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H2O-moderated uranium oxide critical lattices (UO2-LW/CRITUO2)


2.01) UO2-LW-BAPL-TRX

H2O-moderated uranium oxide critical lattices

Laboratory: BAPL Bettis Atomic Power Laboratory, Westinghouse (USA)

Facility: TRX

These benchmarks are three standard (BAPL/1-3) and three additional (BAPL/4-6)
cases of H2O moderated lattices with slightly enriched uranium oxide rods in a
triangular pattern. Material bucklings and several spectral indexes were measured.

Pitch (cm) bapl_trx1: 1.5578
bapl_trx2: 1.6523
bapl_trx3: 1.8057
bapl_trx4: 2.20
bapl_trx5: 2.36
bapl_trx6: 2.51
Lattice geometry Hexagonal
Water/fuel volume ratio bapl_trx1: 1.43
bapl_trx2: 1.78
bapl_trx3: 2.40
bapl_trx4: 1.07
bapl_trx5: 1.40
bapl_trx6: 1.76
Moderator H2O
Fuel material UO2 (1.311 w% enrichment)
Fuel Isotopic Concentration
(atoms/barn.cm)
O:0.046946
U-235: 0.0003112
U-238: 0.023127
Radius of fuel rods (cm) bapl_trx1-3: 0.4864
bapl_trx4-6: 0.7635
Clad material Al
Clad Isotopic Concentration
(atoms/barn.cm)
Al: 0.06025
Outer radius of clad (cm) bapl_trx1-3: 0.5753
bapl_trx4-6: 0.8465
Thickness of clad (cm) 0.0711
Temperatura (K) 293.0
Experimental buckling
(1/cm2)
bapl_1: 0.003259 0.000015
bapl_2: 0.003547 0.000015
bapl_3: 0.003422 0.000013
bapl_4: 0.002837 0.000060
bapl_5: 0.003017 0.000060
bapl_6: 0.002906 0.000070

References

[1] HELLENS, R.L., PRICE, G.A., Reactor Physics Data for Water-Moderated Lattices of
Slightly Enriched Uranium Reactor Technology Selected Reviews, 529, 1964.

[2] BROWN,
J.R., HARIS, D.R. et al., Kinetics and Buckling Measurements on Lattices of
Slightly Enriched Uranium and UO2 Rods in light Water, WAPD-176, January 1958.

[3] BERNOCCHI, E., MARTINELLI, R., (editors), Light Water Lattice Data,
pages 7-9,
Comitato Nazionale per LEnergia Nucleare, Dipartamento Ricerca Tecnologica di Base
ed Avanzata, Quaderno RIT/FIS(77)1,NEACRP-U-190 (1977).


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2.02) UO2-LW-AEEW-DIMPLE

H2O-moderated uranium oxide lattices enriched to 3.003 w% in U-235

Laboratory: AEEW Atomic Energy Establishment, Winfrith (UK)

Facility: DIMPLE

These benchmarks are three H2O moderated lattices of UO2 fuel rods clad in
stainless steel and enriched to 3.003 wt.% in U-235, arranged in square patterns.
The gap between the clad and fuel region contained an aluminum wrapper for
the fuel. Material bucklings were measured. d28 and RCR (spectral indexes) were
measured also for R1/100H and R3/100H.

Pitch (cm) R1100H: 1.3200
R2100H: 1.8660
R3100H: 1.2506
Lattice geometry Square
Water/Fuel volume ratio R1100H: 1.001
R2100H: 3.163
R3100H: 0.779
Moderator H2O
Fuel material UO2 (3.003 w% enrichment)
Fuel Isotopic Concentration
(atoms/barn.cm)
O:0.04659
U-235: 0.0007082
U-238: 0.02259
Radius of fuel rods (cm) 0.506
Wrapper material Al
Outer radius of wrapper (cm) 0.51955
Clad material stainless steel
Clad Density (g/cm3) 8.293
Outer radius of clad (cm) 0.54625
Thickness of clad (cm) 0.0267
Temperature (K) 293.0
Experimental buckling
(1/cm2)
R1100H: 0.006600 0.000022
R2100H: 0.010044 0.000064
R3100H: 0.005096 0.000030

References

[1] BROWN, W.A.V., FOX, W.N., SKILLINGS, D.J., GEORGE, C.F., BURHOLT, G.D.,
Measurements of Material Buckling and Detailed Reaction Rates in a Series of Low
Enrichment UO2 Fuelled Cores Moderated by Light Water, UKAEA Report AEEW-R502 (1967).


