ML20081B007
| ML20081B007 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 02/28/1995 |
| From: | Hassler L, Wittkopf W FRAMATOME COGEMA FUELS (FORMERLY B&W FUEL CO.) |
| To: | |
| Shared Package | |
| ML20081A991 | List: |
| References | |
| BAW-2209, BAW-2209-R01, BAW-2209-R1, NUDOCS 9503150378 | |
| Download: ML20081B007 (81) | |
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B&W FuelC6w@y 7
An American Company With l
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i BAW-2209 Ryision 1 g
Crystal River Unit 3 Spent Fuel Storage Pool B g-Criticality Analysis I
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I February 1995 I
W. A. Wittkopf l
L.A. Hassler i
I l-l B&W Fuel Company P.O. Box 10935 l
Lynchburg, Virginia 24506-0935 i
I
O Ol R&W Fuel Campany BAW-2209. Rev 1 E:
Ii Record Of Revisions Revison Dale Desciriotion 0
October,1993 Initial Release 1
February,1995 Remove proprietary statement, corrections to pages 31 and 33.
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i B&W Fuel Company BAW-2209. Rev 1 g
ABSTRACT I
This mport describes a criticality analysis for the Crystal River Unit 3 Spent Fuel Pool B storage racks. It was performed to allow a fuel enrichment increase up to 5.0 wt% U235 (nominal). The Pool B racks consist of two regions. The results of this analysis for Region l
I show that a nominal fuel enrichment of 5.0 wt% U235 is allowed in a checkerboard pattern of fresh fuel with spent fuel. Region 2 requires specified minimum spent fuel burnup limits.
Bumup versus enrichment curves are provided that specify the loading requirements for both regions.
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n i_m B&W Fuel Company BAW-2209. Rev 1 l
TABLE OF CONTENTS ABSTRACT............................................... iii 1.0 Discussion and Results 1
2.0 Analytical Methods......................................... 5 2.1 Analytical Requirements................................. 5 g
2.2 Computer Pmgrams and Validation.......................... 6 g
2.3 Reactivity Bias and Uncertainty............................ 9 2.4 Material Specifications.................................
12 3.0 Region 1 Rack Analysis....................................
17 3.1 Region 1 KENOIV Geometry Model
.......................17 g-3.2 Cell Uncertainty Evaluation
.............................17 E
3.3 Axial Burnup Shape Effects
.............................20 3.4 Axial Boraflex Shrinkage Effects
..........................21 g
3.5 Misplaced Fuel Assembly...............................
21 5
3.6 Checkerboard Fuel Rack Analysis..........................
21 4.0 Region 2 Rack Analysis....................................
25 4.1 Region 2 KENOIV Geometry Model
.......................25 4.2 Cell Uncertainty Evaluation
.............................25 4.3 Axial Boraflex Shrinkage Effects
..........................28 4.4 Misplaced Fuel Assembly...............................
28 4.5 Axial Bumup Shape Effects
.............................28 4.6 Burned Fuel Analysis
.................................30 5.0 Conclusions............................................ 33 6.0 References
............................................35 I
Appendix A. Region 2 Axial Burnup Profile Discussion...................
37 A.1 Axial Pmfile Generation...............................
37 A.2 Minimum Burnup Versus Enrichment Interpolation Method.........
51 Appendix B. KENOIV Input File Listings............................
54 g
B.1 Region 1 Sample KENOIV Input Files.......................
54 5
B.2 Region 2 Sample KENOIV Input Files.......................
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E B&W Fuel Company BAW-2209. Rev 1 h
- List of Tables h
Table' l.
Minimum Fuel Bumup versus Initial Enrichment Table '.............. 4
' Table 2. -KENOIV Benchmark Results 8-Table 3.
Basis Fuel Assembly Specifications.......-.................... _13
{
Table 4.
Fmsh Fuel Concentrations Vs U235 Enrichment..................
14
- Table 5.
Region 1 Average Burnup Number Densites Versus Enrichment......... 14 -
' Table 6.
Region 2 Axial Number Densities For 5.05 Wt % Initial' Enrichment 45 GWD/MTU Average Burnup....................
15 Table 7. - Non-Fuel Material Densities..............................
16 g
. Table 8.
Region I Rack Cell Dimensions............................. - 19 Table 9.
Summary of Bias and Tolerance Penalties and Uncertainties Applied To Region 1............................................ 2 2.
Table 10. Region 2 Bumup Versus Enrichment Results..................... 24 Table 11. Region 2 Rack Cell Dimensions
...........................27 Table 12. Summary of Bias and Tolerance Penalties and Uncertainties Applied To l
Reg ion 2............................................ 30 Table 13. Burnup Versus Enrichment Values for Region 2.................
31 Table 14. Minimum Top and Bottom and Bounding Axial Burnup Profiles........
39 -
Table 16. Axial Number Densities, 2.0 Wt%, 8 GWD/MTU................
46 Table 17. Axial Number Densities, 2.4 Wt%,15 GWD/MTU...............
47 Table 18. Axial Number Densities, 3.2 Wt%, 25 GWD/MTU................ ' 48 Table 19. Axial Number Densities, 4.1 Wt%, 35 GWD/MTU...............
49 Table 20. Axial Number Densities, 5.0 Wt%, 45 GWD/MTU...............
50 List of Figures Figure 1.
Minimum Fuel Burnup versus Initial Enrichment.................. 2
~ Figure 2.
Minimum Fuel Burnup versus Initial Enrichment.................. L3 Figure 3.
KENOIV versus Experiment 9
Figure 4.
Region 1 Rack Cell Schematic............................
18 Figure 5.
Region 1 KENOIV Model Schematic........................
19 -
Figum 6.
Region 2 Rack Cell Schematic.............................. 26 -
Figure 7.
Region 2 KENOIV Model Schematic........................
27.
Figure 8.
0 - 10 GWD/MTU Axial Pmfiles..........................
41 Figure 9.
10 - 20 GWD/MTU Axial Profiles.........................
42 Figure 10. 20 - 30 GWD/MTU Axial Profiles.........................
43
' Figure 11. 30 - 40 GWD/MTU Axial Profiles..........................
44 -
Figure 12. 40 - 50 GWD/MTU Axial Pmfiles.........................
45 Figure 13. dk/dE Versus Bumup Interpolation Curve.....................
53 Figure 14. KENOIV Region 1 Box Geometry Model.....................
55 Figure 15. KENOIV Region 2 Box Geometry Model.....................
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OI D&W Fuel Company BAW-2209. Rev 1 l
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B&W Fuel Company BAW-2209. Rev 1 1.0 Discussion and Results This document describes the analysis performed to support a fuel enrichment limit increase for the Florida Power Corporation Crystal River 3 Spent Fuel Pool B.
These racks consist I
of two regions. Region I currently allows a uniform loading of up to 4.2 wt% U235 fresh fuel in all positions. Region 2 contains all spent fuel with a maximum initial enrichment of 4.2 wt%. The results of this analysis show that a fuel enrichment increase up to 5.0 wt%
U235, nominal, is allowed provided that specified minimum assembly burnup limits are met.
A Region I checkerboard pattern will allow up to 5.05 wt% fresh fuel and bumed fuel. The Region 1 requied minimum burnup versus initial fuel enrichment curve for the burned fuel is shown in Figure 1. The calculated burnup versus enrichment values are listed in Table 1.
For Region 2, the results show that burned fuel with initial enrichments up to 5.05 wt%
U235 can be safely stored. For the Region 2 bumed fuel, the required minimum bumup versus initial fuel enrichment curve is shown in Figure 2. The calculated values are also listed in Table 1.
The analysis explicitly examined only the deboration accident since the borated pool water provides sufficient reactivity margin to mitigate any effect from the other credible accidents.
