OPAL NUCLEAR REACTOR: EXPERIMENTAL DATA
G. BRAOUDAKIS  
Australian Nuclear Science and Technology Organisation, 
Menai, Australia 
Email: gbx@ansto.gov.au
Abstract
The report provides technical details on the Open Pool Australian Light Water (OPAL) reactor core and immediate structure for 
analysis purposes. The goal of the report is to provide sufficient geometric and material data to build a computational neutronic model 
of the facility.
1. STEADY STATE FLUX DISTRIBUTION
Gold wires are irradiated in the core to measure the thermal neutron flux. The capture of a neutron by the 
stable isotope 197Au leads to the radioactive isotope 198Au. Neutron flux is obtained from activation analysis of the 
gold wires. 
Unless the cadmium ratio is known at the irradiation position, two irradiations are required to determine the 
absolute thermal neutron flux. One irradiation with the wire covered with a cadmium tube and one irradiation with 
the wire bare. Reference bare gold wires or fission counter readings are used to normalize the second irradiation to 
the first one. 
The wires were fixed on an aluminium plate using tape and inserted in between fuel plates (i.e. within a 
coolant channel) for irradiation. The measured (n, γ) reaction rate per atom of gold in the wire and the thermal 
neutron flux are provided in Tables 1 and 2, in which the position of each wire during irradiation is specified by 
the fuel assembly identification, channel number within the fuel assembly, and the coordinates on the aluminium 
plate. These locations are indicated in Figs 1–3. The thermal fluxes are presented as the scalar flux (neutron 
energy < 0.625 eV). The reactor power during the gold–aluminium wire irradiations was estimated to be 36 ± 6 kW. 
The corresponding reactor power is obtained assuming a thermal energy release per fission of 201.97 MeV for 235U.
TABLE 1.  THERMAL FLUX MEASUREMENT BY GOLD WIRES (cont.)
Fuel Fuel Channel Bare wire 
assembly assembly within fuel Position in Position in widthc lengthc reaction rate 
Thermal flux 
−2 −1
index 1a index 2a assemblyb (atom−1·s−1) (cm ·s )
B 1 1 E 1 3.102E–11 1.58E+11
B 1 1 E 3 4.627E–11 2.36E+11
B 1 1 E 5 6.778E–11 3.44E+11
B 1 1 E 7 8.553E–11 4.32E+11
B 1 1 E 9 9.777E–11 4.98E+11
B 1 1 E 11 1.059E–10 5.43E+11
B 1 1 E 13 1.109E–10 5.78E+11
B 1 1 E 15 1.125E–10 5.95E+11
B 1 1 E 17 1.014E–10 5.51E+11
B 1 1 E 19 8.978E–11 5.00E+11
B 1 1 E 21 7.182E–11 4.00E+11
1
TABLE 1.  THERMAL FLUX MEASUREMENT BY GOLD WIRES (cont.)
Fuel Fuel Channel 
assembly assembly within fuel Position in Position in 
Bare wire 
widthc lengthc reaction rate 
Thermal flux 
index 1a index 2a assemblyb (atom−1·s−1) (cm
−2·s−1)
C 1 1 A 1 3.16E–11 1.54E+11
C 1 1 A 3 4.443E–11 2.16E+11
C 1 1 A 5 6.741E–11 3.39E+11
C 1 1 A 7 8.581E–11 4.44E+11
C 1 1 A 9 9.606E–11 5.00E+11
C 1 1 A 11 1.06E–10 5.54E+11
C 1 1 A 13 1.113E–10 5.73E+11
C 1 1 A 15 1.075E–10 5.45E+11
C 1 1 A 17 1.018E–10 5.47E+11
C 1 1 A 19 8.699E–11 4.92E+11
C 1 1 A 21 7.113E–11 4.02E+11
A 2 20 A 1 2.835E–11 1.42E+11
A 2 20 A 2 3.032E–11 1.47E+11
A 2 20 A 3 4.012E–11 1.87E+11
A 2 20 A 4 4.404E–11 1.94E+11
A 2 20 A 5 4.806E–11 1.98E+11
A 2 20 A 6 5.206E–11 1.99E+11
A 2 20 A 7 5.397E–11 1.88E+11
A 2 20 A 8 5.806E–11 2.01E+11
A 2 20 A 9 6.039E–11 2.09E+11
A 2 20 A 10 6.507E–11 2.24E+11
A 2 20 A 11 6.536E–11 2.23E+11
A 2 20 A 12 7.021E–11 2.48E+11
A 2 20 A 13 7.289E–11 2.65E+11
A 2 20 A 14 7.685E–11 2.88E+11
A 2 20 A 15 8.718E–11 3.35E+11
A 2 20 A 16 8.995E–11 3.63E+11
A 2 20 A 17 8.957E–11 3.78E+11
A 2 20 A 18 8.476E–11 3.72E+11
A 2 20 A 19 7.623E–11 3.47E+11
A 2 20 A 20 7.239E–11 3.75E+11
A 2 20 A 21 6.44E–11 3.67E+11
A 2 20 B 17 8.408E–11 3.54E+11
A 2 20 C 17 8.929E–11 3.76E+11
A 2 20 D 17 8.99E–11 3.79E+11
A 2 20 E 17 9.848E–11 4.15E+11
D 2 20 A 17 9.411E–11 3.57E+11
2
TABLE 1.  THERMAL FLUX MEASUREMENT BY GOLD WIRES (cont.)
