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H2O-moderated UO2-PuO2 (MOX) critical lattices-MOX-LW (CRITMOX)

4.01) MOX-LW-WAPD-CRX

H2O-moderated UO2-PuO2 critical lattices

Laboratory: WAPD Westinghouse Atomic Power Department (USA)

Facility: CR

These benchmarks are six H2O moderated lattices of natural uranium oxide-plutonium
oxide rods in square patterns. Material bucklings were measured.

Pitch (cm)	wcrx_pu1: 1.752 wcrx_pu2: 1.905 wcrx_pu3: 2.479 wcrx_pu4: 2.695 wcrx_pu5: 3.505 wcrx_pu6: 1.321
Lattice geometry	Square
Water/fuel volume ratio	wcrx_pu1: 1.123 wcrx_pu2: 1.556 wcrx_pu3: 3.502 wcrx_pu4: 4.367 wcrx_pu5: 8.257 wcrx_pu6: 1.683
Moderator	H2O
Fuel material	wcrx_pu1-5: UO2(natural)+2.0w%PuO2 wcrx_pu6:UO2(natural)+6.6w%PuO2
Fuel Density (g/cm³)	wcrx_pu1-5: 9.54 wcrx_pu6: 10.77
Radius of fuel rods (cm)	wcrx_pu1-5: 0.6415 wcrx_pu6: 0.4285
Clad material	wcrx_pu1-5: Zr-2 wcrx_pu6: Zr-4
Outer radius of clad (cm)	wcrx_pu1-5: 0.7175 wcrx_pu6: 0.4965
Thickness of clad (cm)	wcrx_pu1-5: 0.0762 wcrx_pu6: 0.0590
Temperature (K)	wcrx_pu1-5: 293 wcrx_pu6: 299
Experimental buckling (1/cm2)	wcrx_pu1: 0.006956 0.000100 wcrx_pu2: 0.009000 0.000090 wcrx_pu3: 0.007950 0.000110 wcrx_pu4: 0.007330 0.000070 wcrx_pu5: 0.005030 0.000030 wcrx_pu6: 0.010880 0.000130
Pu isotopic composition (w %)	wcrx_pu1-2,5	Pu239: 91.610 Pu240: 7.654 Pu241: 0.701 Pu242: 0.031
	wcrx_pu3,4	Pu239: 71.760 Pu240: 23.500 Pu241: 4.080 Pu242: 0.656
	wcrx_pu6	Pu239: 90.490 Pu240: 8.570 Pu241: 0.890 Pu242: 0.040

REFERENCES
[1] LEAMER, R.D. et al., PuO2-UO2 Fueled Critical Experiments, USAEC Report WCAP-
3726-1, Westignhouse Electric Corporation, Atomic Power Department (1967).

[2] UOTINEN, V.O. et al., Lattices of Plutonium-Enriched Rods in Light Water - Part I:
Experimental Results, Nucl.Technology, 15, 257 (1972).

[3] BERNOCCHI, E., MARTINELLI, R. (editors), Light Water Lattice Data, pages
90,91,93,95,96,111, 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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4.02) MOX-LW-JAERI-TCA

H2O-moderated UO2-PuO2 critical lattices

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

Facility: TCA Tank type Critical Assembly

These benchmarks are four H2O moderated lattices of natural uranium
oxide-plutonium oxide rods in square patterns. Material bucklings were
measured.

Pitch (cm)	jtca_pu1: 1.825 jtca_pu2: 1.956 jtca_pu3: 2.225 jtca_pu4: 1.474
Lattice geometry	Square
Water/fuel volume ratio	jtca_pu1: 2.42 jtca_pu2: 2.98 jtca_pu3: 4.24 jtca_pu4: 5.55
Moderator	H2O
Fuel material	UO2(natural) + 3.01%PuO2
Americium-241 content	530 ppm in PuO₂ (1)
Impurity content	0.9 ppm equivalent boron concentrationin PuO2-UO2
Fuel Density (g/cm³)	6.056
Radius of fuel rods (cm)	0.5325
Clad material	Zr-2
Cladding density (g/cm³)	6.523
Outer radius of clad (cm)	0.6115
Thickness of clad (cm)	0.0700
Temperature (K)	293
Experimental buckling (1/cm²)	jtca_pu1: 0.008064 0.000005 jtca_pu2: 0.008311 0.000006 jtca_pu3: 0.007782 0.000002 jtca_pu4: 0.006491 0.000004
Pu isotopic composition (w%)	Pu238: 0.494 Pu239: 68.180 Pu240: 22.020 Pu241: 7.260 Pu242: 2.040

(1) on 1971-8-16

References

[1] KOBAYASHI, I. et al., Critical Experiments and Analysis on Light-Water Moderated
PuO2-UO2 Lattices, JAERI-Memo 5745, Japan Atomic Energy Research Institute (1974).