The analytical models were optimized with respect to fuel, modemtor, structural, and fabrication variables. This will provide the maximum credible rack multiplication factor to ensure confonnance with criticality safety requirements. It is noted that the Region 2 burnup versus enrichment curve is more conservative than the similar curve from the previous analysis due to increased penalties for potential Boraflex gap formation and the non-unifonn axial fuel bumup profile.
l I i
Ua B&W Fuel Company BAW-2209. Rev 1 Figure 1.
Minimum Fuel Burnup versus Initial Enrichment g
Region 1 of CR3 Spent Fuel Pool B Burned Fuel Checkerboarded with 5.0 wt% Fresh Fuel I
35.0 30.0 80
/
25 20.0 m
/
- 15.0
/
I
- E $,Q 0.0 - - =
2.0 2.5 3.0 3.5 4.0 4.5 5.0 Initial Enrichment. wi% U235 I
The area above the curve represents burned fuel which can be safely stored in Region 1 of Pool B adjacent to fresh fuel with enrichments up to 5.0 weight percent. It is pointed out that these points have an additional contingency safety margin of 0.0088 Ak which is equivalent to approximately 0.14 in enrichment. An equation for the curve is given by:
I B=0 0.00 s E s 2.08 l
B = 13.00(E-2.08) - 0.90(E-2.08)2 2.08 s E s 5.00 Note that burned fuel with characteristics that fall below this line many be checkertoarded with fuel with characteristics above the line..a
1 r
F B&W Fuel Company BAW-2209. Rev 1 p
Figure 2.
Minimum Fuel Burnup versus Initial Enrichment Region 2 of CR3 Spent Fuel Pool B All Burned Fuel
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L 45 f
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/
40 35 t
g 7
e 30 l
cl g 25 f t 20 z
/
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d
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f 5 10
/
b 5
t o
'1.5 2
2.5 3
3.5 4
4.5 5
5.5 initial Enrichment, wt% U235 I
I.
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The area above the curve represents burned fuel which can be safely stored in Region 2 of
{
Pool B. An equation for the line curve is given by:
B=0 0.00 $ E s 1.63 B = 22.06(E-1.63) 1.63 s E s 2.31 B = 15.00 + 12.90(E-2.31) - 0.87(E-2.31)2 2.31 s E s 5.20 Note that fuel with chacteristics below the line may be stored in region 1 or adjacent to l l l
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I' B&W Fuel Company BAW-2209. Rev 1 waterholes.
Table 1.
Minimum Fuel Burnup versus Initial Enrichment Table l
Region 1 of CR3 Spent Fuel Pool B Burned Fuel Checkerboarded with 5.0 wt% Fresh Fuel Initial Enrichment Minimum Burnup g[
(wt % U235)
(GWD/MTU) g 2.08
. 0.0 gi 3.00 11.2 5
4.00 20.2 5.00 30.3 I,
Region 2 of CR3 Spent Fuel Pool B All Burned Fuel Initial Enrichment Minimum Burnup (wt % U235)
(GWD/MTLD 1,63 0.0 2.04 8.0 2.31 15.0 3.20 25.0 l;
4.07 35.0 5.20 45.0 I:
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- T' B&W Fuel Company BAW-2209. Rev 1 l
L2.0s Analytical Methods j
i s,
This'section describes the analytical requirements for the rack analysis, the computer j
programs used and their validation, the determination of reactivity bias, the material i
specifications for all materials used in the analysis, and the generation of the KENOIV
)
neutron cross sections.
j
' l 2.1 Analytical Requirements -
Criticality of the fuel assemblies in the'CR3 fuel storage racks is prevented both by a j
combination of rack design which limits fuel assembly interaction and administrative controls
(
which limit the maximum reactivity of the fuel.f The rack fuel cells have a fixed minimum j
. separation and a neutron absorbing material (Boraflex) between the fuel cells. The _ criticality analysis for the racks conforms to ANSI /ANS standards'33. The design basis for preventing criticality in the rack is based upon'a 95 % probability at a 95 % confidence level that the rack -
Larray mukiplication factor (Ke) will be less than 0.95 when loaded with fuel and flooded
- with unborated water. Tabulated below are the conservative conditions used to meet the i
design basis:
t i
'1.
The fuel assembly 'contains the highest U235 enrichment authorized, no U234, and is j
i.
at its most reactive' position in the cell. For burned fuel, no credit is taken for I
PM149 at shutdown which decays to SM149 (a significant fission product poison).
l The fuel assembly is modeled with water replacing the assembly grid volume.
2.
The moderator is pure water of density 1.0 g/cc, contains no dissolved boron, and is.
]
at the pool temperature which yields the highest reactivity.
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3.
i
' The storage cell nominal geometry was obtained from information supplied by Florida
}
Power Corporation' for Region I and Region 2, respectively.
4.
The nominal case calculation is infinite in lateral extent and finite in axial extent with' I
'the top' and bottom reflectors modeled with 12 inches of water.
t 5.
Uncertainties due to mechanical and structural tolerances are treated by choosing l j
" worst case" conditions to bound all cases. These include ite.ms such as sts.inless steel thickness, cell ID, cell pitch, water temperature, boron poison concentration, etc.
n.
- 6.'
Credit is taken for neutron absorption in full length structural ~ materials and installed fixed neutron poison (Boraflex).' However, a minimum boron poison concentration is :
used, and a bias is included for particle self-shielding and potential vertical gap q l
. t i
f i
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I, BlkW Fuel Company BAW-2209. Rev 1 formation h isoraflex.
Accidents can be postulated which would incease reactivity beyond the acceptable value if no boron in the water is assumed. The worst credible accident is mistoading a fresh (or low bumup) fuel assembly into a non-allowed positon. However, according to NRC Reg Guide 5
1.13 one is not required to assume two or mon unlikely, independent, concurrent events to pmtect against a criticality accident. Thus, for this accident, we can assume the presence of soluble boron in the pool water, and then the cakulated reactivity is well below 0.95.
Another postulated accident is the " optimum moderation" or " misted water" condition. This is not applicable to the CR3 pool B racks because the presence of fixed Boraflex poison l,'
prevents the reactivity increase normally associated with this condition and the reactivity decreases monotonically with water density decrease.
2.2 Computer Programs and Validation The KENOIV Monte Carlo program
- was used for the absolute reactivity analysis of the rack 7
configurations. The NITAWL program was used along with the 123-group master neutron cross section library generated by Cable' to prepare the KENOIV neutmn cross section g,
libmry. The CASMO3 program' was used to detennine tolerance effects, temperature 5
effects, and fuel burnup isotopics. The NEMO pmgram" was used to obtain the relative axial burnup profiles as a function of fuel burnup for use in determining the non-uniform g'
burnup effects. Brief descriptions of the programs are as follows:
R.
- 1. The KENOIV program is a multigroup Monte Carlo program that allows relatively g
simple description of complex geometries. This code calculates the reactivity of the 5
modeled system and its associated statistical uncertainty.
- 2. The NITAWL pmgram processes cross sections for use with KENOIV. It provides resonance self-shielding corrections to the basic 123-gmup cross sections that were used in this study. The neutron resonance self-shielding calculation employs the Nordheim Integral treatment.
- 3. The CASMO3 program is a multigroup two-dimensional transport theory program for bumup calculations on LWR assemblies or simple pin cells. The code handles a geometry consisting of cylindrical fuel rods of varying composition in a square pitch array. It is primarily used at BWFC to generate cross sections for fuel cycle analysis but simple fuel storage rack geometries can also be handled. The program is used for sensitivity studies and to pmvide depletion data for bumup credit.
.I.
- 4. The NEMO program is a 3-D fuel cycle analysis code which uses the Optimized Nodal Expansion Method to determine detailed core power pmfiles, and isotopic depletion as a function of core opemting history. It is used extensively at BWFC for fuel cycle licensing.a,
B&W Fuel Company BAW-2209. Rev 1 analyses.