Fuel Fuel Channel 
assembly assembly within fuel Position in Position in 
Bare wire 
reaction rate Thermal flux c c −2 −1
index 1a index 2a assemblyb width length (atom−1·s−1) (cm ·s )
D 2 20 B 17 8.634E–11 3.62E+11
D 2 20 C 17 8.15E–11 3.83E+11
D 2 20 D 17 8.05E–11 4.18E+11
D 2 20 E 1 2.002E–11 7.90E+10
D 2 20 E 2 2.478E–11 9.78E+10
D 2 20 E 3 3.052E–11 1.20E+11
D 2 20 E 4 3.503E–11 1.36E+11
D 2 20 E 5 4.101E–11 1.57E+11
D 2 20 E 6 4.484E–11 1.68E+11
D 2 20 E 7 4.739E–11 1.74E+11
D 2 20 E 8 4.957E–11 1.85E+11
D 2 20 E 9 5.203E–11 1.97E+11
D 2 20 E 10 5.577E–11 2.14E+11
D 2 20 E 11 5.985E–11 2.33E+11
D 2 20 E 12 5.899E–11 2.32E+11
D 2 20 E 13 6.445E–11 2.56E+11
D 2 20 E 14 7.058E–11 2.84E+11
D 2 20 E 15 8.165E–11 3.32E+11
D 2 20 E 16 8.239E–11 3.51E+11
D 2 20 E 17 8.102E–11 3.60E+11
D 2 20 E 18 7.82E–11 3.61E+11
D 2 20 E 19 7.165E–11 3.43E+11
D 2 20 E 20 6.288E–11 3.01E+11
D 2 20 E 21 5.596E–11 2.68E+11
A 3 13 C 14 7.752E–11 2.12E+11
A 3 13 C 17 7.713E–11 2.25E+11
B 3 8 C 14 9.686E–11 3.34E+11
B 3 8 C 17 9.792E–11 3.62E+11
C 3 13 C 14 8.406E–11 2.39E+11
C 3 13 C 17 8.116E–11 2.02E+11
D 3 13 C 14 8.52E–11 3.16E+11
D 3 13 C 17 8.377E–11 3.33E+11
B 4 20 A 13 8.656E–11 3.68E+11
B 4 20 B 13 8.237E–11 3.66E+11
B 4 20 C 13 8.497E–11 3.55E+11
B 4 20 D 13 8.549E–11 3.73E+11
B 4 20 E 1 2.555E–11 1.21E+11
3
TABLE 1.  THERMAL FLUX MEASUREMENT BY GOLD WIRES (cont.)
Fuel Fuel Channel 
assembly assembly within fuel Position in Position in 
Bare wire 
widthc lengthc reaction rate 
Thermal flux 
index 1a index 2a assemblyb (atom−1·s−1) (cm
−2·s−1)
B 4 20 E 2 2.974E–11 1.30E+11
B 4 20 E 3 3.811E–11 1.52E+11
B 4 20 E 4 4.616E–11 1.86E+11
B 4 20 E 5 5.808E–11 2.37E+11
B 4 20 E 6 6.49E–11 2.67E+11
B 4 20 E 7 7.302E–11 3.03E+11
B 4 20 E 8 7.663E–11 3.22E+11
B 4 20 E 9 8.056E–11 3.42E+11
B 4 20 E 10 8.863E–11 3.80E+11
B 4 20 E 11 9.055E–11 3.92E+11
B 4 20 E 12 9.421E–11 4.07E+11
B 4 20 E 13 9.561E–11 4.12E+11
B 4 20 E 14 9.771E–11 4.20E+11
B 4 20 E 15 9.419E–11 4.04E+11
B 4 20 E 16 9.217E–11 4.09E+11
B 4 20 E 17 8.981E–11 4.10E+11
B 4 20 E 18 8.346E–11 3.92E+11
B 4 20 E 19 7.837E–11 3.78E+11
B 4 20 E 20 7.079E–11 3.89E+11
B 4 20 E 21 6.507E–11 3.93E+11
C 4 13 C 14 7.967E–11 2.37E+11
C 4 13 C 17 7.528E–11 2.13E+11
A 1 8 C 14 7.285E–11 2.29E+11
A 1 8 C 17 6.636E–11 1.97E+11
D 1 13 C 14 6.943E–11 2.14E+11
D 1 13 C 17 6.507E–11 2.00E+11
B 2 8 C 14 9.876E–11 3.45E+11
B 2 8 C 17 9.934E–11 3.74E+11
C 2 13 C 14 8.418E–11 2.39E+11
C 2 13 C 17 8.642E–11 2.62E+11
A 4 8 C 14 8.016E–11 3.01E+11
A 4 8 C 17 7.677E–11 3.22E+11
D 4 13 C 14 7.499E–11 3.02E+11
D 4 13 C 17 7.161E–11 3.01E+11
a Refer to Fig. 1. 
b Refer to Fig. 2. 
c Refer to Fig. 3.
4
TABLE 2.  REACTION RATE FOR CADMIUM COVERED GOLD WIRES (cont.)
Fuel assembly Fuel assembly Channel within Position in Position in Cd covered 
index 1a index 2a fuel assemblyb widthc lengthc reaction rate (atom−1·s−1)
A 1 8 C 14 5.61E–11
A 1 8 C 17 5.21E–11
A 2 20 A 1 1.68E–11
A 2 20 A 3 2.52E–11
A 2 20 A 7 3.96E–11
A 2 20 A 11 4.86E–11
A 2 20 A 15 6.11E–11
A 2 20 A 19 4.87E–11
A 2 20 A 21 3.40E–11
A 3 13 C 14 6.23E–11
A 3 13 C 17 6.07E–11
A 4 8 C 14 5.71E–11
A 4 8 C 17 5.15E–11
B 1 1 E 3 2.71E–11
B 1 1 E 7 5.03E–11
B 1 1 E 11 6.19E–11
B 1 1 E 15 6.37E–11
B 1 1 E 19 4.88E–11
B 2 8 C 14 7.28E–11
B 2 8 C 17 7.06E–11
B 3 8 C 14 7.15E–11
B 3 8 C 17 6.98E–11
B 4 20 E 1 1.58E–11
B 4 20 E 3 2.62E–11
B 4 20 E 7 4.91E–11
B 4 20 E 11 5.97E–11
B 4 20 E 15 6.21E–11
B 4 20 E 19 4.80E–11
B 4 20 E 21 3.23E–11
C 1 1 A 3 2.70E–11
C 1 1 A 7 4.93E–11
C 1 1 A 11 6.09E–11
C 1 1 A 15 6.31E–11
C 1 1 A 19 4.65E–11
C 2 13 C 14 6.70E–11
C 2 13 C 17 6.75E–11
5
TABLE 2.  REACTION RATE FOR CADMIUM COVERED GOLD WIRES (cont.)
Fuel assembly Fuel assembly Channel within Position in Position in Cd covered 
index 1a index 2a fuel assemblyb widthc lengthc reaction rate (atom−1·s−1)
C 3 13 C 14 6.68E–11
C 3 13 C 17 6.71E–11
C 4 13 C 14 6.23E–11
C 4 13 C 17 5.99E–11
D 1 13 C 14 5.39E–11
D 1 13 C 17 5.05E–11
D 2 20 E 3 2.12E–11
D 2 20 E 7 3.39E–11
D 2 20 E 11 4.19E–11
D 2 20 E 15 5.53E–11
D 2 20 E 19 4.41E–11
D 3 13 C 14 6.07E–11
D 3 13 C 17 5.76E–11
D 4 13 C 14 5.15E–11
D 4 13 C 17 4.80E–11
a Refer to Fig. 1. 
b Refer to Fig. 2. 
c Refer to Fig. 3.