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2.03) UO2-LW-NAIG-NCA

H2O-moderated uranium oxide critical lattice

Laboratory: NAIG Nippon Atomic Industries Group (Japan)

Facility: NCA

This benchmark is an H2O moderated lattice of 2.02 w% enriched uranium oxide rods
in a square pattern. Material buckling was measured.

Pitch (cm) 1.84 (square)
Water/fuel volume ratio 2.918
Moderator H2O
Fuel material UO2 (2.02 w% enrichment)
Fuel Density (g/cm3) 10.37
Radius of fuel rods (cm) 0.50
Clad material Al
Clad Density (g/cm3) 2.6999
Outer radius of clad (cm) 0.59
Thickness of clad (cm) 0.08
Temperature (K) 293.0
Experimental buckling
(1/cm2)
0.006972 0.000136

References

[1] MIZUTA, H., MAKINO, K., Few Group Diffusion Calculations of a Light Water
Moderated lattice, J.Nucl.Sci.Technol.,8,4,201 (1971).

[2] BERNOCCHI, E., MARTINELLI, R. (editors), Light Water Lattice Data, page 13,
Comitato Nazionale per LEnergia Nucleare, Dipartamento Ricerca Tecnologica di Base
ed Avanzata, Quaderno RIT/FIS(77)1,NEACRP-U-190 (1977).


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2.04) UO2-LW-CURL-ZPR

H2O-moderated uranium oxide critical lattices

Laboratory: CURL Cornell University Nuclear Reactor Laboratory (USA)

Facility: ZPR

These benchmarks are four H2O moderated lattices of 2.07 w% enriched uranium oxide
rods in a triangular pattern. Material bucklings were measured. d28 was measured for
CURL_ZPR3 only.

Pitch (cm) curl_zpr1: 2.174
curl_zpr2: 2.616
curl_zpr3: 2.990
curl_zpr4: 3.325
Lattice geometry Hexagonal
Water/fuel volume ratio curl_zpr1: 1.012
curl_zpr2: 2.017
curl_zpr3: 3.011
curl_zpr4: 4.016
Moderator H2O
Fuel material UO2 (2.07 w% enrichment)
Fuel Density (g/cm3) 10.382
Radius of fuel rods (cm) 0.762
Clad material 6061-76 Al
Clad Density (g/cm3) 2.6999
Outer radius of clad (cm) 0.846
Thickness of clad (cm) 0.071
Temperature (K) 293.0
Experimental buckling
(1/cm2)
curl_zpr1: 0.00576 0.00030
curl_zpr2: 0.00832 0.00020
curl_zpr3: 0.00748 0.00055
curl_zpr4: 0.00606 0.00035

References

[1] BERG, S.S., Initial Experiments on the Cornell University Zero Power Reactor Cores
CURL-7, Cornell University Nuclear Reactor Laboratory (1964).

[2] FEHR, E.B., BRYCE, D.H., Reactivity Values in Central Water and Air in the ZPR
RM-17, Cornell University Nuclear Reactor Laboratory (1964).

[3] WYNN, W.P., Experimental Determination of the Isothermal Temperature Coefficients of
Reactivity and Temperature Dependent Disadvantage Factors of the Cornell University

ZPR CURL-11, Cornell University Nuclear Reactor Laboratory (1964).


[
4] OSIAS, D.J., Investigation of Space Dependent Fast Fission Ratios and Measurements of
Fission Fragment Recoil Ranges in Aluminium, CURL-23, Cornell University Nuclear
Reactor
Laboratory (1967).

[5] BERNOCCHI, E., MARTINELLI, R. (editors), Light Water Lattice Data, pages 14,16-18
Comitato Nazionale per LEnergia Nucleare, Dipartamento Ricerca Tecnologica di Base

ed Avanzata, Quaderno RIT/FIS(77)1,NEACRP-U-190 (1977).