Validation of the criticality methods and cross sections is accomplished by comparison with critical experiment data" for assemblies similar to those for which the racks are designed.
The KENOIV code with the 123 group cmss section library has been benchmarked against these critical experiments. The experiments were conducted at the Babcock and Wilcox Lynchburg Research Center to support close proximity storage of LWR fuel assemblies.
Various combinations of fuel assembly spacings and interspersed absorbing materials were examined in the experimental configumtions. All cases used water as the moderating material. The benchmarking data is sufficiently diverse to establish that the method bias and uncertainty will apply to rack conditions which include stmng absorbers and large water gaps.
Comparison of the calculated and measured data is shown in Table 2. From this analysis for j
the 21 B&W close spaced critical experiments, the average deviation of calculated KENO 4
]
criticality to measured data was 0.00673 and the mean squared deviation was 0.00664. The l
worst case underprediction of 0.01453 occurred at the largest cell separation of 2.576 inches.
L The data show that the KENOIV bias increases with increasing water gap between fuel l
assemblies. The maximum negative bias is 0.01 for water gaps less than 1.932 inches and is r
positive for water gaps less than 0.644 inches. A graph of the comparison of calculated to L
measured reactivity is given in Figure 3.
[
The CASMO3 program is used here only to determine tolerance (perturbation) effects and to generate bumup isotopics for input to KENOIV. CASMO3 is currently used extensively throughout the nuclear industry. It is also used, and has been benchmarked, at BWFC. The NEMO program is used here only to obtain the detailed axial burnup profiles as a function of l
fuel burnup. It has been benchmarked at BWFC for this application.
C,'
o B&W Fuel ComDany BAW-2209. Rev 1 I
I:
1 Table 2.
KENOIV Benchmark Results l'
Array Spacing Core ID KENOIV Calculated Measured Calc -
(inches)
No.
k,r,
Ia k rr Ia Meas Ak o
0.000 1
1.00447 0.00181 1.0002 (0.0005) 0.00427 i
II 1.00892 0.00168 1.0001 i (0.0005) 0.00882 0.644 III 0.99937 0.00149 1.0000 (0.0006)
-0.00063 IV 1.00669 0.00192 0.9999 (0.0006) 0.00679 XI 1.00242 i 0.00168 1.0000 i (0.0006) 0.00242 XIII 1.01025 i 0.00188 1.0000 i (0.0010) 0.01025 m
XIV 1.00405 0.00181 1.0001 (0.0010) 0.00395 gi XV 0.99596 0.00171 0.9998 (0.0016)
-0.00384 XVII 1.00015 0.00188 1.0000 (0.0010) 0.00015 E
XIX 1.00150 0.00176 1.0002 (0.0010) 0.00130 5
1.288 V
1.00189 i 0.00186 1.0000 i (0.0007) 0.00189 VI 1.00929 i 0.00187 1.0097 (0.0012)
-0.00041 g
XII 0.99691 0.00173 1.0000 i (0.0007)
-0.00309 E
XVI 0.99193 i 0.00200 1.0001' (0.0019)
-0.00817 i
XVIII 0.99139 0.00179 1.0002 (0.0011)
-0.00881 g,
XX 0.99193 0.00186 1.0003 (0.0011)
-0.00837 5
1.932 VII 0.99190 i 0.00192 0.9998 (0.0009)
-0.00790 VIII 1.00497 0.00190 1.0083 (0.0012)
-0.00333 g'
X 0.99182 0.00179 1.0001 (0.0009)
-0.00828 s
1
' 0.01016 XXI 0.98954 i 0.00159 0.9997 i (0.0015) g; 2.576 IX 0.98847 0.00185 1.0030 i (0.0009)
-0.01453 Ii Il
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B&W Fuel Company BAW-2209. Rev 1 Figure 3.
KENOIV versus Experiment 0.01S O.01, um 0.005, 5
h o
3
-0.005 m
=
-0.01
^'
' r. s ki, u,..
2 2.s 3
2.3 Reactivity Bias and Uncertainty The design basis for preventing criticality in the rack is based upon a 95% pmbability at a 95 % confidence level that the rack array multiplication factor, km, will be less than 0.95 when loaded with fuel and flooded with unborated water. The 95/95 one sided tolerance factor for a nonnal distribution is 1.763 times the standard deviation, o, for the number of histories generated for this analysis. The combined statistical uncertainty from different penalties, cmdits, and KENOIV statistical uncertainty is computed by the square root of the sum of the squares of the individual uncertainty components.
The following items are considered in determining the bias and uncertainty in the calculated results:
- 1. KENOIV Bias - The primary uncenainty is the inherent accuracy of the KENOIV pmgram with its associated cross section library. The pmgram has been benchmarked against critical experiments to obtain the calculational bias inherent in the results, see Table
- 2. This bias is applied to all reactivities calculated by KENOIV as a function of fuel assembly spacing in the storage rack. For Region 1 the spacing is less than 1.932 inches, so the KENOIV bias and uncertainty are taken as 0.010 i 0.00363. For Region 2, the spacing is less than 0.644 inches, so the KENOIV bias is positive. However, for conservatism, no credit is taken for this positive bias. _ - _ _ _ _ _ _ _ _ _
O C i i1
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B&W Fuel Company BAW-2209. Rev 1 l
- 2. Tolerance Effects - The reactivity of a fuel storage rack cell can be affected by material composition and dimenision tolerances, fabrication tolerances (cell pitch and width), and positioning of the fuel assembly within the cell. For Region 1 the " worst case" configuration (from a reactivity standpoint) was determined and used for all KENOIV reactivity calculations. Since this application is conservative for all cases, no additional tolerance uncertainty is required for Region 1.
For Region 2, the " worst case" tolerance was applied to all KENOIV results.
- 3. Temnerature Effects - The presence of the Boraflex poison plates prevents the reactivity from increasing due to the " misted" or " optimum moderation" effect, or from a temperature l
increase. As shown later in section 3.2, the maximum reactivity occurs at the lowest temperature which was taken as 50'F. For conservatism, all KENOIV calculations were done at 50 F and no bias is required for these effects.
- 4. Potential Borauex Gap - An assessment of Boraflex gap formation and poison g
performance in fuel storage racks has been documented by EPRI 2,".
The gaps appear to g
occur randomly and most are small with negligible effect on reactivity'. The latter EPRI document" states that the reactivity effect of gaps is demonstrated to be very small and when g
densification of Boraflex is considered, the reactivity effect is smaller yet, and is almost 5
within the statistical variations inherent in the determining method. It further states that "this result is not unexpected, as gap formation and growth represents no loss of baron from the g
system. The gap phenomenon merely results in a redistribution of the neutron absorber 3
material to a slightly less than optimum configuration. Accordingly, the reactivity effect due to Bomflex gaps should be accommodated within the existing design basis of most racks." In g
view of this assessment, there is probably no need to consider a Bomflex bias.