6
FIG. 1.  The fuel assembly identifications and orientations.
Channel 1
Channel 2
Channel 3
Channel 4
  :
  :
  :
  :
Channel 20
 
FIG. 2.  Water channel identification for the fuel assembly orientations.
7
Channel 1
Channel 2
Channel 3
Channel 4
  :
  :
  :
  :
Channel 20
A B C D E
 1
Water Channel Profile
 2
 3
 4
 5
 6  Axial 
Profile
 7
 8
 9
10
11 Core Centre
12
13
14
15
16
17
18
19
20
21
Dimensions in mm
Note: Column A is the leftmost (horizontal plates) or bottom (vertical plates) column. 
FIG. 3.  Coordinates of the gold wire placement on a fuel plate. 
8
The gold–aluminium wires were nominally 8 mm long × 0.508 mm in diameter and 0.112 4wt% gold. The 
cadmium covers were tubes with a 1.27 mm inner diameter and a 2.286 mm outer diameter. The aluminium plates 
were 1.6 mm thick. The reactor state during the irradiations is defined in Table 3.
TABLE 3.  REACTOR STATE DURING GOLD–ALUMINIUM IRRADIATION
Coolant temp. 22.0°C
Reflector temp. 20.3°C
Core Fresh fuel/cycle 001
Critical control rod (CR) positions (%)
    CR1 85.7
    CR2 36.0
    CR3 35.9
    CR4 84.8
    CR5 21.6
Cold neutron source Standby operation mode
2. CONTROL ROD WORTH
Control rod calibration was conducted using the asymptotic period method on a critical reactor at low power 
(negligible feedback effects), no external neutron sources and negligible buildup of neutron poisons during the 
measurements.
The point kinetics equation that relates the stable period (T) and the reactivity ($) is the following:
 (1)
where
bi and λi are physical constants associated with the delayed neutron precursors;
Λ  is the average neutron generation time;
i  is the neutron precursor index;
and β is the effective delayed neutron fraction.
The first term of the equation is neglected in comparison with the second term. The equation that relates the 
stable period and the reactivity is then:
 (2)
The reactivity of each portion of the control rod is obtained using the stable period (T) from the collected 
data and Eq. (2). Nuclear data for 235U, 238U and the mixture corresponding to the cycle 01 core configurations are 
presented in Table 4. Cycle 01 is the first core.
9
TABLE 4.  DELAYED NEUTRON PRECURSOR DATA
Group λi (U-235) bi (U-235) bi (U-238) bi first core
1 0.012 4 0.033 0 0.013 0 0.032 5
2 0.030 5 0.219 0 0.137 0 0.218 0
3 0.111 0.196 0 0.162 0 0.195 7
4 0.301 0.395 0 0.388 0 0.394 7
5 1.14 0.115 0 0.225 0 0.116 7
6 3.01 0.042 0 0.075 0 0.042 4
n.a.a 13.034 5 8.511 0 12.955 3
a n.a.: not applicable.
Tables 5–19 describe control rod positions under critical and supercritical conditions. Tables 5–8 are for 
calibration of CR-2 and CR-3. Tables 9–14 are for calibration of CR-1 and CR-4. Tables 15–18 for calibration of 
CR-5. In each step (each row of the table), the initial positions of ROD-A and ROD-B are critical positions and so 
are the final positions. The reactor is supercritical when ROD-A is at the final position while ROD-B remains at 
the initial position. The reactor period under the supercritical condition is measured by three fission chambers and 
converted to reactivity ($) given by Eq. (2). The reactor state during the control rod worth measurements is defined 
in Table 19. 
TABLE 5.  CRITICAL CONTROL AND REGULATING PLATE POSITIONS
Plate position Withdrawal (%)
CR-1 100.0
CR-2 100.0
CR-3 0.0
CR-4 0.0
CR-5 31.4
TABLE 6.  DIFFERENTIAL CONTROL AND REGULATING PLATE WORTH (cont.)
ROD-A → CR-3 ROD-B → CR-2 Reactivity ($)
Initial Final Initial Final FC-1 FC-2 FC-3 Av.
0 8.1 100 94.8 0.114 029 0.111 843 0.113 864 0.113 245
8.1 15.2 94.8 88.5 0.218 159 0.214 17 0.217 436 0.216 588
15.2 20.5 88.5 83 0.247 252 0.244 161 0.247 711 0.246 375
20.5 24.8 83 78.6 0.236 879 0.230 87 0.232 837 0.233 529
24.8 28.1 78.6 75.2 0.203 814 0.201 061 0.203 93 0.202 935
28.1 31.9 75.2 71.2 0.246 117 0.241 014 0.245 365 0.244 165
31.9 35.2 71.2 67.8 0.221 006 0.217 763 0.221 509 0.220 093
35.2 38.3 67.8 64.7 0.210 129 0.207 139 0.210 484 0.209 251
38.3 42.2 64.7 60.8 0.277 884 0.272 531 0.272 932 0.274 449
42.2 45.5 60.8 57.6 0.240 455 0.235 76 0.238 541 0.238 252
10
TABLE 6.  DIFFERENTIAL CONTROL AND REGULATING PLATE WORTH (cont.)
ROD-A → CR-3 ROD-B → CR-2 Reactivity ($)
Initial Final Initial Final FC-1 FC-2 FC-3 Av.
45.5 49.2 57.6 54.3 0.254 96 0.251 485 0.254 994 0.253 813
49.2 53.8 54.3 50.4 0.309 705 0.306 6 0.310 302 0.308 869
53.8 58.1 50.4 46.9 0.285 938 0.282 071 0.285 431 0.284 48
58.1 62 46.9 43.9 0.244 447 0.241 024 0.243 63 0.243 034
62 66.8 43.9 40.5 0.280 965 0.275 081 0.277 611 0.277 886
66.8 71.6 40.5 37.2 0.267 542 0.264 647 0.268 851 0.267 013
71.6 75.1 37.2 34.9 0.182 104 0.179 465 0.181 526 0.181 032
75.1 79.8 34.9 31.9 0.227 243 0.224 234 0.226 828 0.226 102
79.8 85.5 31.9 28.6 0.240 142 0.236 392 0.239 45 0.238 661
85.5 91.8 28.6 25.8 0.204 0.200 704 0.202 88 0.202 528
91.8 100 25.8 23.2 0.168 647 0.166 633 0.168 552 0.167 944
Note: FC — fission chamber.