[2] TSURUTA, H. et. al., Critical Sizes of Light Water Moderated UO2 and PuO2-UO2
Lattice, JAERI 1254 (1978).

[3] TSURUTA, H. et. al., Experiment and Calculation of Keff for the Light-Water
ModeratedTwo-Region Core of UO2 and PuO2-UO2 Lattices,
JAERI-M 4696 (1972) [in Japanese].

[4] TSURUTA, H. et. al., Critical Experiments and Analyses on 7x7 PuO2-UO2 Lattices in
Light-Water Moderated UO2 Core, JAERI 1234 (1973).

[5] NUCLEAR ENERGY AGENCY, CRITICAL ARRAYS OF MIXED PLUTONIUM-
URANIUM FUEL RODS WITH WATER-TO-FUEL VOLUME RATIOS RANGING
FROM 2.4 TO 5.6, NEA/NSC/DOC/(95)03/VI, Volume VI, MIX-COMP-THERM-004,
Nuclear Science Committee, International Handbook of Evaluated Criticality Safety
Benchmark Experiments, September 2001 Edition, Nuclear Energy Agency,
OECD (2001)

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4.03) MOX-LW-GE-GEea

H2O-moderated UO2-PuO2 lattices (exponential experiments)

Laboratory: GE - General Electric Company (USA)

These benchmarks are six H2O moderated lattices of depleted uranium oxide
(0.22 w % U235)-plutonium oxide rods in hexagonal patterns. Material bucklings
were measured from exponential experiments.

Pitch (cm)	ge_pu1: 1.397 ge_pu2: 1.524 ge_pu3: 1.803 ge_pu4: 2.032 ge_pu5: 2.286 ge_pu6: 2.362
Lattice geometry	Hexagonal
Water/fuel volumen ratio	ge_pu1: 1.100 ge_pu2: 1.558 ge_pu3: 2.704 ge_pu4: 3.789 ge_pu5: 5.144 ge_pu6: 5.580
Moderator	H2O
Fuel material	UO2(0.22 W% U235)+1.5 w% PuO2
Fuel Density (g/cm³)	9.65
Radius of fuel rods (cm)	0.4725
Clad material	Zry-2
Outer radius of clad (cm)	0.541
Thickness of clad (cm)	0.069
Temperature (K)	293
Experimental buckling (1/cm²)	ge_pu1: 0.00480 0.00012 ge_pu2: 0.00651 0.00008 ge_pu3: 0.00785 0.00003 ge_pu4: 0.00749 0.00003 ge_pu5: 0.00609 0.00002 ge_pu6: 0.00552 0.00002
Pu isotopic composition (w%)	Pu239: 91.41 Pu240: 7.83 Pu241: 0.73 Pu242: 0.03

References

[1] UOTINEN, V.O., LAUBY, J.H., SCHMID, L.C., STINSON, W. P., Lattices of
Plutonium-Enriched Rods in Light Water-Part I: Experimental Results, Nucl. Technol.,
15, 257 (1972).

[2] PETERSON, R.E., WINEGARDNER, W.K., WITTENBROCK, N.G., Plutonium
Recycle Critical Facility Final Safeguards Analysis Supplement: Supplement II: Analysis
of Light Water Moderation, HW-69168 SUP (1964).

[3] LIIKALA, R.C., UOTINEN, V.O., JENQUIN, U.P., Lattices of Plutonium-Enriched Rods
in Light Water-Part II: Theoreti cal Analysis of Plutonium-Fueled Systems, Nucl.
Technol., 15, 272 (1972).

[4] TOPPEL, B.J., VOGELBERGER, P.J. Jr., WIMUNC, E.A., Safety Analysis Associated
with the Plutonium Recycle Experiment in EBWR, ANL-6841 (1966).