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2.05)UO2-LW-BAW-BAY2

H2O-moderated uranium oxide critical lattices

Laboratory: BAW Babcock & Wilcox Company (USA)

Facility: BAY-2

These benchmarks are three H2O moderated lattices of enriched uranium oxide rods
in a square pattern. Material bucklings and r28 were measured.

Pitch (cm) baw_bay2a: 1.5113
baw_bay2b1: 1.4503
baw_bay2b2: 1.5113
Lattice geometry Square
Water/fuel volume ratio baw_bay2a: 1.3710
baw_bay2b1: 0.959
baw_bay2b2: 1.140
Moderator H2O
Fuel material UO2
baw_bay2a: 2.459w% enr.
baw_bay2b: 4.020w% enr.
Fuel Density (g/cm3) baw_bay2a: 10.24
baw_bay2b: 9.46
Radius of fuel rods (cm) baw_bay2a: 0.5150
baw_bay2b: 0.5639
Clad material baw_bay2a: 6061 al
baw/bay2b: 304-ss
Outer radius of clad (cm) baw_bay2a: 0.6030
baw_bay2b: 0.6039
Thickness of clad (cm) baw_bay2a: 0.0813
baw_bay2b: 0.0406
Temperature (K) baw_bay2a,b1: 295
baw_bay2b2: 288
Experimental buckling
(1/cm2)
baw_bay2a: 0.00701 0.00007
baw_bay2b1: 0.00790 0.00010
baw_bay2b2: 0.00880 0.00004

References

[1] ENGELDER, T.C. et al., Measurements and Analysis of Uniform Lattices of Slightly
Enriched UO2 Moderated by D2O-H2O Mixtures, USAEC Report BAW-3647-3, The

Babcock & Wilson Company, Virginia (1967).

[2] BARRET, L.G. et al.,Exponential Experiments at Elevated Temperatures on Lattices
Moderated by D2O-H2O
Mixtures, USAEC Report BAW-1233, The Babcock&Wilson Company,
Virginia (1962).


[3] BERNOCCHI, E., MARTINELLI, R. (editors), Light Water Lattice Data, pages 20,75,76

Comitato Nazionale per LEnergia Nucleare, Dipartamento Ricerca Tecnologica di Base

ed Avanzata, Quaderno RIT/FIS(77)1,NEACRP-U-190 (1977).


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2.06) UO2-LW-BAW-CX10

H2O-moderated uranium oxide critical lattice

Laboratory: BAW Babcock & Wilcox Company (USA)

Facility: CX-10

This benchmark is an H2O moderated lattice of 2.459 w% enriched uranium oxide
rods in a square pattern. Material buckling and r28 were measured.

Pitch (cm) 1.6358 (square)
Water/Fuel volume ratio 1.841
Moderator H2O
Fuel material UO2 (2.459 w% enr.)
Fuel Density (g/cm3) 10.24
Radius of fuel rods (cm) 0.515
Clad material 6061-Al
Outer radius of clad (cm) 0.603
Thickness of clad (cm) 0.0813
Temperature (K) 294
Experimental buckling
(1/cm2)
0.00861 0.00004
References

[1] CLARK, R.H. et al., Lumped Burnable Poison Program - Final Report USAEC Report
BAW-3492-1, The Babcock & Wilson Company, Virginia (1966).


[2] CLARK, R.H. et al., Physics Verification Program Part III, Tasks 2 and 3 Final Report

USAEC Report BAW-3647-3, The Babcock & Wilson Company, Virginia (1967).

[3] BALDWIN, M.N. et al., Physics Verification Program - Part II, Final Report USAEC
Report BAW-3647-7, The Babcock & Wilson Company, Virginia (1968).

[4] BALDWIN, M.N. et al., Physics Verification Program Part III, Tasks 2 and 3 Final Report
USAEC Report BAW-3647-16, The Babcock & Wilson Company, Virginia (1970).

[5] BALDWIN, M.N., STERN, M.E., Physics Verification Program - Part III, Task 4,
Summary Report USAEC Report BAW-3647-20, The Babcock & Wilson Company,
Virginia (1971).