TABLE 7.  CRITICAL CONTROL AND REGULATING PLATE POSITIONS
Plate position Withdrawal (%)
CR-1 100.0
CR-2 0.0
CR-3 100.0
CR-4 0.0
CR-5 47.2
TABLE 8.  DIFFERENTIAL CONTROL AND REGULATING PLATE WORTH
ROD-A → CR-2 ROD-B → CR-3 Reactivity ($)
Initial Final Initial Final FC-1 FC-2 FC-3 Av.
0 11.3 100 90 0.225 272 0.223 84 0.224 601 0.224 571
11.3 18 90 82.3 0.292 081 0.289 983 0.291 482 0.291 182
18 21.2 82.3 78.2 0.192 472 0.190 65 0.192 398 0.191 84
21.2 23.2 78.2 75.5 0.140 143 0.138 02 0.139 404 0.139 189
Note: FC — fission chamber.
TABLE 9.  CRITICAL CONTROL AND REGULATING PLATE POSITIONS
Plate position Withdrawal (%)
CR-1 100.0
CR-2 0.0
CR-3 100.0
CR-4 0.0
CR-5 47.2
11
TABLE 10.  DIFFERENTIAL CONTROL AND REGULATING PLATE WORTH
ROD-A → CR-4 ROD-B → CR-1 Reactivity ($ )
Initial Final Initial Final FC-1 FC-2 FC-3 Av.
0 11.3 100 90.2 0.229 712 0.226 045 0.229 492 0.228 416
11.3 18.3 90.2 82.6 0.305 889 0.298 254 0.302 686 0.302 276
18.3 22.2 82.6 77.7 0.239 336 0.236 325 0.237 702 0.237 788
22.2 26.3 77.7 72.8 0.272 845 0.270 352 0.271 363 0.271 52
26.3 30.8 72.8 67.3 0.339 475 0.334 391 0.339 573 0.337 813
Note: FC — fission chamber.
TABLE 11.  CRITICAL CONTROL AND REGULATING PLATE POSITIONS
Plate position Withdrawal (%)
CR-1 67.3
CR-2 0.0
CR-3 100.0
CR-4 30.8
CR-5 46.7
TABLE 12.  DIFFERENTIAL CONTROL AND REGULATING PLATE WORTH
ROD-A → CR-4 ROD-B → CR-1 Reactivity ($)
Initial Final Initial Final FC-1 FC-2 FC-3 Average
30.8 34.7 67.3 62.8 0.301 84 0.296 577 0.301 535 0.299 984
34.7 38.5 62.8 58.3 0.318 945 0.315 047 0.319 345 0.317 779
38.5 41.8 58.3 54.6 0.285 033 0.281 113 0.283 39 0.283 179
41.8 44.9 54.6 51.2 0.269 514 0.265 912 0.267 167 0.267 531
44.9 48.5 51.2 47.9 0.287 36 0.284 684 0.284 082 0.285 375
48.5 51.9 47.9 45.1 0.247 504 0.247 315 0.249 281 0.248 033
51.9 55.1 45.1 42.5 0.237 793 0.234 174 0.235 591 0.235 853
55.1 58.7 42.5 39.9 0.247 206 0.244 336 0.245 115 0.245 552
58.7 61.8 39.9 37.7 0.205 109 0.201 979 0.203 063 0.203 384
61.8 66 37.7 35 0.245 255 0.241 327 0.242 582 0.243 055
66 71.3 35 31.6 0.291 603 0.286 148 0.288 289 0.288 68
71.3 76.6 31.6 28.1 0.282 045 0.276 268 0.278 146 0.278 82
76.6 81.5 28.1 24.8 0.237 068 0.232 442 0.233 683 0.234 398
81.5 87.5 24.8 21.1 0.233 974 0.231 211 0.232 639 0.232 608
87.5 94.2 21.1 17.5 0.194 549 0.191 045 0.193 102 0.192 899
94.2 100 17.5 15.4 0.095 621 0.094 247 0.095 201 0.095 023
Note: FC — fission chamber.
12
TABLE 13.  CRITICAL CONTROL AND REGULATING PLATE POSITIONS
Plate position Withdrawal (%)
CR-1 0.0
CR-2 0.0
CR-3 100.0
CR-4 100.0
CR-5 53.5
TABLE 14.  DIFFERENTIAL CONTROL AND REGULATING PLATE WORTH
ROD-A → CR-1 ROD-B → CR-4 Reactivity ($)
Initial Final Initial Final FC-1 FC-2 FC-3 Av.
0 11.2 100 90.5 0.203 946 0.198 7 0.200 899 0.201 182
11.2 15.4 90.5 86 0.160 245 0.155 799 0.157 795 0.157 946
Note: FC — fission chamber.
TABLE 15.  CRITICAL CONTROL AND REGULATING PLATE POSITIONS
Plate position Withdrawal (%)
CR-1 85.0
CR-2 35.3
CR-3 35.4
CR-4 85.0
CR-5 0.0
TABLE 16.  DIFFERENTIAL CONTROL AND REGULATING PLATE WORTH (cont.)
ROD-A → CR-5 ROD-B1 → CR-2 ROD-B2 → CR-3 Reactivity ($)
Initial Final Initial Final Initial Final FC-1 FC-2 FC-3 Av.
0 9 35.3 32.6 35.4 35.4 0.229 266 0.226 371 0.229 305 0.228 314
9 14.7 32.6 32.6 35.4 31.7 0.279 015 0.274 359 0.277 612 0.276 995
14.7 18.1 32.6 29.9 31.7 31.7 0.217 403 0.213 249 0.216 411 0.215 688
18.1 21.2 29.9 29.9 31.7 28.7 0.226 794 0.221 144 0.222 631 0.223 523
21.2 24.7 29.9 27.2 28.7 28.7 0.250 353 0.245 843 0.248 166 0.248 121
24.7 28.8 27.2 27.2 28.7 25 0.290 858 0.287 779 0.291 182 0.289 94
28.8 32.6 27.2 24.6 25 25 0.246 551 0.243 314 0.246 035 0.245 3
32.6 35.8 24.6 24.6 25 22.4 0.199 24 0.195 547 0.197 668 0.197 485
35.8 40.4 24.6 21.8 22.4 22.4 0.259 134 0.253 623 0.255 616 0.256 124
40.4 45 21.8 21.8 22.4 18.9 0.262 685 0.258 507 0.262 442 0.261 211
45 49.6 21.8 18.7 18.9 18.9 0.255 298 0.250 443 0.253 378 0.253 04
49.6 54.8 18.7 18.7 18.9 14.6 0.276 004 0.270 554 0.274 32 0.273 626
54.8 59.3 18.7 15.4 14.6 14.6 0.225 896 0.223 625 0.226 22 0.225 247
13
TABLE 16.  DIFFERENTIAL CONTROL AND REGULATING PLATE WORTH (cont.)