5 However, for conservatism, we will include the bias for the reactivity effect of large (4 inch) 3 gaps occurring at the same elevation in two adjacent Boraflex panels. The largest reactivity B
effect is caused by the largest gaps. First let us estimate the probability of this event occurring. Blackness testing of Boraflex panels showed that only 44% of the panels developed detectable gaps", and the largest gaps were on the order of 4 inches. The fraction of gaps 4 inches or larger is detennined to be 0.08. Thus the probability that a single panel fonns a 4-inch or larger gap is (0.44)(0.08) = 0.0352. The probability for two adjacent panels to fonn gaps at exactly the same elevation is vanishingly small. However, for conservatism, we will assume that if the gaps form within 10 inches of each other, they have the same effect as being at the same elevation. If the gaps are separated by more than 10 Subsequent to the completion of the calculations of this report, NRC Infonnation Notice 93-70: " Degradation of Boraflex Neutron Absorber Coupons," 09/10/93 was issued. Since the applicability and impact of this notice on the FPC storage racks has l
not been defined, no consideration of this infonnation is provided in this analysis. E,
(
MW_ Fuel Company BAW-2209. Rev 1 inches, the gap interaction effect is negligible'7 With this very conservative assumption, the probability of the event occurring is (0.0352)(0.0352)(20/140) = 0.000176. For more than two panels, the probability for 4-inch or larger gaps to occur within 10 inches of a fixed elevation is exceedingly small. This could be considered an unlikely event, which would allow for consideration of bomn in the pool water. The Boraflex bias is computed separately for each region using the above defined 4 inch gap assumption.
- 5. LBP History Effect - When a fuel assembly is depleted with lumped burnable poison (LBP) rods insened, the reactivity of the fuel assembly after the LBP rods are pulled is greater than the reactivity of a similar fuel assembly depleted without LBP rods to the same burnup. This is because of the greater conversion of U238 to fissile plutonium with LBP rods inserted.
For conservatism, all burned fuel analyzed for these racks has been burned with LBP rods insened. This provides a conservative reactivity bound for all cases, and no bias is required for this effect.
- 6. Non-Uniform Axial Bumuo - When a fuel assembly is burned in a nuclear reactor, the central axial portion of the assembly undergoes higher burnup than the top and bottom portions because of the non-uniform axial power profile. This could result in a negative bias E
relative to calculations using a unifonn axial burnup. For fresh fuel checkerboarded with spent fuel, calculations show that the bias is zero or slightly positive. For all spent fuel in a rack, the bias is negative. This bias is calculated separately for each region.
- 7. Boron Particle Self-Shielding - The negative bias due to neutron self-shielding in the Boraflex poison is relatively small, and has been determined in the previous rack analysis".
l These values are again used here. The bias for Region 1 is 0.0012Ak and for Region 2 is 0.0019ak.
Summary For any rack configuration, the calculated reactivity, bias, and uncertainty are combined as follows to give the maximum reactivity for the rack configuration.
1 l
kgf + A km, + / (1. 7 6 3 a ) ' + (1.76303) 3 K
=
ar c
whem K
= maximum reactivity for the rack configuration < 0.95.
mx k
= KENOIV calculated reactivity for the configuration.
ar __- __
o O=
i B&W Fuel Company BAW-2209. Rev 1 Aka, = sum of all bias values from the items listed above, o,
= statistically combined uncenainty (95/95) in the total bias from the items
.l' listed above.
a,
= 95/95 uncenainty in the KENOIV calculated reactivity.
I 2.4 Material Specifications I_
The materials used in the analysis includes the basis fuel assembly (BWFC MARK B9, 15x15), the pool water, the stainless steel (SS) can and wrapper, and the Boraflex poison material.
Except for the fuel enrichment, the specification of the basis fuel assembly (FA) is given in g
Table 3. Based upon a UO density of 10.2083 g/cc, the isotopic concentrations in the pellet g
2 for the various fresh fuel enrichments used in this analysis are given in Table 4.
For the Region 1 analysis, uniform average bumups as a function of initial enrichment are g
used. Table 5 pmvides the number densities for the examined burnups, Section 3.3 3
provides more detail for the Region 1 burnup requirements. For Region 2 axial burnup profiles are employed for the evaluation. Table 6 lists the' axial number density profile for g
an initial emichment of 5.05 wt% with an average burnup of 45 GWD/MT. Profiles for the 5
other enrichment /burnup combinations considered in the analysis are provided in Appendix A. Section 4.5 and Appendix A pmvides more detail of the generation and use of the axial g
burnup profiles.
W The number densities for the non-fuel materials are listed in Table 7. They are based upon the follow considerations.
1)
Ziracoly-4 is assumed to be composed of 100% zirconium.
2)
The composition of the pool water is taken at a conservative water density of 1.0 g/cc.
3)
For the KENOIV four quaner rack model, the instmment tube is homogenized with the water in the pin cell.
4)
The stainless steel can and wrapper are type SS 304LN ASME SA-240 cold mlled strip. The nominal composition" and atomic concentrations of the major components l-as used in this analysis are listed in Table 7. The combined weight fraction of minor components, i.e, carbon, phosphoms, sulfur, silicon, and nitrogen, is less than 0.01.
Since none are significant neutron absorbers, they were lumped with the Fe. The SS l B
=
-n 1
= ;;f B&W Fuel Company BAW-2209. Rev 1 2o
- 304 density is taken as 8.07 g/cc,
'5)
The EPRI Boraflex composition ' essentially used minimum concentrations for B10 of 2
2 2
0.023 g/cm in the Boraflex for Region 1 and of 0.015 g/cm in the Boraflex for Region 2. The thickness of Boraflex for Region 1 is 0.085 inches and the thickness i
for Region 2 is 0.058 inches. The Boraflex density 22 is taken as 1.70 g/cc.with a BIO
~
atom fraction in natural boron of 0.198.
.4 lJ l-Table 3.
Basis Fuel' Assembly Specifications Parameter Description Assembly ID MARK B9 15x15 Assembly type.
208 Fuel Rods per Assembly Guide Tubes per Assembly 16 Instnament Tubes per Assembly 1
Fuel Rod Pitch, cm.
1.44272 Pellet Radius, cm.
0.46990 Cladding OR, cm.
0.54610 Cladding IR, cm.
0.47879 Fuel Stack length, cm.
357.111 Guide Tube OR, cm.
0.67310 Guide Tube IR, cm.
0.63246 Instrument Tube OR, cm.
0.690965 o
Instrument Tube IR, cm.
0.560070 Cladding Material Zircaloy-4 GT Material Zircaloy-4 l
IT Material Zircaloy-4 Fuel Assembly Loading, KgU 463.664 i
UO2 Density g/cc 10.2083*
- Based upon fuel loading, KgU and pellet stack volume, i.e.
KgU x (r,,,,e) 2 (hu,3) (pins /assy) (
)
p ;
O t-].
JL&W Fuel Comgany BAW-2209. Rev 1 I
Table 4.
Fresh Fuel Concentrations Vs U235 Enrichment I
Enrichment Pellet Concentrations (atoms /b-cm) l wt% U235 TJ23,5 U238 016 5.05 0.00116438 0.0216162 0.0455362 2.10 0.000484198 0.0222878 2.00 0.000461141 0.0223106 1.80 0.000415027 0.0223561 1.64 0.000378135 0.0223925 1
1.62 0.000373524 0.0223971-l.60 0.000368913 0.0224016 I
I Table 5.
Region 1 Average Burnup Number Densites Versus Enrichment (atoms /b-cm) 3.0 wt%
3.0 wt %
4.0 wt%
5.0 wt%
5.0 wt%
hogg 10 GWD 12.5 GWD_
20 GWD 30 GWD -
35 GWD U235 4.71556E-04 4.28391E-04 5.02721E-04 5.33577E-04 4.60647E-04 l
U238 2.19091E-02 2.18649E-02 2.15406E-02 2.11867E-02 2.11069E-02 0
4.55362E-02 4.55362E-02 4.55362E-02 4.55362E-02 4.55362E-02 Sml49 8.88612E-08 9.19174E-08 1.22684E-07 1.50847E-07 1.46848E-07 U236 4.05835E-05 4.81524E-05 7.78790E-05 1.15297E-04 1.26726E-04 Pu239 8.98955E-05 1.00962E-04 1.25304E-04 1.47831E-04 1.52582E-04 Pu240 1.46768E-05 1.96493E-05 2.86346E-05 3.92015E-05 4.61314E-05 Pu241 6.15532E-06 9.28532E-06 1.62267E-05 2.55891E-05 3.07286E-05
- B10' 6.42800E-06 7.83010E-06 1.28787E-05 1.97519E-05 2.25610E-05 B10 number density providing reactivity equivalent to burnt fuel isotopes not listed.
