable material data and two different set of buckling values reported).
HWL Benchmark Cases Details
Page num. |
Sheet ID |
Fuel |
Clad |
Shroud |
LATTICE IDENTIFICATION |
Enrichment |
Fuel Dia. [cm] |
S.- Cluster |
Coolant |
Num. Pitch |
B2 |
Type of experiment |
Measurements |
WLUP ID |
WIMS input name (.win) |
36 |
CH1 |
UM |
A |
EIR-MINOR 4.1 |
nat |
3.56 |
S |
D2O |
5 |
x |
EXP |
minor4 1-5 |
minor4 |
||
37 |
CH2 |
UM |
B |
EIR-MINOR 1.1 |
nat |
2.692 |
S |
D2O |
7 |
x |
EXP |
minor1 1-7 |
minor1 |
||
39 |
CH3 |
UM |
B |
EIR-MINOR 3.1 |
nat |
2.00 |
S |
D2O |
2 |
x |
EXP |
minor3 1-2 |
minor3 |
||
40 |
CH4 |
UM |
B |
EIR-MINOR 2.1 |
nat |
2.00 |
S |
D2O |
7 |
x |
EXP |
minor2 1-7 |
minor2 |
||
103 |
N3 |
UO |
S |
IFA-NORA S1 |
3 |
1.128 |
S |
D2O |
1 |
x |
CRIT |
nd, d58 |
norahw s1 |
norahw |
|
104 |
N4 |
UO |
S |
IFA-NORA S2 |
3 |
1.128 |
S |
D2O |
1 |
x |
CRIT |
nd, d58 |
norahw s2 |
norahw |
|
105 |
N5 |
UO |
S |
IFA-NORA S3 |
3 |
1.128 |
S |
D2O |
1 |
x |
CRIT |
nd, d58 |
norahw s3 |
norahw |
|
106 |
N6 |
UO |
S |
IFA-NORA S4 |
3 |
1.128 |
S |
D2O |
1 |
x |
CRIT |
nd, d58 |
norahw s4 |
norahw |
|
107 |
N7 |
UO |
S |
IFA-NORA S6 |
3 |
1.128 |
S |
D2O |
1 |
x |
CRIT |
nd, d58 |
norahw s6 |
norahw |
|
139 |
UK1 |
UO |
A |
C |
AERE-DIMPLE-SGHW1 |
1.1 |
0.3" |
90 |
air |
1 |
x |
CRIT |
kinf |
dimpsghw1 |
dimpsghw |
140 |
UK2 |
UO |
A |
C |
AERE-DIMPLE-SGHW2 |
1.1 |
0.3" |
90 |
D2O |
1 |
x |
CRIT |
kinf |
dimpsghw2 |
dimpsghw |
141 |
UK3 |
UO |
A |
C |
AERE-DIMPLE-SGHW3 |
1.1 |
0.3" |
90 |
H2O |
1 |
x |
CRIT |
kinf |
dimpsghw3 |
dimpsghw |
142 |
UK4 |
UO |
A |
C |
AERE-DIMPLE-SGHW4 |
1.1 |
0.3" |
90 |
80% D2O |
1 |
x |
CRIT |
kinf |
dimpsghw4 |
dimpsghw |
143 |
UK5 |
UO |
A |
C |
AERE-DIMPLE-SGHW5 |
1.1 |
0.3" |
90 |
60% D2O |
1 |
x |
CRIT |
kinf |
dimpsghw5 |
dimpsghw |
146 |
US1 |
UM |
A |
SRL-UR-7 |
nat |
0.998" |
S |
D2O |
1 |
x |
CRIT |
d58, df58 |
srlur 7 |
srlur |
|
147 |
US2 |
UM |
A |
SRL-UR-8 |
nat |
0.998" |
S |
D2O |
1 |
x |
CRIT |
d58, df58 |
srlur 8 |
srlur |
|
148 |
US3 |
UM |
A |
SRL-UR-9 |
nat |
0.998" |
S |
D2O |
1 |
x |
CRIT |
d58, df58 |
srlur 9 |
srlur |
|
149 |
US4 |
UM |
A |
SRL-UR-12 |
nat |
0.998" |
S |
D2O |
1 |
x |
CRIT |
d58, df58 |
srlur 12 |
srlur |
|
287 |
US142 |
UO |
A |
A |
WESTINGHOUS-LRX 6.5x6.5 |
1.1 |
.043" |
19 |
D2O |
1 |
x |
CRIT |
d58, df58 |
wlrx 65x65 |
wlrx |
288 |
US143 |
UO |
A |
A |
WESTINGHOUS-LRX 6.5x8.0 |
1.1 |
.043" |
19 |
D2O |
1 |
x |
CRIT |
d58, df58 |
wlrx 65x80 |
wlrx |
289 |
US144 |
UO |
A |
A |
WESTINGHOUS-LRX 8.0x8.0 |
1.1 |
.043" |
19 |
D2O |
1 |
x |
CRIT |
d58, df58 |
wlrx 80x80 |
wlrx |
All benchmarks were analysed for keff uncertainty and (depending on data) on uncertainties in material and dimensional data.
