WIMS Library Update Project |
H2O-moderated uranium oxide critical lattices (UO2-LW/CRITUO2)
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).
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).
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 |
[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).
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).
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).
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 |
[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).
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).
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 |
[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).
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).
H2O-moderated uranium oxide critical lattice
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 |
H2O-moderated uranium oxide critical lattices
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 ofH2O-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) |
|
Water/fuel volume ratio |
anl_zpr7a1:
0.4347 |
|
Moderator |
H2O |
|
Fuel material |
UO2 |
|
Fuel Density (g/cm3) |
anl_zpr7a:
10.17 |
|
Radius of fuel rods (cm) |
anl_zpr7a:
0.4675 |
|
Clad material |
||
Outer radius of clad (cm) |
anl_zpr7a1-3,5:
0.5290 |
|
Thickness of clad (cm) |
anl_zpr7a1-3,5:
0.0480 |
|
Temperature (K) |
293 |
|
Experimental
buckling |
anl_zpr7a1:
0.0024360.00001 |
|
References
[1] HELLENS, R.L., PRICE, G.A., Reactor Physics Data for Water Moderated Lattices ofH2O-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 EnrichedH2O-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 |
[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).