ROD-A → CR-5 ROD-B1 → CR-2 ROD-B2 → CR-3 Reactivity ($)
Initial Final Initial Final Initial Final FC-1 FC-2 FC-3 Av.
59.3 63.8 15.4 15.4 14.6 9.9 0.217 726 0.212 793 0.215 84 0.215 453
63.8 68.3 15.4 11.7 9.9 9.9 0.201 208 0.196 736 0.199 419 0.199 121
68.3 72.9 11.7 6.6 9.9 9.9 0.186 165 0.183 593 0.184 972 0.184 91
72.9 79.5 6.6 6 9.9 0 0.229 014 0.225 382 0.228 394 0.227 597
79.5 86.6 6 0 0 83.3 0.179 666 0.175 526 0.178 83 0.178 007
Note: FC — fission chamber.
TABLE 17.  CRITICAL CONTROL AND REGULATING PLATE POSITIONS
Plate position Withdrawal (%)
CR-1 83.3
CR-2 0.0
CR-3 0.0
CR-4 85.0
CR-5 86.6
TABLE 18.  DIFFERENTIAL CONTROL AND REGULATING PLATE WORTH
ROD-A → CR-5 ROD-B1 → CR-1 ROD-B2 → CR-4 Reactivity ($)
Initial Final Initial Final Initial Final FC-1 FC-2 FC-3 Average
86.6 94.5 83.3 83.3 85 82.8 0.099 949 0.097 905 0.099 187 0.099 014
94.5 100 83.3 82.6 82.8 82.8 0.037 068 0.036 118 0.036 277 0.036 488
Note: FC — fission chamber.
TABLE 19.  REACTOR STATE DURING CONTROL ROD MEASUREMENTS
Coolant temp. 20.0°C
Reflector temp. 19.5°C
Core Fresh fuel/cycle 001
Cold neutron source Standby operation mode
3. KINETIC PARAMETERS
The ratio of the effective delayed neutron fraction to the prompt neutron generation time was determined 
using the Feynman-α method. The core state used was cold BOC Cycle 001 with position C3 empty (i.e. only 
15 fuel assemblies in the core). The experimentally determined value for α was 38.1 s−1. The critical control rod 
configuration is indicated in Table 20.
14
TABLE 20.  CRITICAL CONTROL AND REGULATING PLATE POSITIONS FOR 
PROMPT NEUTRON DECAY CONSTANT MEASUREMENT
Plate position Withdrawal (%)
CR-1 100.0
CR-2 47.1
CR-3 80.0
CR-4 100.0
CR-5 0.0
4. OPERATIONAL DATA
The thermal power transferred to the primary cooling system, and the reflector cooling and purification 
system is defined as the reactor power for the Open Pool Australian Light Water (OPAL) reactor. The data are 
recorded automatically and are available to determine the power and burnup at any stage. In addition, the control 
rod positions are also recorded. All raw data were analysed and simplified for the purpose of producing data suitable 
for criticality and burnup calculations. Tables 21–26 provide information on the average reactor power and control 
rod positions at various times for six cycles. 
TABLE 21.  CYCLE 007 OPERATIONAL DATA (cont.)
Time  Reactor  Critical and regulating plate position (%)
(days) power  (MW) CR-1 CR-2 CR-3 CR-4 CR-5
0 0.00 85.07 23.47 23.10 84.97 49.90
0.58 0.69 85.06 23.47 23.10 85.17 67.54
0.92 0.00 85.05 40.06 40.02 85.06 23.31
1.02 2.41 85.05 40.06 40.02 84.91 22.10
1.08 0.00 85.00 40.00 39.91 85.01 25.41
1.80 5.81 85.00 40.00 39.91 85.01 66.20
1.92 0.00 85.04 45.99 55.02 85.06 62.62
2.79 9.99 85.04 70.60 69.04 85.06 20.09
2.83 0.00 85.00 84.23 84.75 84.96 35.21
2.96 14.36 85.00 62.32 63.95 84.96 21.01
3.00 0.00 84.98 78.05 79.87 85.07 22.34
4.04 19.26 84.98 77.54 81.56 84.93 21.00
5.08 18.74 84.98 84.08 84.55 84.93 21.31
6.13 18.80 84.98 84.08 84.55 84.93 28.33
7.51 18.78 84.98 84.08 84.55 84.93 31.74
9.42 0.00 85.02 85.03 84.87 84.97 26.59
9.92 1.10 85.02 62.12 64.18 84.97 21.03
9.96 8.26 85.02 57.27 62.72 84.97 21.03
10.21 14.76 85.02 72.65 63.33 84.97 21.03
15
TABLE 21.  CYCLE 007 OPERATIONAL DATA (cont.)
Time  Reactor  Critical and regulating plate position (%)
(days) power  (MW) CR-1 CR-2 CR-3 CR-4 CR-5
11.29 17.94 85.02 83.96 84.05 84.97 30.29
13.33 0.00 85.08 75.03 75.49 85.01 20.30
13.38 8.63 85.08 65.59 64.42 85.01 20.30
14.38 19.19 85.08 84.01 84.00 85.01 31.92
14.63 14.49 85.08 84.01 84.00 85.01 33.08
17.32 0.00 84.97 58.67 58.16 85.12 20.06
18.13 18.73 84.97 83.99 84.09 85.12 29.85
19.08 18.75 84.97 83.99 84.09 85.12 37.51
20.17 18.75 84.97 83.99 84.09 85.12 39.13
21.25 18.75 84.97 83.99 84.09 85.12 40.44
22.42 18.77 84.97 83.99 84.09 85.12 42.00
23.27 18.76 84.97 83.99 84.09 85.12 42.86
25.29 0.00 85.17 85.13 84.90 85.05 29.14
25.33 13.52 85.17 70.97 71.01 85.05 20.12
26.42 18.97 85.17 83.91 83.97 84.91 40.92
27.58 18.93 85.17 84.06 83.97 84.91 42.97
28.75 18.99 85.17 84.06 83.97 84.91 43.08
29.92 19.54 85.17 84.06 83.97 84.91 43.19
31.25 19.60 85.17 84.06 84.11 84.91 43.10
32.46 19.59 85.17 84.06 84.11 84.91 43.19
33.71 19.55 85.17 84.06 84.11 84.91 43.57
34.92 19.43 85.17 84.06 84.11 84.91 44.20
36.13 19.37 85.17 84.06 84.11 84.91 44.95
37.46 19.40 85.17 84.06 84.11 84.91 46.73
38.83 18.70 85.17 84.06 84.11 84.91 49.03
TABLE 22.  CYCLE 008 OPERATIONAL DATA (cont.)
