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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

 

2.1 Processed benchmarks

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.


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