[6] BERNOCCHI, E., MARTINELLI, R. (editors), Light Water Lattice Data, page 21,
Comitato Nazionale per LEnergia Nucleare, Dipartamento Ricerca Tecnologica di Base
ed Avanzata, Quaderno RIT/FIS(77)1,NEACRP-U-190 (1977).


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2.07) UO2-LW-AERL-OCF

H2O-moderated uranium oxide critical lattices

Laboratory: AERL Atomic Energy Research Laboratory, Ozeny (Japan)

Facility: OCF

These benchmarks are two H2O moderated lattices of 2.49 w% enriched uranium oxide
rods in a square pattern. Material bucklings, r28 and d28 were measured.

Pitch (cm) aerl_ocf1: 1.77
aerl_ocf2: 1.98
Lattice geometry Square
Water/fuel volume ratio aerl_ocf1: 2.50
aerl_ocf2: 3.50
Moderator H2O
Fuel material UO2 (2.49 w% enr.)
Fuel Density (g/cm3) 10.4
Radius of fuel rods (cm) 0.50
Clad material Al
Clad Density (g/cm3) 2.6999
Outer radius of clad (cm) 0.61
Thickness of clad (cm) 0.08
Temperature (K) 291
Experimental buckling
(1/cm2)
aerl_ocf1: 0.00855 0.00007
aerl_ocf2: 0.00834 0.00048

References

[1] WAJIMA, J.T. et al., Experimental Studies of UO2-H2O Uniform Lattices,
J.Nucl.Sci.Technol.,8,4,201 (1971).

[2] WAJIMA, J.T., YAMAMOTO, K., Temperature Coefficient of Water Lattices,
J.Nucl.Sci.Technol.,2,9,331 (1965).

[3] BERNOCCHI, E., MARTINELLI, R. (editors), Light Water Lattice Data, pages 25,26,
Comitato Nazionale per LEnergia Nucleare, Dipartamento Ricerca Tecnologica di Base

ed Avanzata, Quaderno RIT/FIS(77)1,NEACRP-U-190 (1977).


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2.08) UO2-LW-JAERI-TCA

H2O-moderated uranium oxide critical lattices

Laboratory: JAERI Japan Atomic Energy Research Institute,
Tokai Research Establishment (Japan)

Facility: TCA Tank type Critical Assembly

These benchmarks are seven H2O moderated lattices ofenriched uranium oxide rods
in square patterns. Material bucklings were measured.

Pitch (cm) jaeri_tca1: 1.660
jaeri_tca2: 1.725
jaeri_tca3: 1.820
jaeri_tca4: 1.849
jaeri_tca5: 1.956
jaeri_tca6: 2.150
jaeri_tca7: 2.930
Lattice geometry Square
Water/fuel volume ratio jaeri_tca1: 1.760
jaeri_tca2: 2.000
jaeri_tca3: 2.380
jaeri_tca4: 1.50
jaeri_tca5: 1.83
jaeri_tca6: 2.48
jaeri_tca7: 3.00
Moderator H2O
Fuel material UO2
jaeri_tca1-3: 2.588 w% enr.
jaeri_tca4-7: 2.596 w% enr.
Fuel Density (g/cm3) 10.40
Radius of fuel rods (cm) jaeri_tca1-3: 0.5355
jaeri_tca4-7: 0.6250
Clad material Al
Clad Density(g/cm3) 2.6999
Outer radius of clad (cm) jaeri_tca1-3: 0.6115
jaeri_tca4-7: 0.7085
Thickness of clad (cm) jaeri_tca1-3: 0.070
jaeri_tca4-7: 0.076
Temperature (K) jaeri_tca1,2: 294
jaeri_tca3: 289
jaeri_tca4-7: 293
Experimental buckling
(1/cm2)
jaeri_tca1: 0.00922
jaeri_tca2: 0.00964
jaeri_tca3: 0.01008
jaeri_tca4: 0.00833 0.0001
jaeri_tca5: 0.00943 0.00013
jaeri_tca6: 0.00983 0.00008
jaeri_tca7: 0.00952 0.00014
References

[1] TSURUTA, H. et al., Critical Sizes of Light-Water Moderated UO2 and PuO2-UO2
Lattices, JAERI-Memo 6568, Japan Atomic Energy Research Institute (1976).