I E.
F b
B&W Fuel Company BAW-2209. Rev 1
- Table 6.'
Region 2 Axial Number Densities For 5.05 Wt % Initial Enrichment 45 GWD/MTU Average Burnup (atoms /b-cm) 4 Burnup, GWD/MTU Isotope 29.88 42.53 46.66 48.33 0
4.55362E-02 4.55362E-02 4.55362E-02 4.55362E-02 U235 5.35275E-04 3.63566E-04 3.16626E-04 2.98898E-04 U236 1.15024E-04 1.40611E-04 1.46619E-04 1.48731E-04 U238 2.ll888E-02 2.09821E-02 2.09111E-02 2.08817E-02 Pu239 1.47518E-04 1.55633E-04 1.55834E-04 1.55784E-04 y
Pu240 3.93807E-05 5.5855 "E-05 6.06465E-05 6.23594E-05 Pu241 2.51184E-05 3.70827E-05 3.98743E-05 4.09775E-05 g'
Sm149 1.49196E-07 1.38534E-07 1.32596E-07 1.31115E-07 B10' 1.96660E-05 2.65746E-05 2.86512E-05 2.94701E-05 Burnup, GWDiMTU Lwtopg 45.31 39.06 26.51 0
4.55362E-02 4.55362E-02 4.55362E-02 c'
U235 3.31462E-04 4.06424E-04 5.88544E-04 U236 1.44786E-04 1.34696E-04 1.06233E-04 U238 2.09346E-02 2.10404E-02 2.12414E-02 i
Pu239 1.55785E-04 1.54693E-04 1.42621E-04 LI Pu240 5.92191E-05 5.15479E-05 3.45439E-05 Pu241 3.89193E-05 3.43408E-05 2.12647E-05 I
Sm149 1.33591E-07 1.42700E-07 1.49890E-07 B10' 2.79751E-05 2.47626E-05 1.77177E-05 B10 number density providing reactivity equivalent to burnt fuel isotopes not listed. t
(
L
- CO B&W Fuel Company BAW-2209. Rev I g
Table 7.
Non-Fuel Material Densities Material Densities For Zircaloy-4 l
13919 3
. Weight %
Concentration (atoms /b-cm)
-l Zr 1C0.00 4.35745E-02 Mateiial Densities For Pool Water Isotope Weicht %
Concentration (atoms /b-cm)
HI i1.19000 6.68571E-02 016 88.81000 3.34308E-02 I
Material Densities For IIomogenized Instrument Tube Isotope Weicht %
Concentration (atoms /b-cm)
H1 3.53350 5.03327E-02 016 28.04400 2.51680E-02 Zr4 68.4225 1.07699E-02 Material Densities For Stainless Steel Element Weight %
Concentratiori(aloms/b-cm)
Cr 19.00 1.77597E-02 Mn 2.00 1 769333-03 Fe 69.00 6.00483E-92 Ni 10.00 8.27827E-03 Material Densities For EPRI Boraflex Composition Region 1 Region 2 l
Element Weight %
Concentration Weight %
Concentration H
3.0000 3.04711E-02 3.0000 3.04711E-02 l
B 34.1738 3.23611E-02 32.6625 3.09300E-02 C
19.0000 1.61958E-02 19.0000 1.61958E-02 016 22.0000 1.40785E-02 22.0000 1.40785E-02 Si 21.8262 7.95638E-03 23.3375 8.50730E-03 II
I I
B&W Fuel Company BAW-2209. Rev 1 l
3.0 Region 1 Rack Analysis This section describes the Region I rack analysis including the Region 1 KENOIV geometry model, cell uncenainty evaluation, axial burnup shape effects, axial Eoraflex shrinkage effects, misplaced fuel assembly, and checkerboard fuel loading analysis.
3.1 Region 1 KENOlV Geometry Model Storage Pool B is divided into two regions. Region 1 (174 locations) consists of high density fuel assembly spacing obtained by utilizing a neutrun absorting material. It is reserved for I
core off-loading (177 fuel assemblies). Region 2 (641 locations) also consists of high density fuel assembly spacing and provides normal storage for spent fuel assemblies.
I The Region I storage rack modules are composed of individual storage cells made of stainless steel. These racks utilize a neutron absorbing material, Boraflex, which is attached to the walls of each cell. The cells within a module are interconnected by grid assemblies to I
fonn an integral structure. The major components of the cell assembly are the fuel assembly cell, the Boraflex material, and the wrapper. The wrapper covers the Boraflex material with provision for venting of the Boranex region to the pool environment. A schematic for the Region 1 rack cells is provided in Figure 4.
The KENOIV model has been optimized relative to tolerances to provide the highest kar, as l
discussed in Section 3.2. A comparison of the model dimensions versus the nominal rack dimensions is provided in Table 8. A 4 x 1/4 assembly rack xy-model is used to obtain the effect of the checkerboard rack array and to model axial uncenainty effects. Figure 5 provides a schematic of the model. Note that two minor approximations have been made in the model. The first is the addition of the wrapper thickness with the stainless steel wall thickness interior to the poison plate. The second is neglecting the indentations at the I
interior corner of the rack cells. It is assumed the stainless steel wall forms a square box on which the Boraflex material is attached. Neither of these changes is expected to significantly affect the rack results.
3.2 Cell Uncertainty Evaluation The reactivity of a fuel storage rack cell can be affected by material size and composition tolerances, fabrication tolerances (cell pitch and width), asymmetric (off-center) loading of the fuel assembly within the cell, and pool temperature. A deterministic code, such as I
CASMO3, is generally more accurate in detennining the reactivity effect of small penurbations (such as those tolerances stated above) than is a Monte Carlo code; even though I
the Monte Carlo code may provide a more accurate geometric representation and theoretical model. In most cases, this is because the statistical uncenainty in the Monte Carlo I
Oo B&W Fuel Company BAW-2209. Rev 1 Figure 4.
Region 1 Rack Cell Schematic l
I I
=
- 10.60 CENTER-TO-CENTER SPAC]NG
-l I
W/////////////W///////////
W M V W f////// W M
i 9
7.50 BORAF LEX 7
3 l
j 3
/,
S S
I;I
- p
?
5 S
S, l
t
. 4-.-f
/
s
?
l
?
3
/
9.00 J
/
f
- f f
CELL
].D.
s
+
G
?
l I,
e en
__W___
_W_
l l
1.20 s
s CELL-TO-CELL GAP
\\
.060 1NNER 120 CELL WALL GAP
.095 BORAFLEX
- 020 V/ RAPPER I
I
l l
B&W Fuel Company BAW-2209. Rev 1 l
Table 8.
Region I Rack Cell Dimensions lI
- Descri cion Model Basis l
Dimension, in Cell l
Pitch 10.512 Minimum pitch for the nominal 10.60 inch pitch.
Inner Width 9.088 Maximum of nominal 9.00 inch cell inner l
dimension.
SS Wall 0.086 Sum of nominal 0.060 inch wall and 0.020 l
Thickness inch wrapper plus tolerance of 0.006 inch t
Borauex:
Thickness 0.085 Minimum Boraflex thickness.
l Width 7.384 Minimum for a nominal of 7.60 inches.
Length 140.6 Extends only over active fuel length, rather than nominal length of 144.00 0.25 inches.
I l
Figure 5.