Time  Reactor  Critical and regulating plate position (%)
(days) power  (MW) CR-1 CR-2 CR-3 CR-4 CR-5
-20 0 n.a.a n.a.a n.a.a n.a.a n.a.a
0 0 85.02 41.9 41.02 84.98 20.07
0.26 5.22 85.77 51.07 49.90 84.98 20.04
0.68 5.27 85.77 62.83 60.99 84.98 20.02
1.18 18.03 85.77 66.31 66.90 84.98 20.01
16
TABLE 22.  CYCLE 008 OPERATIONAL DATA (cont.)
Time  Reactor  Critical and regulating plate position (%)
(days) power  (MW) CR-1 CR-2 CR-3 CR-4 CR-5
1.68 18.03 85.77 69.77 76.22 84.98 19.99
2.68 18.01 85.77 72.80 76.22 84.98 19.97
3.68 17.95 85.77 74.07 76.22 84.98 19.87
4.68 17.92 85.77 76.78 76.22 84.98 19.84
5.68 19.26 85.77 80.57 76.22 84.98 19.81
6.68 19.46 85.77 83.93 78.37 84.98 19.81
7.80 19.32 85.09 84.09 84.00 84.98 22.02
10.97 0.00 85.06 48.30 48.70 85.08 20.16
11.80 18.61 85.06 80.20 79.93 85.08 20.17
12.05 9.94 85.06 84.09 83.99 85.08 41.00b
13.13 0.00 85.13 85.08 85.09 85.01 57.14
13.84 8.76 85.04 54.69 54.52 85.08 48.33
14.47 18.46 85.04 77.34 81.91 85.08 21.45
35.09 0.00 85.05 47.80 48.17 85.10 20.12
35.51 18.13 85.05 72.87 70.85 85.10 20.15
36.59 18.39 85.05 84.08 84.01 85.10 27.72
37.68 18.26 85.05 84.08 84.01 85.10 29.48
38.76 19.14 85.05 84.08 84.01 85.10 31.67
39.84 19.31 85.05 84.08 84.01 85.10 34.39
40.97 18.71 85.05 84.08 84.01 85.10 37.22
42.05 19.41 85.05 84.08 84.01 84.96 39.72
43.13 19.39 85.05 84.08 84.01 84.96 42.37
44.22 19.40 85.05 84.08 84.01 84.96 44.52
45.30 19.37 85.05 84.08 84.01 84.96 46.69
46.38 19.35 85.05 84.08 84.01 84.96 49.12
47.47 19.66 85.05 84.08 84.01 84.96 51.09
48.55 19.78 85.05 84.08 84.01 84.96 53.64
49.63 19.80 85.05 84.08 84.01 84.96 56.10
50.72 19.77 85.05 84.08 84.01 84.96 59.15
51.05 19.79 85.05 84.08 84.01 84.96 59.79
a n.a.: not applicable.
b CR5 dropped causing power and xenon transient.
17
TABLE 23.  CYCLE 009 OPERATIONAL DATA
Time Reactor power Critical and regulating plate position (%)
(days) (MW) CR-1 CR-2 CR-3 CR-4 CR-5
-11 0.00 n.a.a n.a.a n.a.a n.a.a n.a.a
0 0.00 85.06 38.04 38.09 85.05 20.14
0.04 4.84 85.06 40.86 39.66 85.05 20.15
0.83 17.81 85.06 69.50 65.90 85.05 20.19
3.91 0.00 85.09 38.18 39.48 85.04 20.19
4.04 11.88 85.09 41.53 44.02 84.89 20.19
4.58 17.73 85.09 62.20 63.91 84.89 20.19
5.75 17.72 85.07 73.82 68.60 84.92 20.19
6.87 18.83 85.07 73.82 70.82 84.92 20.19
7.91 19.26 85.07 73.82 72.92 84.92 20.20
8.91 20.04 85.07 73.82 80.22 84.92 20.21
9.91 20.08 85.07 75.89 83.84 84.92 20.21
10.91 20.04 85.07 80.39 83.84 84.92 20.21
11.91 20.01 85.07 83.88 84.04 84.92 21.00
11.96 2.62 85.07 85.10 84.87 84.92 68.18
12.00 14.50 85.07 85.10 84.87 84.92 45.71
13.04 19.93 85.07 83.97 84.87 84.92 23.18
14.08 19.97 85.11 84.03 84.91 84.99 26.58
15.12 19.95 85.11 84.03 84.91 84.99 29.22
16.16 19.95 85.11 84.03 84.91 84.99 31.47
17.21 19.92 85.11 84.03 84.91 84.99 33.59
18.25 19.93 85.11 84.03 84.91 84.99 35.54
19.29 19.91 85.11 84.03 84.77 84.99 37.63
20.33 19.91 85.11 84.03 84.77 84.99 39.66
21.41 19.13 85.11 84.03 84.77 84.99 41.47
22.46 19.87 85.11 84.03 84.77 84.99 43.36
23.50 19.70 85.11 84.03 84.77 84.99 44.95
24.54 19.67 85.11 84.03 84.77 84.99 46.65
25.58 19.69 85.11 84.03 84.77 84.99 48.56
26.62 19.64 85.11 84.03 84.77 84.99 50.43
27.66 19.60 85.11 84.03 84.77 84.99 52.48
28.71 19.60 85.11 84.03 84.77 84.99 54.82
29.67 19.58 85.11 84.03 84.77 84.99 57.29
a n.a.: not applicable.
18
TABLE 24.  CYCLE 010 OPERATIONAL DATA (cont.)