[5] SCHMID, L.C., LIIKALA, R.C., STINSON, W.P., WORDEN, J.R., Critical Masses and
Bucklings of PuO2-UO2 H2O Systems, HW-83187 (1964).

[6] SCHMID, L.C., LIIKALA, R.C., STINSON, W.P., WORDEN, J.R., Experiments with
PuO2-UO2 Fuel Elements in Light Water, HW-81659 (1964).

[7] NUCLEAR ENERGY AGENCY, MIXED-OXIDE FUEL-PIN LATTICE 1.5 WT.%
PuO2, 8% 240 Pu, DEPLETED URANIUM, NEA/NSC/DOC(95)03/VI, Volume VI,
MIX-COMP-THERM-009, Nuclear Science Committee, International Handbook of
Evaluated Criticality Safety Benchmark Experiments, September 2001 Edition, Nuclear
Energy Agency, OECD (2001)

[8] BERNOCCHI, E., MARTINELLI, R. (editors), Light Water Lattice Data, page 118,
rows 1-6, 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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4.04) MOX-LW-BNW-BNWea

H2O-moderated UO2-PuO2 lattices (exponential experiments)

Laboratory: BNW - Battelle NorthWest Laboratory (USA)

These benchmarks are 24 H2O moderated lattices of natural uranium oxide-plutonium
oxide rods in hexagonal patterns. Material bucklings were measured from exponential
experiments.

Pitch (cm)	bnw_pua1,c1,d1: 2.032 bnw_pud2: 2.159 bnw_pua2,b1,c2,d3: 2.362 bnw_pua3,b2,c3: 2.667 bnw_pua4,b3,c4: 2.903 bnw_pua5,b4,c5: 3.352 bnw_pua6,b5,c6: 3.420 bnw_pud4: 3.519 bnw_pua7: 4.064 bnw_pua8: 4.089 bnw_pud5: 4.318
Lattice geometry	Hexagonal
Water/fuel volume ratio	bnw_pua1,c1: 1.486 bnw_pud1: 1.564 bnw_pud2: 1.929 bnw_pua2,b1,c2: 2.447 bnw_pud3: 2.563 bnw_pua3,b2,c3: 3.463 bnw_pua4,b3,c4: 4.335 bnw_pua5,b4,c5: 6.196 bnw_pua6,b5,c6: 6.501 bnw_pud4: 7.271 bnw_pua7: 9.696 bnw_pua8: 9.831 bnw_pud5: 11.58
Moderator	H2O
Fuel material	bnw_pua-c: Natural UO2+2.0 w% PuO2 bnw_pud: Natural UO2+4.0 w% PuO2
Fuel Density (g/cm³)	bnw_pua-c: 9.54 bnw_pud: 9.46
Radius of fuel rods (cm)	bnw_pua-c: 0.645 bnw_pud: 0.632
Clad material	Zr-2
Outer radius of clad (cm)	bnw_pua-c: 0.7215 bnw_pud: 0.7175
Thickness of clad (cm)	bnw_pua-c: 0.076 bnw_pud: 0.086
Temperature (K)	293
Experimental buckling (1/cm²)	bnw_pua1: 0.00880 0.00003 bnw_pua2: 0.01029 0.00003 bnw_pua3: 0.01034 0.00006 bnw_pua4: 0.00978 0.00004 bnw_pua5: 0.00768 0.00003 bnw_pua6: 0.00700 0.00004 bnw_pua7: 0.00317 0.00018 bnw_pua8: 0.00327 0.00004 bnw_pub1: 0.00884 0.00003 bnw_pub2: 0.00890 0.00005 bnw_pub3: 0.00819 0.00003 bnw_pub4: 0.00618 0.00002 bnw_pub5: 0.00555 0.00003 bnw_puc1: 0.00624 0.00003 bnw_puc2: 0.00789 0.00003 bnw_puc3: 0.00771 0.00003 bnw_puc4: 0.00722 0.00002 bnw_puc5: 0.00536 0.00002 bnw_puc6: 0.00440 0.00001 bnw_pud1: 0.00848 0.00005 bnw_pud2: 0.00947 0.00003 bnw_pud3: 0.01079 0.00003 bnw_pud4: 0.00876 0.00005 bnw_pud5: 0.00414 0.00002
Pu isotopic composition (w %)	bnw_pua	Pu238: 0.0 Pu239: 91.62 Pu240: 7.65 Pu241: 0.70 Pu242: 0.03
	bnw_pub	Pu238: 0.0 Pu239: 81.11 Pu240: 16.54 Pu241: 2.15 Pu242: 0.20
	bnw_puc	Pu238: 0.0 Pu239: 71.76 Pu240: 23.50 Pu241: 4.08 Pu242: 0.66
	bnw_pud	Pu238: 0.28 Pu239: 75.38 Pu240: 18.10 Pu241: 5.08 Pu242: 1.15