[2] KOBAYASHI, I., HAYATA, K., JAERI-Memo 2861, Japan Atomic Energy Research

Institute (1967).

[3] BERNOCCHI, E., MARTINELLI, R. (editors), Light Water Lattice Data, pages 27-29,
Comitato Nazionale per LEnergia Nucleare, Dipartamento Ricerca Tecnologica di Base

ed Avanzata, Quaderno RIT/FIS(77)1,NEACRP-U-190 (1977).


[4] NUCLEAR ENERGY AGENCY, CRITICAL ARRAYS OF LOW-ENRICHED UO2
FUEL RODS WITH WATER-TO-FUEL VOLUME RATIOS RANGING FROM 1.5 TO

3.0, NEA/NSC/DOC/(95)03/IV, Volume IV, LEU-COMP-THERM-006, Nuclear Science

Committee, International Handbook of Evaluated Criticality Safety Benchmark

Experiments, September 2001 Edition, Nuclear Energy Agency, OECD (2001).


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2.09) UO2-LW-WAPD-CRX

H2O-moderated uranium oxide critical lattices

Laboratory: WAPD Westinghouse Atomic Power Department (USA)

Facility: CRX

These benchmarks are twelve H2O moderated lattices of enriched (from 2.7 w% to 5.74 w%)
uranium oxide rods in square patterns. Material bucklings and several spectral indexes
were measured.

Pitch (cm) wapd_crxa1: 1.0290
wapd_crxa2: 1.0617
wapd_crxa3: 1.1050
wapd_crxa4: 1.1940
wapd_crxa5: 1.2520
wapd_crxa6: 1.6890
wapd_crxb1: 1.0617
wapd_crxb2: 1.2520
wapd_crxc: 1.1050
wapd_crxd1: 1.3208
wapd_crxd2: 1.4224
wapd_crxd3: 2.0116
Lattice geometry Square
  Water/fuel volume ratio wapd_crxa1: 1.048
wapd_crxa2: 1.200
wapd_crxa3: 1.405
wapd_crxa4: 1.853
wapd_crxa5: 2.166
wapd_crxa6: 4.984
wapd_crxb1: 1.225
wapd_crxb2: 2.212
wapd_crxc: 1.346
wapd_crxd1: 1.502
wapd_crxd2: 1.934
wapd_crxd3: 5.067
Moderator H2O
Fuel material UO2
wapd_crxa: 2.7 w% enr.,
wapd_crxb: 3.7 w% enr.,
wapd_crxc: 4.43 w% enr.,
wapd_crxd: 5.742 w% enr.
Fuel Density (g/cm3) wapd_crxa: 10.18
wapd_crxb: 10.40
wapd_crxc: 10.17
wapd_crxd: 10.20
Radius of fuel rods (cm) wapd_crxa,c: 0.3810
wapd_crxb: 0.3770
wapd_crxd: 0.4534
Clad material 304 SS
Outer radius of clad (cm) wapd_crxa: 0.4295
wapd_crxb: 0.4298
wapd_crxc: 0.4395
wapd_crxd: 0.4965
Thickness of clad (cm) wapd_crxa,b: 0.0409
wapd_crxc:0.0550
wapd_crxd:0.0380
Temperature (K) wapd_crxa1-5,b: 293
wapd_crxa6:296
wapd_crxc:289
wapd_crxd1:292
wapd_crxd2:291
wapd_crxd3:290
Experimental buckling
(1/cm2)
wapd_crxa1: 0.00407 0.00004
wapd_crxa2: 0.00475 0.00004
wapd_crxa3: 0.00532 0.00007
wapd_crxa4: 0.00633 0.00004
wapd_crxa5: 0.00688 0.00005
wapd_crxa6: 0.00510 0.00005
wapd_crxb1: 0.00683 0.00003
wapd_crxb2: 0.00951 0.00007
wapd_crxc: 0.00797 0.00008
wapd_crxd1: 0.01176 0.00018
wapd_crxd2: 0.01271 0.00014
wapd_crxd3: 0.01368 0.00009

Refereences

[1] HELLENS, R.L., PRICE, G.A., Reactor Physics Data for Water Moderated Lattices of
Slightly Enriched Uranium Reactor Technology, Selected Reviews - 1964, USAEC-TID

8540, pp.529-609 (1964).