Region 1 KENOIV Model Schematic l
Water Cell, SS, Boroflex, flux Trap I\\
s5
/ \\
lI Fuel fuel Assembly 1 Assembly 2 I
II l
Fuel fuel Assembly 2 Assembly 1 0
0 I1 B&W Fugl Company BAW-2209. Rev 1 calculation is a significant fraction (or even greater than) the fractional change in reactivity 3
caused by the perturbation. Consequently, the CASMO3 code is used to compute many of E
these effects.
To obtain the reactivity sensitivity due to material and constmetion tolerances, a nominal (base) case is compared to the perturbed case. The difference in reactivity between the two cases gives a quite accurate estimate of the sensitivity. This is so because, in most cases, the perturbation can be mocked up exactly, even though the overall geometry is approximated and the overall reactivity is less accurate. An example is the SS thickness sensitivity.
t Because of the curvatures in the SS can and wrapper, the SS can and wrapper geometry is approximated with square corners. However, the change in SS thickness can be obtained exactly even with the approximate model.
I Using a single assembly storage rack cell, sensitivity calculations wem completed varying SS wall thickness, SS box width, rack cell pitch, off-center fuel assembly position, pool water temperature, and misted or " optimum moderation" conditions. It was determined that the misted condition for higher mactivity could not occur in Region I racks because of the presence of poison plates and relatively close cell spacing. Based on the above ',ndividual a
sensitivity studies, the " worst" case conditions for the CR3 pool B Region I rack cell are the g
following:
2
- 1. Minimum B10 concentration in Boraflex (0.023 g/cm )
- 2. Maximum SS thickness (3.086 inches)
- 3. Maximum SS box width (9.088 inches)
Ei
- 4. Minimum cell pitch (10.512 inches) 3l
- 5. Minimum pool water temperature (50"F)
- 6. Fuel assembly centered within the cell.
j These " worst" case conditions were used to set up the KENOIV geometry and input so that all cases are conservatively bounded with respect to these variations. The CASMO3 g
calculated total penalty for using the " worst" case conditions rather than the nominal 5'
conditions is 0.02143 Aka. This does not include the B10 concentration in Boraflex since the minimum value was used in the analysis.
3.3 Axial Burnup Shape Effects I'4 To determine if a non-uniform axial fuel burnup distribution has an adverse effect on rack criticality when burned fuel is checkerboarded with fresh fuel, a burned fuel distribution from the Region 2 rack analys's is used. For this study the fuel stack height is increased to 360.18 cm to correspond to tho axial pmfile data which is more conservative than the 357.11 cm height. For the fresh fuel on the checkerboard pattern, the enrichment actually used in l!
]
the calculations was 5.05 wt% to allow for an enrichment uncertainty of I % and for B=,
1 l
l t
B&W Fuel Company BAW-2209. Rev 1 conservatism. From section 4.6, the point which had the largest non-uniform axial burnup penalty was that at 15 GWD/MTU. This case also had the " worst case" axial burnup profile as shown in Figure 9. For this axial burnup distribution case, the axial concentrations are j
used for the burned fuel checkerboarded with the 5.05 wt% fresh fuel, and the KENOIV 1
calculated k.n is 0.89855 0.00137. For the corresponding uniform axial burnup case l
based upon the average burnup, the KENOIV calculated k,n is 0.90023 0.00134. The i
difference is a positive bias of 0.00168 0.00338 (Ak i 1.763o). This shows the uniform l
burnup calculation is statistically equal to that for an explicit axial burnup profile. Thus it is I
not required to determine the axial bumup effects for spent fuel in Region 1 of the CR3 pool B racks.
3.4 Axial Boraflex Shrinkage Effects l
As stated in section 2.3, the design will allow for the occurrence, at the same vertical position, of two 4-inch gaps in adjacent Bomflex panels. Because of the 4 x 1/4 KENOIV geometry, this is two adjacent 4-inch gaps in every row position and in every other column l
position of the X-Y rack checkerboard array, and hence is a very conservative condition.
This condition is represented in KENOIV by defining a model with the 4-inch gaps in the 4 x 1/4 geometry array. Since the purpose is to determine a ok due to the gaps, the enrichment l
of the fuel checkerboarded with the 5.05 wt% fresh fuel is not crucial, thus a 1.80 wt%
U235 fresh fuel enrichment was chosen to give a k,n between 0.90 and 0.95. For the 4-inch gap case the KENOIV calculated k,n is 0.91336 0.00132. The corresponding base case (no gaps) KENOIV calculated k,n is 0.90894 0.00138. The difference is -0.00442 i j
0.00337 Ak, This negative bias due to Boraflex shrinkage will be accounted for in the l
subsequent criticality calculations. The KENOIV input files for these two cases are shown in l
Appendix B.I.
3.5 Misplaced Fuel Assembly l
As stated in section 2.1, the worst credible accident is to misload a fresh 5.0 wt% U235 fuel assembly into a burned fuel position. However, in this case 2000 ppm soluble boron is allowed in the pool water based upon the double contingency principle. A 5.05 wt% U235 fuel assembly was placed in every burned fuel position in the rack with 2000 ppm borated water. The KENOIV calculated k.n = 0.80153 i 0.00118 for this case. Thus, even if all burned fuel positions contain 5.05 wt% U235 fresh fuel, the rack configuration still remains well subcritical with 2000 ppm boron in the pool water.
3.6 Checkerboard Fuel Rack Analysis Table 9 summarizes the penalties and uncertainties discussed in section 2.3 for Regio. I of the pool racks. ______
fl O
B&W Fuel Company BAW-2209. Rev 1 I'
Table 9.
Summary of Bias and Tolerance Penalties and Uncertainties Applied To Region 1 l
Rem Bias Uncenaintv' Comments
- 1. KENOIV Bias 0.01000 0.00363 Figure 3, Spacing < l.932
- 2. Tolerances 0.0 Used worst case geometry B
- 3. Temperature 0.0 Used worst case temperature 3
- 4. Boraflex Gaps 0.00442 0.00337 Two adjacent 4-inch gaps
- 5. LBP history 0.0 Used worst case history B
- 6. Non-uniform burn 0.0 Calc. positive bias
.5,
- 7. B-part. Self-Sh.
0.00120 From previous analysis Total 0.01562 0.00495 Total bias - Region 1 The uncertainties include the 1.763 tolerance factor.
I:
Using the defm' itions of section 2.3, sufficient neutron histories (300500) were used in the subsequent KENOIV criticality runs such that a, < 0.00150. With o, = 0.00495, Aks, =
0.01562, and Kmx = 0.9500, the maximum allowed k,n is detennined from:
km 0.95 - 0.0156 - /(0.00495)2 + (1.7630 ) 2 0.9288
=
c When generating the fuel burnup versus initial U235 enrichment curw for the spent fuel, a k,y value of 0.9200 was used which provides an additional 0.0088 Ak for contingency. For the fresh fuel on the checkerboard pattern, the enrichment actually used in the calculations was 5.05 wt % to allow for an enrichment uncenainty of I %. This will allow storage of nominal 5.0 wt%
l, fuel.
First the reactivity of the array with 5.05 wt% fuel checkerboarded with empty cells (water) was computed. The calculated KENOIV multiplication was k,n = 0.82854 0.00148. Thus, this case is well suberitical.
To determine the minimum burnup for burned fuel, the burned fuel isotopes as computed by CASMO3 must be represented in KENOIV. First, the major fuel isotopes and fission pioducts g
which contribute to fuel reactivity and whose neutron cross sections are available on the 3 I!
=,
I
e L
IL&W Fuel Company BAW-2209. Rev 1 KENOIV library are identified. These include 016, SM149, U235, U236, U238, PU239, p
PU240, and PU241. Concentrations for these isotopes at a given burnup are transferred directly L
to KENOIV from CASMO3. All remaining fission products and higherisotopes from CASMO3 are represented by an equivalent B10 concentration in KENOIV. To obtain an accurate value p
for this equivalent B10 concentration at a given burnup, the following procedure is performed.