References

[1] STINSON, W.P., LAUBY, J.H., Approach-to-Critical Experiments with UO2-4 wt.%
PuO2-H2O Lattices in Plutonium, Utilization Program Technical Activities Quarterly
Report September-November 1968, BNWL-963, Pacific Northwest Laboratories (1969).

[2] STINSON, W.P., UOTINEN, V.O., Destructive and Nondestructive Analysis of
Plutonium Fuels Used in Lattice Experiments, BNWL-1627, Battelle Pacific Northwest
Laboratories (1971).

[3] NEELY, V.I., LLOYD, R.C., CLAYTON, E.D., Neutron Multiplication Measurements
with Pu-Al Alloy Rods in Light Water in Nuclear Physics Research Quarterly Report
January,February, March, 1960, HW-64866, General Electric Company (1960).

[4] NEWMAN, S.D.F., Measurement of K and Relative Reaction Rates in an H2O
Moderated UO2-PuO2 Particulate Fueled Lattice, Nucl. Technol., 15, 192 (1972).

[5] LIIKALA, R.C., UOTINEN, V.O., JENQUIN, U.P., Lattices of Plutonium-Enriched
Rods in Light Water Part II Theoretical Analysis of Plutonium-Fueled Systems, Nucl.
Technol., 15, 272 (1972).

[6] GELHAUS, G.L., LIIKALAM R.C., Preli minary Calculated Results for UO2-4 wt.%
PuO2-H2O Lattices, BNWL-685, Pacific Northwest Laboratories (1968).

[7] NUCLEAR ENERGY AGENCY, WATER-MODERATED MIXED PLUTONIUM-
URANIUM OXIDE PINS,4.0 WT.% PuO2, 18% 240 Pu, NATURAL URANIUM
NEA/NSC/DOC(95)03/VI,Volume VI,MIX-COMP-THERM-005, Nuclear Science
Committee, International Handbook of Evaluated Criticality Safety Benchmark
Experiments, September 2001 Edition, Nuclear Energy Agency, OECD (2001).

[8] NUCLEAR ENERGY AGENCY, WATER-MODERATED MIXED OXIDE
HEXAGONAL LATTICES -2.0 WT.% PuO2, 8% 240 Pu, NATURAL URANIUM
NEA/NSC/DOC(95)03/VI,Volume VI,MIX-COMP-THERM-006, Nuclear Science
Committee, International Handbook of Evaluated Criticality Safety Benchmark
Experiments, September 2001 Edition, Nuclear Energy Agency, OECD (2001).

[9] NUCLEAR ENERGY AGENCY, HEXAGONAL LATTICES OF MIXED OXIDE
FUEL PINS UO2 2 Wt.% PuO2 (16% 240 Pu), NATURAL URANIUM,
NEA/NSC/DOC(95)03/VI, Volume VI, MIX-COMP-THERM-007, Nuclear Science
Committee, International Handbook of Evaluated Criticality Safety Benchmark
Experiments, September 2001 Edition, Nuclear Energy Agency, OECD (2001).

[10] NUCLEAR ENERGY AGENCY, HEXAGONAL LATTICES OF MIXED OXIDE

FUEL PINS UO2 2.0 WT.% PuO2, 24% 240 Pu, NATURAL URANIUM
NEA/NSC/DOC(95)03/VI, Volume VI, MIX-COMP-THERM-008, Nuclear Science
Committee, International Handbook of Evaluated Criticality Safety Benchmark
Experiments, September 2001 Edition, Nuclear Energy Agency, OECD (2001)

[11] BERNOCCHI, E., MARTINELLI, R. (editors), Light Water Lattice Data, page
118, rows 8-24, page 119, rows 1-5,8,10, 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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