[2] DAVISON, P.W. et al., Yankee Critical Experiments-Measurements on Lattices of
Stainless Steel Clad Slightly Enriched Uranium Dioxide Fuel Rods in Light Water

USAEC Report YAEC-94, Westignhouse Electric Corporation, Atomic Power

Department (1959).

[3] EICH, W.J., KOVACK, W.P., Reactivity and Neutron Flux Distribution Studies in Multi-
Region Loaded Reactor Cores, USAEC Report WCAP-1433, Westignhouse Electric
Corporation, Atomic Power Department (1959).

[4] DAVISON, P.W. et al., Multi-Region Reactor Lattice Studies, Microscopic Lattice

Parameters in Single and Multi-Region Cores: A Comparison of Theory and Experiment,
USAEC Report WCAP-1434, Westignhouse Electric Corporation, Atomic Power

Department (1961).


[5] GROB, V.E. et al., Measurements of Parameters Leading to P28, f and eta in Light Water

Moderated 4.48% and 2.73% Enriched Lattices, Nucl.Sci.and Eng.,7,514 (1960).


[6] GROB, V.E. et al., Multi-Region Reactor Lattice Studies, Results of Critical Experiments

in Loose Lattices of UO2 Rods in H2O, USAEC Report WCAP-1412, Westignhouse

Electric Corporation, Atomic Power Department (1960).


[7] DAVISON, P.W. et al., Two-Region Critical Experiments with Water Moderated Slightly

Enriched UO2 Lattices, USAEC Report YAEC-142, Westignhouse Electric Corporation,

Atomic Power Department (1959).


[8] GROB, V.E. et al., Measurements of Parameters Leading to P, f and eta in a Water

Moderated 4.4% Enriched UO2 Lattices, USAEC Report WCAP-1175, Westignhouse

Electric Corporation, Atomic Power Department (1959).


[9] BERNOCCHI, E., MARTINELLI, R. (editors), Light Water Lattice Data, pages 35-
39,
42,71,72,78,83-85, Comitato Nazionale per LEnergia Nucleare, Dipartamento Ricerca

Tecnologica di Base ed Avanzata, Quaderno RIT/FIS(77)1,NEACRP-U-190 (1977).


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2.10) UO2-LW-AEEW-JUNO

H2O-moderated uranium oxide critical lattice

Laboratory: AEEW Atomic Energy Establishment, Winfrith (UK)

Facility: JUNO

This benchmark is an H2O moderated lattice of 3.003 w% enriched uranium
oxide rods in a hexagonal pattern. Material buckling was measured.

Pitch (cm) 1.87 (hexagonal)
Water/fuel volume ratio 2.597
Moderator H2O
Fuel material UO2 (3.003 w% enr.)
Fuel Density (g/cm3) 10.44
Radius of fuel rods (cm) 0.506
Clad material 18/8/1-SS
Outer radius of clad (cm) 0.54625
Thickness of clad (cm) 0.0267
Temperature (K) 293
Experimental buckling
(1/cm2)
0.01023 0.00009
References
[1] BERNOCCHI, E., MARTINELLI, R. (editors), Light Water Lattice Data, page 49,
Comitato Nazionale per LEnergia Nucleare, Dipartamento Ricerca Tecnologica di Base

ed Avanzata, Quaderno RIT/FIS(77)1,NEACRP-U-190 (1977).


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2.11) UO2-LW-BNL-BNLea

H2O-moderated uranium oxide critical lattices

Laboratory: BNL Brookhaven National laboratory (USA)

Facility: BNL Exponential Assemblies

These benchmarks are five H2O moderated lattices of 3.006 w% enriched uranium
oxide rods in hexagonal patterns. Material bucklings, r28 and d28 were measured.

