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D2O-moderated uranium oxide critical lattices (UO2-HW/CRITD2O)

8.01) UO2HW-AECLZED2

D2O-moderated uranium oxide critical lattices

Laboratory: AECL Atomic Energy of Canada Limited, Chalk River Nuclear Laboratories,
Chalk River, Ontario (Canada)

Facility: ZED-2 Numerous experiments with different fuel elements of CANDU type
have been performed in the Canadian heavy water reactor ZED-2. They were made
using UO2 (natural) fuel on 37(a) and 28 hexagonal(b) and square(c) fuel clusters,
including buckling measurements and several parameters of the cells. Three of these
experiments were selected:

a) Analysis of Experiments with 37-rod Fuel clustersMeasurements have been
made at a single pitch 28.58 cm square, UO2 (natural) fuel, using heavy water
and air as coolants.

Pitch (cm) 28.58 (square)
Coolants zed2t1d2o : D2O
zed2t1air : Air
Moderator D2O
Number of rods 37 (1/6/12/18)
Radius of rod centers (cm) 0.0/1.4885/2.8755/4.3305
Fuel material UO2-nat
Density of fuel material(g/cm3) 10.50
Radius of fuel rods (cm) Central: 0.5965
Others: 0.6050
Sheath material Zry-4
Density of sheath material (g/cm3) 6.55
Internal radius of sheath (cm) 0.61
Thickness of sheath (cm) 0.045
Material of pressure and calandria tubes 1050 Al alloy
Density of pressure and
calandria Tubes (g/cm3)		 2.7
Internal radius of pressure tube (cm) 5.195
Thickness of pressure tube (cm) 0.315
Internal radius of calandria tube (cm) 6.35
Thickness of calandria tube (cm) 0.32
Temperature (K) 294.8
Experimental buckling
(1/cm2)		 zed2t1d2o : 0.00027
zed2t1air : 0.00020

References

[1] INTERNATIOAL ATOMIC ENERGY AGENCY, In-core fuel management benchmarks
for PHWRs, IAEA-TECDOC-887, Task 9.1,Pag.111-117,1996.

[2] KAY, R.E., Lattice Measurements with 37-Element Bruce Reactor Fuel in Heavy Water
Moderator: Detailed Lattice Cell Parameters, AECL-5307,1976.

b) Analysis of Experiments with 28-rod Fuel Clusters (hexagonal pitches)

Measurements were made using UO2 (natural) fuel, heavy water and air as coolants.
Buckling measurements were performed at 8 triangular lattice pitches of 24, 26, 28,
30, 32, 34, 36 and 40 cm for both the coolants, and detailed reaction rate measurements
were carried out at 4 lattice pitches of 24, 28, 32 and 40 cm only.
Pitch (cm) zed2t2p24: 24.0
zed2t2p40: 40.0
Lattice geometry Hexagonal
Coolant D2O
Moderator D2O
Number of rods 28 (4/8/16)
Radius of rod centres (cm) 1.163/2.652/4.206
Fuel material UO2-nat
Density of fuel material (g/cm3) 10.45
Radius of fuel rods (cm) 0.71
Sheath material Zry-2
Density of sheath material (g/cm3) 6.55
Internal radius of sheath (cm) 0.715
Thickness of sheath (cm) 0.045
Material of pressure tube 65s Al alloy
Material of calandria tube 50s Al alloy
Density of pressure and
calandria tubes (g/cm3)		 2.7
Internal radius of pressure tube (cm) 5.095
Thickness of pressure tube (cm) 0.295
Internal radius of calandria tube (cm) 6.23
Thickness of calandria tube (cm) 0.14
Temperature (K) 296.0
Experimental buckling
(1/cm2)		 zed2t2p24: 0.0002804
zed2t2p40: 0.0002772

References

[1] INTERNATIONAL ATOMIC ENERGY AGENCY, In- core fuel management
benchmarks for PHWRs, IAEA-TECDOC-887, Task 9.2,Pag.117-122,1996.