The CASMO3 code is used to deplete the fuel to the specified burnup, and a CASMO3 recovery L
is made at the specified burnup and at the pool rack conditions (pool temperatum and pressure, F
soluble bomn = 0.0, XE135 = 0.0, LBP rods out, etc). Then the major isotopes listed above L
are input to a new CASMO3 run with the same geometry and at the pool rack conditions; and the B10 concentration in the fuel pellet is adjusted to give the same CASMO3 reactivity as for I
the previous CASMO3 recovery mn. This procedure provides an accurate value of equivalent B10 for KENOIV which reproduces the fuel assembly reactivity at pool conditions.
I Using the above procedures, CASMO3 depletion calculations were completed for 3.0,4.0, and 5.0 wt% U235 enriched fuel at several burnups. The burned fuel concentrations were input to KENOIV and 3-D criticality calculations were completed for selected burnups at each enrichment. The KENOIV calculated values are listed below.
g Enrichment Burnup (wt% U235)
(GWD/MTU)
_Ag a
2.0 0.0 0.91538 0.00136 2.1 0.0 0.92195 0.00134
[
3.0 10.0 0.92364 0.00134 3.0 12.5 0.91609 0.00131 4.0 20.0 0.92022 0.00135 p
L 5.0 30.0 0.92040 0.00137 5.0 35.0 0.91443 0.00135 At each enrichment, interpolation on bumup corresponding to a constant Iqu of 0.9200 yielded the values in Table 10.
{
[
[
[
23 -
-.--4
=
f-0:
RLikW Fuel Company BAW-2209. Rev 1 I,
Table 10. Region 2 Burnup Versus Enrichment Results Fuel Enrichment Fuel Burnup (wt% U235)
(GWD/MTtn 2.08 0.0 3.00 11.2 4.00 20.2 l.
5.00' 30.3 It is pointed out that these points have an additional contingency safety margin of 0.0088 Ak as described above. A curve which falls on the " safe" side of all the points is given by:
Minimum bumup =
0.0 0.00s E s2.08 Minimum burnup = 13.00(E-2.08)4).90(E-2.08)2 2.08s E s5.00 The points and the curve are shown on Figum 1. A sample KENOIV input file for the above calculations is shown in Appendix B.I.
I I
I Ii i
g a
'1 l
1
?
i.
B&W Fuel Company BAW-2209. Rev 1 4.0 Region 2 Rack Analysis This section describes the Region 2 rack analysis including the Region 2 KENOIV geometry model, cell uncertainty evaluation, axial Boraflex shrinkage effects, misplaced fuel assembly, axial burnup shape effects, and burned fuel loading analysis.
4.1 Region 2 KENOIV Geometry Model The Region 2 storage rack modules consist of stainless steel cells (641 locations) assembled in a checkerboard pattern, producing a honeycomb type stmeture. Each cell is similar to those of Region I for the major components of the cell, the Boraflex material, and the wrapper. However, the cell pitch,9.17 inches, is smaller than that of Region I with only one borauex plate between each assembly cell. A schematic for the Region 2 rack cells is provided in Figure 6.
The KENOIV model has been optimized for tolerances to provide the highest km as discussed
-in Section 4.2. A comparison of the model dimensions versus the nominal rack dimensions
{
is provided in Table 11. The effect of the checkerboard rack array and the model axial uncertainty effects are obtained from a 4 x 1/4 assembly rack xy-model. Figure 7 provides a schematic of the model. Note that the same two minor approximations are made relative to the combination of the stainless steel layers and squaring the corners as were made in the Region 1 model.
4.2 Cell Uncertainty Evaluation As for Region 1, CASMO3 is used to determine the tolerance uncertainties and the most
(
reactive combination of tolerances. The dimensions for the base case are given in Table 11.
The results of this case will be compared to the perturbed cases to determine the reactivity sensitivities. At 50"F and 1.60 wt% U235, the neutron multiplication for the base case is
(
0.91546.
Using this single assembly storage rack cell, sensitivity calculations were completed varying
(
SS thickness, rack cell pitch, off-center fuel assembly position, pool water temperature, and misted or " optimum moderation" conditions. It was determined that the misted condition for higher reactivity could not occur in Region 2 racks because of the presence of poison plates and relatively close cell spacing. Based on the above individual sensitivity studies, the i _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _
Oi O4 B&W Fuel Company BAW-2209. Rev 1 i
Figure 6.
Region 2 Rack Cell Schematic g
I 9.17 CENTER-TO-CENTER SPACING i
l'
,I I
'd l
j
/
B.994 NON-CELL 1.D.
)
i I
.c.
9.81
/ t, / // w//, /A :
~ //r H/H/ //Hf N////H/'s L l:/// // / p t/.1
.032 l
fi 7.60 DORarLEx
'j 1
l
/
i u
i p
l' l
'd
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e
- 4. _
0.00
/
CELL
).D.
9
)
6
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2 l
y/// /////_i pA :
- 3;,,4,,,j_,,
,/,,,,,,;/,,;,, y,,ig-
- T' /M /s 'i s/3 N.,
g s
B 3
\\
r,060 3 ME R
/
jCELLWALL
.0g3-DAP g
.050 DORArLEX
- 070 WRAPFER I aa
{
B&W Fuel Company BAW-2209. Rev 1 Table 11. Region 2 Rack Cell Dimensions
, Description -
.. Model :
Basis:
! Dimensioniin Cell Pitch 9.05 Minimum pitch for the nominal 9.17 inch pitch.
Inner Width 9.0 Nominal cell inner dimension.
{
SS Wall 0.086 Sum of nominal 0.060 inch wall and 0.020 Thickness inch wrapper plus tolerance of 0.006 inches.
Boraflex Plate Thickness 0.058 Minimum Boraflex thickness.
Width 7.6 Nominal value.
12ngth 141.8 Extends only over active fuel length used for axial effects cases, rather than nominal length of 144.00 0.25 inches.
(
Figure 7.
Region 2 KENOIV Model Schematic
{
Wotor Cell, SS, Boroflex
{
l
(
fuel fuel Assembly I Assembly 2 Fuel fuel Assembly 2 Assembly 1 _ _
Oo B&W Fuel Company BAW-2209. Rev 1
" worst" case conditions for the CR3 pool B Region 2 rack cell are the following:
2
- 1. Minimum B10 concentration in Boraflex (0.015 g/cm )
- 2. Maximum SS thickness (0.086 inches)
- 3. Minimum cell pitch (9.05 inches)
- 4. Minimum pool water temperatum (50"F)
- 5. Fuel assembly centered within the cell.
A CASMO3 case was set up which simulates all of the above conditions simultaneously.
The calculated neutron multiplication is 0.91973, and the change in multiplication is
+0.00427. These " worst" case conditions are used in the KENOIV calculations to directly include the bias and uncertainty for tolerances.
4.3 Axial Boraflex Shrinkage Effects Using the KENGIV geometry description as given in section 4.1, a base case KENOIV with 1.60 wt% U235 fresh fuel was set up. The base case (no gaps) KENOIV calculated k,y =
0.92980 i 0.00105.
As stated in section 2.3, the design will allow for the occurrence of two 4-inch gaps in adjacent Botaflex panels at the same vertical position. Because of the KENOIV geometry model, this mpresents 4 inch gaps in adjacent panels in every other row of cells in the rack.
This condition is represented in KENOIV by redefining some boxes in the 4 x 1/4 geometry army. This is similar to the method used in section 3.4. The calculated k,y = 0.93364 i 0.00107. Thus, the negative bias due to Boraflex shrinkage is 0.00384 i 0.00264 (1.763o)
Ak., and this will be accounted for in the subsequent criticality calculations.