Pitch (cm) bnluo2_1: 1.719
bnluo2_2: 1.819
bnluo2_3: 1.957
bnluo2_4: 2.169
bnluo2_5: 2.466
Lattice geometry Hexagonal
Water/fuel volume ratio bnluo2_1: 1.319
bnluo2_2: 1.632
bnluo2_3: 2.091
bnluo2_4: 2.863
bnluo2_5: 4.071
Moderator H2O
Fuel material UO2 (3.006 w%)
Fuel Density (g/cm3) 9.30
Radius of fuel rods (cm) 0.564
Clad material 304-SS
Outer radius of clad (cm) 0.6335
Thickness of clad (cm) 0.070
Temperature (K) 293
Experimental buckling
(1/cm2)
bnluo2_1: 0.005660 0.000050
bnluo2_2: 0.006581 0.000052
bnluo2_3: 0.007049 0.000060
bnluo2_4: 0.007022 0.000055
bnluo2_5: 0.006173 0.000051

References

[1] HELLENS, R.L., PRICE, G.A., Reactor Physics Data for Water Moderated Lattices of
Slightly Enriched Uranium Reactor Technology, Selected Reviews - 1964, USAEC-TID

8540, pp.529-609 (1964).


[2] PRICE, G.A., Uranium-Water Lattice Compilation Part I, BNL Exponential Assemblies

USAEC Report BNL 50035 (T-449) (Reactor Technology-4500), Brookhaven National

Laboratory (1966).


[3] WINDOSR, H.H., Buckling Measurements in Water-Moderated and Reflected

Exponential Experiments, Nucl.Sci.and Eng.,5,61 (1959).


[4] BERNOCCHI, E., MARTINELLI, R. (editors), Light Water Lattice Data, pages 51-55,

Comitato Nazionale per LEnergia Nucleare, Dipartamento Ricerca Tecnologica di Base

ed Avanzata, Quaderno RIT/FIS(77)1,NEACRP-U-190 (1977).




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2.12) UO2-LW-ANL-ZPR7

H2O-moderated uranium oxide critical lattices

Laboratory: ANL Argonne National laboratory (USA)

Facility: ZPR-7

These benchmarks are seven H2O moderated lattices of enriched uranium oxide rods in hexagonal
and square patterns. Material bucklings and some spectral indexes were measured.

Pitch (cm)

anl_zpr7a1: 1.166 (hexagonal)
anl_zpr7a2: 1.270 (hexagonal)
anl_zpr7a3: 1.240 (square)
anl_zpr7a4: 1.240 (square)
anl_zpr7a5: 1.349 (square)
anl_zpr7b1: 1.270 (hexagonal)
anl_zpr7b2: 1.270 (square)

Water/fuel volume ratio

anl_zpr7a1: 0.4347
anl_zpr7a2: 0.7544
anl_zpr7a3: 0.9596
anl_zpr7a4: 0.9620
anl_zpr7a5: 1.3710
anl_zpr7b1: 1.1410
anl_zpr7b2: 1.5040

Moderator

H2O

Fuel material

UO2
anl_zpr7a: 3.042 w%
anl_zpr7b: 4.950 w%

Fuel Density (g/cm3)

anl_zpr7a: 10.17
anl_zpr7b: 10.20

 

Radius of fuel rods (cm)

anl_zpr7a: 0.4675
anl_zpr7b: 0.4355

Clad material

anl_zpr7a1-3,5: 6061-T6Al
anl_zpr7a4,b: 304-SS

Outer radius of clad (cm)

anl_zpr7a1-3,5: 0.5290
anl_zpr7a4:0.5285
anl_zpr7b:0.4775

Thickness of clad (cm)

anl_zpr7a1-3,5: 0.0480
anl_zpr 7a4:0.0496
anl_zpr 7b:0.0381

Temperature (K)

293

Experimental buckling
(1/cm2)

anl_zpr7a1: 0.0024360.00001
anl_zpr7a2: 0.0055380.000024
anl_zpr7a3: 0.0070760.000071
anl_zpr7a4: 0.0047470.000027
anl_zpr7a5: 0.0091820.00008
anl_zpr7b1: 0.0091470.000068
anl_zpr7b2: 0.0107630.00019

References

[1] HELLENS, R.L., PRICE, G.A., Reactor Physics Data for Water Moderated Lattices of
Slightly Enriched Uranium React or Technology, Selected Reviews - 1964, USAEC-TID

8540, pp.529-609 (1964).