Time Reactor power Critical and regulating plate position (%)
(days) (MW) CR-1 CR-2 CR-3 CR-4 CR-5
-16.00 0.00 n.a.a n.a.a n.a.a n.a.a n.a.a
0.00 0.00 84.90 33.10 33.10 84.90 20.00
0.83 5.15 85.16 50.03 59.40 85.00 20.04
1.96 13.77 85.16 60.36 66.77 85.00 20.04
3.04 19.06 85.16 69.11 62.56 85.00 20.04
4.33 19.48 85.16 69.11 67.47 85.00 20.05
5.71 19.46 85.16 69.11 72.32 85.00 20.05
5.75 7.07 85.37 85.07 74.57 85.12 36.80
5.79 15.71 85.37 85.07 77.28 85.12 22.64
6.83 19.49 85.32 70.97 73.90 84.98 20.05
7.96 19.48 85.32 79.32 69.99 84.98 20.07
8.92 19.46 85.32 79.32 73.93 84.98 20.07
9.88 19.44 85.32 79.32 77.86 84.98 20.08
9.92 13.39 85.32 79.32 78.03 84.98 20.08
9.96 0.00 85.16 84.95 84.96 85.01 71.84
10.00 16.35 85.02 84.95 84.96 84.01 42.13
11.17 18.36 85.14 83.48 75.24 85.09 20.91
12.25 18.44 85.14 83.48 81.37 85.09 20.91
13.33 18.39 85.14 84.82 84.07 85.09 21.22
14.42 18.39 85.14 84.13 84.04 84.94 23.03
15.38 18.38 85.14 84.13 84.04 84.94 25.43
16.50 18.25 85.14 84.13 84.04 84.94 27.42
17.63 18.43 85.14 84.13 84.04 84.94 29.83
18.58 18.39 85.14 84.13 84.04 84.94 31.03
18.63 13.86 85.14 84.13 84.04 84.94 31.05
23.29 0.00 85.10 51.70 49.83 85.02 20.25
23.79 9.97 85.10 80.68 75.27 84.88 20.23
23.96 17.31 85.10 78.84 72.91 85.03 20.09
25.00 19.36 85.10 84.92 84.04 85.03 33.30
26.13 18.09 85.10 84.92 84.04 85.03 33.00
27.21 18.31 85.10 84.92 84.04 85.03 35.68
28.33 18.23 85.10 84.77 84.04 85.03 38.32
29.46 18.22 85.10 84.77 84.04 85.03 40.83
30.67 18.69 85.10 84.77 84.04 85.03 44.21
31.71 19.18 85.10 84.77 84.04 85.03 46.28
32.79 19.15 85.10 84.77 84.04 85.03 49.15
19
TABLE 24.  CYCLE 010 OPERATIONAL DATA (cont.)
Time Reactor power Critical and regulating plate position (%)
(days) (MW) CR-1 CR-2 CR-3 CR-4 CR-5
33.38 19.17 85.10 84.77 84.04 85.03 51.10
33.42 18.21 85.10 84.77 84.04 85.03 52.66
a n.a.: not applicable.
TABLE 25.  CYCLE 011 OPERATIONAL DATA (cont.)
Time Reactor power Critical and regulating plate position (%)
(days) (MW) CR-1 CR-2 CR-3 CR-4 CR-5
-6.00 0.00 n.a.a n.a.a n.a.a n.a.a n.a.a
0.00 0.00 84.97 30.43 30.93 85.04 20.11
0.04 6.27 84.97 33.80 30.93 85.04 20.09
0.08 13.59 84.97 39.07 30.93 84.89 20.09
0.71 17.96 84.97 60.87 57.21 84.89 20.07
1.37 17.87 84.97 60.87 68.74 84.89 20.07
2.08 17.96 84.97 60.87 70.42 84.89 20.07
3.12 18.82 84.97 60.76 70.55 84.89 20.01
4.21 18.73 84.97 63.25 70.56 84.75 20.03
5.25 18.76 84.97 66.44 70.56 84.75 20.05
6.33 18.76 84.97 70.16 70.56 84.75 20.03
7.37 18.78 84.97 73.80 70.56 84.75 19.91
8.46 18.78 84.97 77.84 70.56 84.75 20.10
9.54 18.78 84.97 80.24 72.34 84.75 20.11
10.58 18.75 84.97 80.24 75.79 84.75 20.12
11.67 18.72 84.97 80.24 79.98 84.75 20.12
12.71 18.70 84.97 80.26 83.90 84.75 20.13
13.79 18.70 84.97 83.70 83.92 84.75 20.30
14.87 18.69 84.97 83.99 84.42 84.75 23.25
15.42 18.70 84.97 83.99 84.42 84.75 24.28
15.46 14.12 84.97 83.99 84.42 84.75 24.24
15.50 3.66 85.00 85.18 85.11 85.33 65.20
15.54 16.20 85.00 85.18 85.11 85.33 41.03
15.79 18.48 85.00 84.22 85.11 85.33 22.31
15.83 4.86 85.00 84.22 85.11 85.33 22.61
17.75 0.00 84.84 70.50 72.37 84.94 20.03
17.79 4.79 84.84 68.80 62.64 84.94 20.08
18.92 17.71 84.84 83.94 84.00 84.94 26.55
20
TABLE 25.  CYCLE 011 OPERATIONAL DATA (cont.)
Time Reactor power Critical and regulating plate position (%)
(days) (MW) CR-1 CR-2 CR-3 CR-4 CR-5
19.96 18.59 84.84 83.94 84.00 84.94 29.64
21.08 18.61 84.84 83.94 84.00 84.94 31.14
21.75 18.63 84.84 83.94 84.00 84.94 32.37
21.79 14.55 84.84 83.94 84.00 84.94 32.20
21.83 7.79 85.00 85.02 84.83 85.04 55.67
21.87 15.93 85.00 85.02 84.83 85.04 42.92
23.04 18.58 85.00 84.88 84.83 85.04 31.62
23.08 6.68 85.05 85.19 85.09 84.98 53.64
23.12 17.19 85.05 85.19 85.09 84.98 40.12
24.21 18.44 85.05 85.19 85.09 84.98 33.12
25.25 18.64 85.05 85.19 85.09 84.98 35.00
26.29 18.78 85.05 85.19 85.09 84.98 37.29
27.37 18.76 85.05 85.19 85.09 84.98 39.34
28.46 18.74 85.05 85.19 85.09 84.98 41.00
29.54 18.71 85.05 85.19 85.09 84.98 43.69
29.96 18.58 85.05 85.19 85.09 84.98 44.16
31.46 0.00 84.99 85.03 84.98 85.06 79.57
31.50 1.71 84.99 85.03 84.98 85.06 65.39
31.54 15.62 84.99 85.03 84.98 85.06 21.95
31.83 17.87 84.99 81.57 83.96 85.06 20.90
31.87 8.37 85.00 50.03 59.98 85.02 20.18
31.92 2.67 85.00 84.99 84.88 85.02 54.38
31.96 16.99 85.00 84.99 84.88 85.02 34.86
33.00 18.20 85.00 84.99 84.88 85.02 44.96
34.08 18.45 85.00 84.99 84.88 85.02 47.63
35.17 18.43 84.86 84.99 84.88 84.88 49.40
36.25 18.43 84.93 84.99 84.92 84.90 51.93
37.33 18.47 84.93 84.99 84.92 84.90 54.28
38.42 18.46 84.93 84.99 84.92 84.90 57.29
38.62 18.19 84.93 84.99 84.92 84.90 57.81
a n.a.: not applicable.