[2] SERDULA, K.J., AECL-2606,1966.

c) Analysis of Experiments with 28-rod Fuel Clusters (square pitch)

Measurement of material buckling has been made at a single pitch 28.575 cm
square, using UO2 (natural) fuel and heavy water as coolant.
Pitch (cm) 28.575 (square)
Coolant D2O
Moderator D2O
Number of rods 28 (4/8/16)
Radius of rod centres (cm) 1.163/2.652/4.206
Fuel material UO2-nat
Density of fuel material (g/cm3) 10.0277
Radius of fuel rods (cm) 0.7105
Sheath material Zry-2
Density of sheath material (g/cm3) 6.55
Internal radius of sheath (cm) 0.7155
Thickness of sheath (cm) 0.0454
Material of pressure tube 65s Al alloy
Material of calandria tube 50s Al alloy
Density of pressure and
calandria tubes (g/cm3)		 2.7
Internal radius of pressure tube (cm) 5.0965
Thickness of pressure tube (cm) 0.296
Internal radius of calandria tube (cm) 6.23
Thickness of calandria tube (cm) 0.139
Temperature (K) 296.0
Experimental buckling (1/cm2) 0.000377

References

[1] JONES, R.T., AECL-5853,1977.
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8.02) UO2HW-JNCDIDCA  

D2O-moderated uranium oxide critical lattices

Laboratory: Japan Nuclear Cycle Development Institute (Japan)

Facility: DCA Deuterium Critical Assembly

DCA is a Japanese critical facility with 28 fuel elements of CANDU type.
The fuel is made of UO2 with slightly enriched uranium (1.2 w% U235).
Experiments were made including buckling measurements with different coolants:
heavy water, air and light water. Buckling measurements were performed at two
square lattice pitches of 22.5 and 25.0 cm.

Pitch (cm) dcat1d22,a22,h22: 22.5
dcat1d25,a25,h25: 25.0
Lattice geometry Square
Coolants dcat1d : D2O
dcat1a: Air
dcat1h: H2O
Moderator D2O
Number of rods 28 (4/8/16)
Radius of rod centres (cm) 1.3125/3.0/4.7575
Fuel material UO2-1.2w%
Density of fuel material (g/cm3) 10.36
Radius of fuel rods (cm) 0.74
Sheath material Al
Density of sheath material (g/cm3) 2.7
Internal radius of sheath (cm) 0.7515
Thickness of sheath (cm) 0.0850
Material of pressure and calandria tubes Al
Density of pressure and calandria tubes (g/cm3) 2.7
Internal radius of pressure
tube (cm)		 5.84
Thickness of pressure
tube (cm)		 0.20
Internal radius of calandria tube (cm) 6.625
Thickness of calandria
tube (cm)		 0.20
Temperature (K) 295.15
Experimental bucklings
(1/cm2)



 (1) Void fraction: 87 %(99.82 atom % of D2O)
dcat1d22(1): Br2= 0.000247 Bz2= 0.000766
dcat1a22(1): Br2= 0.000236 Bz2= 0.000647
dcat1h22(1): Br2= 0.000247 Bz2= 0.000859

(2) Void fraction: 70 %(88.88 atom % of D2O)
dcat1d25(2): Br2= 0.000247 Bz2= 0.000781
dcat1a25(2): Br2= 0.000231 Bz2= 0.000725
dcat1h25(2): Br2= 0.000245 Bz2= 0.000727

References

[1] SHIBA, K., Substitution measurements on 28-fuel-rod-critical Clusters in D2O and Their
Analysis by the Second-Order Perturbation method Nucl.Sci. and Engn.65,492-507
(1978).

[2] KOWATA, Y., FUKUMURA, N., Nucl.Sci.and Engn.99,299-312 (1988).[3] LERNER, A.M.,
Evaluation of neutronic parameters in heavy water and slightly enriched uranium.
Comparison between calculated values with WIMS code and measurements
performed in DCA falicity. Tech.Rep. CNEA-RE-CA 94-07, 1994 (in Spanish).
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