WLUP ID |
Total keff uncertainty [pcm] |
Parameter varied |
minor |
(200) |
B2, D2O purity T and rho |
srlur |
400 - 800 |
B2, D2O purity T and rho, Al comp., fuel rho and dimensions |
norahw |
230 - 720 |
B2, D2O purity T and rho |
wlrx |
200 - 450 |
B2, D2O purity T and rho |
dimpsghw |
(150 - 450) |
B2 |
NORA-RESR-EXP-001
CRIT-BUCK-RRATE
Date: between August 1960 and February 1963
Experiments were carried out in the NORA zero-power critical facility with a core of 3% enriched SS-clad fuel elements and heavy water moderator. For all lattices measured B2 with experimental error is reported and for some also r28, the ratio of neutron captures in 238U above Cd cut-off and below, and d28, the ratio between fission rates in 238U and 235U. The d28 was measured in different facility (the fuel elements were taken to JEEPNIK core for d28 determination).
References:
1. Sheets N3 to N7
2. K. Bryhn-Ingebrigtsen, et al., Heavy Water Lattices: 2nd Pannel, IAEA 1963, p.251-254
3. S. O. Larvin, et al., Exponential and Critical Experiments Vol. II: Symposium, IAEA 1964, p.161-179
MINOR-RESR-EXP-001 to 004
SUB-BUCK
Date: between January and September 1963
MINOR subcritical exponential facility consisted of experimental tank 140 cm in diameter and 280 cm high filled with heavy water. Fuel rods inside the tank are suspended from above. Measurements were started with "reference lattices", completely filled with one type of fuel. In the next step the two zone measurements were performed. First set of measurements is considered in this benchmark with three different types of fuel (MINOR, DIORIT and AQUILON). For all lattices the Bm2 was measured and reported with error interval.
The MINOR facility is very well documented with all necessary data needed to evaluate the subcritical exponential benchmarks.
References:
1. Sheets CH1 to CH4
2. R. W. Meier, et al., Exponential and Critical Experiments Vol. II: Symposium, IAEA 1964, p.59-83
3. H. R. Lutz, et al., Exponential and Critical Experiments Vol. II: Symposium, IAEA 1964, p.85-108
PDP-RESR- EXP-001
CRIT-BUCK-RRATE
Date: before 1961
PDP facility at Savannah River Laboratory (SRL) was SS tank 16 ft 2 3/4 inch in diameter. It was filled with different single rods or clusters and the moderator height was adjusted to critical level. In the radial direction the pile could be reduced with adding Li-Al poison rods to the outer regions of tank.
Single rod configurations with lattice numbers 1-7, 1-8, 1-9 and 1-12 (SRL-UR-7 to SRL-UR-12) are processed in this batch. The same rods were also used for cluster experiments.
References:
1. Sheets US1 to US4
2. T. J. Hurley, et al., Nuclear Science and Engineering: 12, p.341-347 (1962)
LRX-RESR-EXP-001
CRIT-BUCK-SPEC-COEF-RRATE-POWDIS
Date:
WAPD Westinghouse Atomic Power Division, LRX Facility
The cluster consists of 19 fuel rods arranged in hexagonal geometry with rod to rod spacing 0.60". 19 rods make up one fuel assembly surrounded with one Al cluster tube. Fuel assemblies were studied in core tank (126" I.D., 139.6" depth) in three different square lattice pitches and two different enrichments.
Core configuration with 2% enrichment has no B2 measurements.
DIMPLE-HWR-EXP-001
CRIT-BUCK-SPEC-RRATE
Date:1960 - 1961
Bz and Br bucklings were measured and Lu/Mn reaction rates. From these the delta28 and rho28 were determined. Also kinf value was measured.