21
TABLE 26.  CYCLE 012 OPERATIONAL DATA
Time Reactor power Critical and regulating plate position (%)
(days) (MW) CR-1 CR-2 CR-3 CR-4 CR-5
-4.00 0.00 n.a.a n.a.a n.a.a n.a.a n.a.a
0.00 0.00 84.99 37.15 36.32 85.02 20.08
0.27 17.94 84.99 50.91 55.20 85.02 20.20
0.52 17.92 84.99 62.91 60.82 85.02 20.19
1.10 17.89 84.99 70.73 68.71 85.02 20.20
1.69 17.89 84.99 70.73 69.56 85.02 20.19
2.27 18.78 84.99 70.73 73.30 85.02 20.19
3.40 18.82 84.99 70.73 77.47 85.02 20.19
4.44 18.84 84.99 71.76 80.62 85.02 20.19
5.48 18.83 84.99 75.55 80.62 85.02 20.20
6.56 18.83 84.99 79.38 80.62 85.02 20.20
7.60 18.78 84.99 84.05 81.31 85.02 20.21
8.69 18.60 84.99 85.00 84.07 85.02 22.07
9.31 18.09 84.99 84.46 84.07 85.02 21.04
9.36 13.98 84.99 85.19 85.04 85.02 33.38
15.19 0.00 85.09 49.46 45.27 84.96 20.04
15.23 13.87 84.95 50.45 51.42 84.96 20.00
16.40 17.48 85.06 83.97 84.05 85.05 23.76
17.44 18.68 85.06 84.11 84.05 85.05 26.74
18.52 18.72 85.06 84.11 84.05 85.05 28.08
19.60 18.70 85.06 84.11 84.05 85.05 29.67
20.65 18.69 85.06 84.11 84.05 85.05 31.83
21.73 18.67 85.06 84.11 84.05 85.05 33.83
22.81 18.66 85.06 84.11 84.05 85.05 35.76
23.85 18.65 85.06 84.11 84.05 85.05 37.67
24.94 18.64 85.06 84.11 84.05 85.05 39.06
26.02 18.61 85.06 84.11 84.05 85.05 41.11
27.10 18.59 85.06 84.11 84.05 85.05 42.79
27.53 18.59 85.06 84.11 84.05 85.05 43.62
29.02 0.00 85.04 85.13 84.93 85.14 79.10
29.06 6.73 85.04 85.13 84.93 85.14 45.09
30.15 18.37 85.04 84.03 84.00 85.14 41.71
31.19 18.84 85.04 84.03 84.00 85.14 45.89
32.23 18.82 85.04 84.03 84.00 85.14 47.29
33.31 18.81 85.04 84.03 84.00 85.14 49.41
34.15 18.79 85.04 84.03 84.00 85.14 50.91
a n.a.: not applicable.
22
The average reactor power is averaged from the previous time period to the present time period. The control 
rod positions are instantaneous at the stated time. For cycles 008–012, the first time indicates the time shutdown 
(no power) between the current and the previous cycle (see Tables 22–26). The data provided were significantly 
simplified for the purpose of presenting in a concise format, and although care was taken to preserve the accuracy, 
some concessions have been made. In particular, some operational issues resulted in the uncoupling of control rods 
that temporarily shut down the reactor. This in turn resulted in significant power and xenon transients. To provide 
all the data necessary to accurately capture this would result in a significant increase in the data with no impact on 
the global burnup calculations and so some detail was sacrificed in terms of reactor power evolution.
During operation of cycles 007–012, the reactor experienced minor light water leakage into the reflector 
vessel. The result of this was a continuing change in the heavy water purity during this time. Following cycle 009, 
the heavy water inventory was replaced with virgin heavy water. The average heavy water purity over each cycle is 
provided in Table 27. The purity was determined using a Fourier transform infrared spectrophotometer.
TABLE 27.  HEAVY WATER PURITY DURING OPERATIONAL CYCLES
Cycle D2O purity (wt%)
007 97.5
008 97.1
009 96.9
010 99.55
011 99.24
012 98.93
During operation, the reactor coolant inlet temperature is nominally at 36°C (controlled by a feedback 
temperature loop). The outlet temperature is 44°C at 20 MW, and the temperature difference can be assumed to be 
proportional to the reactor power. At startup (beginning of cycle), the temperature can be assumed to be 21°C. The 
cold neutron source was in normal operation mode.
The fuel management strategy and core loading for the operational cycles are provided in Table 28.
TABLE 28.  FUEL MANAGEMENT STRATEGY AND LOADING FOR THE 
OPERATIONAL CYCLES (cont.)
Cycle Fuel assembly load and management
007 Fresh ~484 g U-235/FA loaded at position B4, D2 and A2
Fresh ~383 g U-235/FA loaded at position C3, A3, D1, C4, C2 and A1
Fresh ~212 g U-235/FA loaded at position D4, D3, C1, B3, A4, B1 and B2
008 Fresh ~484 g U-235/FA to position D3 à B2 à Out
Fresh ~484 g U-235/FA to position A4 à B3 à Out
Fresh ~484 g U-235/FA to position B1 à Out
009 Fresh ~484 g U-235/FA to position D4 à B2 à Out 
Fresh ~484 g U-235/FA to position A3 à B3 à Out
Fresh ~484 g U-235/FA to position C1 à Out
010 Fresh ~484 g U-235/FA to position C4 à B3 à Out 
Fresh ~484 g U-235/FA to position D1 à C2 à Out
Fresh ~484 g U-235/FA to position A1 à B2 à Out 
011 Fresh ~484 g U-235/FA to position C3 à Out
Fresh ~484 g U-235/FA to position A3 à B3 à Out
Fresh ~484 g U-235/FA to position D1 à C2 à B2 à Out
23
TABLE 28.  FUEL MANAGEMENT STRATEGY AND LOADING FOR THE 
OPERATIONAL CYCLES (cont.)
Cycle Fuel assembly load and management
012 Fresh ~484 g U-235/FA to position B4 à Out
Fresh ~484 g U-235/FA to position D2 à B2 à Out
Fresh ~484 g U-235/FA to position A2 à Out
Note: T he short hand D3 à B2 à Out means take the fuel assembly in B2 out, move D3 to B2 and load a fresh 
fuel assembly into D3.
24