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 UO_{2} fuel in stainless steel cladding in five different square lattice pitches.
ˇ WLRX Clusters of 19 rods made of 1.1% enriched UO_{2} 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 UO_{2} 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 
EIRMINOR 4.1 
nat 
3.56 
S 
D2O 
5 
x 
EXP 
minor4 15 
minor4 

37 
CH2 
UM 
B 
EIRMINOR 1.1 
nat 
2.692 
S 
D2O 
7 
x 
EXP 
minor1 17 
minor1 

39 
CH3 
UM 
B 
EIRMINOR 3.1 
nat 
2.00 
S 
D2O 
2 
x 
EXP 
minor3 12 
minor3 

40 
CH4 
UM 
B 
EIRMINOR 2.1 
nat 
2.00 
S 
D2O 
7 
x 
EXP 
minor2 17 
minor2 

103 
N3 
UO 
S 
IFANORA S1 
3 
1.128 
S 
D2O 
1 
x 
CRIT 
nd, d58 
norahw s1 
norahw 

104 
N4 
UO 
S 
IFANORA S2 
3 
1.128 
S 
D2O 
1 
x 
CRIT 
nd, d58 
norahw s2 
norahw 

105 
N5 
UO 
S 
IFANORA S3 
3 
1.128 
S 
D2O 
1 
x 
CRIT 
nd, d58 
norahw s3 
norahw 

106 
N6 
UO 
S 
IFANORA S4 
3 
1.128 
S 
D2O 
1 
x 
CRIT 
nd, d58 
norahw s4 
norahw 

107 
N7 
UO 
S 
IFANORA S6 
3 
1.128 
S 
D2O 
1 
x 
CRIT 
nd, d58 
norahw s6 
norahw 

139 
UK1 
UO 
A 
C 
AEREDIMPLESGHW1 
1.1 
0.3" 
90 
air 
1 
x 
CRIT 
kinf 
dimpsghw1 
dimpsghw 
140 
UK2 
UO 
A 
C 
AEREDIMPLESGHW2 
1.1 
0.3" 
90 
D2O 
1 
x 
CRIT 
kinf 
dimpsghw2 
dimpsghw 
141 
UK3 
UO 
A 
C 
AEREDIMPLESGHW3 
1.1 
0.3" 
90 
H2O 
1 
x 
CRIT 
kinf 
dimpsghw3 
dimpsghw 
142 
UK4 
UO 
A 
C 
AEREDIMPLESGHW4 
1.1 
0.3" 
90 
80% D2O 
1 
x 
CRIT 
kinf 
dimpsghw4 
dimpsghw 
143 
UK5 
UO 
A 
C 
AEREDIMPLESGHW5 
1.1 
0.3" 
90 
60% D2O 
1 
x 
CRIT 
kinf 
dimpsghw5 
dimpsghw 
146 
US1 
UM 
A 
SRLUR7 
nat 
0.998" 
S 
D2O 
1 
x 
CRIT 
d58, df58 
srlur 7 
srlur 

147 
US2 
UM 
A 
SRLUR8 
nat 
0.998" 
S 
D2O 
1 
x 
CRIT 
d58, df58 
srlur 8 
srlur 

148 
US3 
UM 
A 
SRLUR9 
nat 
0.998" 
S 
D2O 
1 
x 
CRIT 
d58, df58 
srlur 9 
srlur 

149 
US4 
UM 
A 
SRLUR12 
nat 
0.998" 
S 
D2O 
1 
x 
CRIT 
d58, df58 
srlur 12 
srlur 

287 
US142 
UO 
A 
A 
WESTINGHOUSLRX 6.5x6.5 
1.1 
.043" 
19 
D2O 
1 
x 
CRIT 
d58, df58 
wlrx 65x65 
wlrx 
288 
US143 
UO 
A 
A 
WESTINGHOUSLRX 6.5x8.0 
1.1 
.043" 
19 
D2O 
1 
x 
CRIT 
d58, df58 
wlrx 65x80 
wlrx 
289 
US144 
UO 
A 
A 
WESTINGHOUSLRX 8.0x8.0 
1.1 
.043" 
19 
D2O 
1 
x 
CRIT 
d58, df58 
wlrx 80x80 
wlrx 
All benchmarks were analysed for k_{eff} uncertainty and (depending on data) on uncertainties in material and dimensional data.
WLUP ID 
Total keff uncertainty [pcm] 
Parameter varied 
minor 
(200) 
B^{2}, D_{2}O purity T and rho 
srlur 
400  800 
B^{2}, D_{2}O purity T and rho, Al comp., fuel rho and dimensions 
norahw 
230  720 
B^{2}, D_{2}O purity T and rho 
wlrx 
200  450 
B^{2}, D_{2}O purity T and rho 
dimpsghw 
(150  450) 
B^{2} 
NORARESREXP001
CRITBUCKRRATE
Date: between August 1960 and February 1963
Experiments were carried out in the NORA zeropower critical facility with a core of 3% enriched SSclad fuel elements and heavy water moderator. For all lattices measured B^{2} with experimental error is reported and for some also r_{28}, the ratio of neutron captures in ^{238}U above Cd cutoff and below, and d^{28}, the ratio between fission rates in ^{238}U and ^{235}U. The d^{28} was measured in different facility (the fuel elements were taken to JEEPNIK core for d^{28} determination).
References:
1. Sheets N3 to N7
2. K. BryhnIngebrigtsen, et al., Heavy Water Lattices: 2^{nd} Pannel, IAEA 1963, p.251254
3. S. O. Larvin, et al., Exponential and Critical Experiments Vol. II: Symposium, IAEA 1964, p.161179
MINORRESREXP001 to 004
SUBBUCK
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 B_{m}^{2} 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.5983
3. H. R. Lutz, et al., Exponential and Critical Experiments Vol. II: Symposium, IAEA 1964, p.85108
PDPRESR EXP001
CRITBUCKRRATE
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 LiAl poison rods to the outer regions of tank.
Single rod configurations with lattice numbers 17, 18, 19 and 112 (SRLUR7 to SRLUR12) 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.341347 (1962)
LRXRESREXP001
CRITBUCKSPECCOEFRRATEPOWDIS
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 B^{2} measurements.
DIMPLEHWREXP001
CRITBUCKSPECRRATE
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.