[2] PRICE, G.A., Uranium-Water Lattice Compilation Part I, BNL Exponential Assemblies

USAEC Report BNL 50035 (T-449) (Reactor Technology-4500), Brookhaven National

Laboratory (1966).


[3] WINDSOR, H.H., Buckling Measurements in Water-Moderated and Reflected

Exponential Experiments, Nucl.Sci.and Eng.,5,61 (1959).


[4] BERNOCCHI, E., MARTINELLI, R. (editors), Light Water Lattice Data, pages 59,61,
63-
65,81,82, Comitato Nazionale per LEnergia Nucleare, Dipartamento Ricerca Tecnologica
di Base ed Avanzata, Quaderno RIT/FIS(77)1,NEACRP-U-190 (1977).


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2.13)UO2-LW-NPY-NORA

H2O-moderated uranium oxide critical lattices

Laboratory: NPY Norway-Poland-Yugoslavia Association, Kjeller (Norway)

Facility: NORA

These benchmarks are three H2O moderated lattices of3.41 w% enriched uranium oxide
rods in square patterns. Material bucklings and spectral indexes were measured.

Pitch (cm) npy_nora1: 1.900
npy_nora2: 2.314
npy_nora3: 2.687
Lattice geometry Square
Water/fuel volume ratio npy_nora1: 1.66
npy_nora2: 3.03
npy_nora3: 4.51
Moderator H2O
Fuel material UO2 (3.410 w%)
Fuel Density (g/cm3) 10.4
Radius of fuel rods (cm) 0.635
Clad material 304-SS
Outer radius of clad (cm) 0.694
Thickness of clad (cm) 0.048
Temperature (K) 293
Experimental buckling
(1/cm2)
npy_nora1: 0.00918 0.00017
npy_nora2: 0.00988 0.00012
npy_nora3: 0.00864 0.0001

Refereences

[1] KAPLAN, I. et al., The Measurements of Reactor Parameters in Slightly Enriched
Uranium Heavy Water Moderated Miniature Lattices, MIT-2344-8, Massachusets

Institute of Technology (1966).


[2] ANDERSEN, E. et al., Topics in Light Water Reactor Physics: Final Report of the NORA

Project Technical Report Series No, 113, International Atomic Energy Agency (1970).


[3] BERNOCCHI, E., MARTINELLI, R. (editors), Light Water Lattice Data, pages 68-70,

Comitato Nazionale per LEnergia Nucleare, Dipartamento Ricerca Tecnologica di Base

ed Avanzata, Quaderno RIT/FIS(77)1,NEACRP-U-190 (1977).


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2.14) UO2-LW-SCKBN-VENUS

H2O-moderated uranium oxide critical lattices

Laboratory: SCK-BN Studie Centrum voor Kernenergie
Belgonucleaire Association (Belgium)

Facility: VENUS

Pitch (cm) sck_venus1: 1.303
sck_venus2: 1.843
Lattice geometry Square
Water/fuel volume ratio sck_venus1: 1.522
sck_venus2: 4.252
Moderator H2O
Fuel material UO2 (4.01 w%)
Fuel Density (g/cm3) 10.29
Radius of fuel rods (cm) 0.445
Clad material 304-SS
Outer radius of clad (cm) 0.489
Thickness of clad (cm) 0.038
Temperature (K) 293
Experimental buckling
(1/cm2)
sck_venus1: 0.009910 0.000170
sck_venus2: 0.011418 0.000041
References

[1] BINDLER, L. et al., Experimental and Theoretical Physics Work on Plutonium Enriched
LWR's Lattices, BLG-440, BN-7006-03, Belgonucleaire Studie Centrum voor
Kernenenergie Association (1970).

[2] BERNOCCHI, E., MARTINELLI, R. (editors) Light Water Lattice Data, pages 73,74,

Comitato Nazionale per LEnergia Nucleare, Dipartamento Ricerca Tecnologica di Base

ed Avanzata, Quaderno RIT/FIS(77)1,NEACRP-U-190 (1977).


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