I 4.4 Misplaced Fuel Assembly I-As stated in section 2.1, the worst credible accident is to misload a fresh 5.05 wt% U235 fuel assembly into a burned fuel position. However, in thi case 2000 ppm soluble boron is allowed in the pool water based upon the double contingency principle. We now place a 5.05 wt% U235 fuel assembly in every other checkerboard burned fuel position in the rack flooded with 2000 ppm borated water. The KENOIV calculated k,y = 0.85491 0.00102.
Thus, even if all ckeckerboarded burned fuel positions contain 5.05 wt% U235 fresh fuel, l
the rack configuration is well suberitical with 2000 ppm of soluble boron.
4.5 Axial Burnup Shape Effects A unifonn, average bumup distribution over the entire length of the assembly is typically
. E m
f B&W Fuel Company BAW-2209. Rev 1 used for burnup credit rack analysis with KENOIV. Such a ciistribution underpredicts the bumup at the center of the assembly and overpredicts the burnup at the top and bottom of the assembly. To adequately utilize burnup credit, an estimate of the reactivity effects of the axial burnup distribution relative to a uniform burnup distribution must be determined and appropriately applied to the results. This section summarizes the method used to determine the axial effects of burnup. A more detailed description is provided in Appendix A.
There are two major sources of uncertainty associated with the use of burnup credit: the measured burnup and the axial shape. The administrative controls applied to the bumup credit will associate a measured burnup with an initial enrichment. Any uncertainty associated with the bumup measurement should be covered in the administrative controls and measurement specification and is not included here in the enrichment versus minimum burnup curve. The axial shapes used in the analysis are bounding shapes generated from burnup shapes obtained from NEMO analyses for the completed cycles I through 9 of CR3.
Use of bounding shapes explicitly includes the uncertainty in the axial shapes.
The total burnup range of the fuel assemblies is divided into 5 regions: 0 - 10, 10 - 20, 20 -
30, 30 - 40, and 40 - 50 in units of GWD/MTU. The calculations are done at 8, 15, 25, 35, and 45 GWD/MTU to determine the maximum safe fuel enrichments corresponding to these burnups. Within each burnup range, the bounding (or worst) axial profile was used for r
conservatism.
The minimum number of axial regions to be used in the KENOIV rack criticality calculations is limited by the requirement to perform an accurate 3D calculation. Examination of the axial bumup profiles indicates that essentially all of the bias due to non-uniform axial burnup is caused by the low-bumed fuel near the top and bottom of the core. Based on the above profiles, it seems prudent to keep at least 3 nodes at the top and 3 nodes at the bottom for the KENOIV calculations. Thus,7 axial regions were used in the KENOIV axial burnup calculations. When performing the axial burnup calculations, for conservatism, the base fuel assembly length is increased to 360.18 cm, using the axial spacings specified for the axial burnup profiles from NEMO. Except for the first range which is calculated at 8 GWD/MTU, the burnups are calculated at the midpoint of each range. For each bumup range, the KENOIV axial region burnups are tabulated in Table A-1. The values from that table are used to obtain the axial fuel concentrations for the KENOIV 3-D analysis of minimum burnup versus enrichment for the CR3 Pool B Region 2 fuel storage racks.
The burned fuel isotopics for these various burnups were obtained with the CASMO3 computer pmgram, using the same procedures as described in section 3.6. The calculation of the axial concentrations is simplified by using fixed values for fuel temperature, moderator tempemture, and soluble boron concentration. This should be adequate since isotopics depend primarily on fuel burnup and a bounding (worst case) axial bumup profile which includes the effects of the axial variation of fuel and moderator temperatures was used. As - -
ou O
B&W Fuel Company BAW-2209. Rev 1 an additional conservatism, all fuel is completely burned with LBP rods inserted. For a 3
given average fuel burnup point, the average bumup is multiplied by the bounding pmfile E i values to give the burnups for the 7 axial regions, Table A-2. The fuel is then burned using CASMO3 with burnup steps which include those for the 7 axial regions and the average burnup. At each of these burnup points, a recovery is made at pool rack conditions and a mactivity value obtained. For each burnup point, the major isotopes plus an equivalent B10 concentration are then re-input to CASMO3 and the B10 concentration adjusted until the above pool rack reactivity value is reproduced, i.e.the BIO equivalent to the remaining isotopes is obtained.
I 4.6 Burned Fuel Analysis Table 12 summarizes the negative bias and uncertainty items as discussed in section 2.3 and l
computed above for Region 2 of the Pool B racks. Since the analysis for the Region 2 racks utilizes explicit 3-D KENOIV geometry, no bias is required for the non-uniform axial burnup effects. However, the uncertainties associated with the 3-D KENOIV calculations are included in the results.
I Table 12. Summary of Bias and Tolerance Penalties and Uncertainties Applied To Region 2 Item Bias Uncenaintv' Comments
- 1. KENOIV Bias 0.0 0.0 Figure 3, Spacing <0.644 Used worst case tolerances
- 2. Tolerances 0.00427
- 3. Temperature 0.0 Used worst case temp.
- 4. Boraflex Gaps 0.00384 0.00264 Two adjacent 4-inch gaps
- 5. LBP history 0.0 Used worst case history l,
- 6. Non-uniform burn 0.0 Explicit 3-D KENOIV Calc.
ll
- 7. B-part. Self-Sh.
0.00190 Used orig. value (ref 5)
Total 0.01001 0.00264 Total bias - Region 2 The uncertainties include the 1.763 tolerance factor.
Using the definitions of section 2.3, sufficient neutron histories (300500) were used in the subsequent 3-D KENOIV criticality analysis such that a,< 0.00150. With a, = 0.00264 and j B-
W
,s t
B&W Fuel Company BAW-2209. Rev_1 i
'the total bias = 0.0100, a target k rr is chosen such that o
k6. = k n + 0. 010 0 + g (0. 0 026 4 ) 3. + (1.7630,)3 0.9499 < 0.95
=
e CASMO3 depletion ca'lculations were completed for average fuel burnups of 8.0,15.0,25.0, 35.0,'and 45.0 GWD/MTU at selected initial fuel enrichments. For each axial region, the j
burned fuel concentrations were used for 3-D KENOIV criticality calculations for selected
~
enrichments at each average burnup, For each average burnup, the KENOIV calculated multiplication at the selected initial fuel enrichments are tabulated below.
Average Burnup Enrichment GWD/MTU wt% U235 k tr_
a.
0.0 1.62 0.93351 0.00110 0.0 1.64 0.93857 0.00114 8.0 2.00 0.93071 0.00103 15.0 2.40 0.94714 0.00122 l
25.0 3.20 0.93700 0.00115 35.0 4.10 0.93898 0.00119 45.0 5.00 0.92400 0.00122 A typical KENOIV input file for these cases is listed in Appendix B.2.
Based upon the interpolation methodology described in Appendix A.2, the required burnups to give a Kmx of 0.9499 are determined. This data allows generation of the curve defining the minimum burnup versus initial fuel enrichment for spent fuel in Region 2, pool B of the CR3 storage racks. The calculated points are listed in Table 13.
h Table 13. Burnup Versus Enrichment Values for Region 2 E
O I!
B&W Fuel Company BAW-2209. Rev 1 Fuel Enrichment Fuel Burnup
)
(wt% U235)
(GWD/MTin 1.63 0.0 2.04 8.0 2.31 15.0 3.20 25.0 l
4.07 35.0 5.20 45.0 j
A smooth curve is drawn which encompasses the " safe" side of all the computed points and this is the recommended curve which gives the minimum burnup versus initial fuel enrichment for spent fuel storage in Region 2 of the CR3 Pool B racks. The curve is shown in Figure 2.
1 I:
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B&W Fuel Company BAW-2209. Rev 1
['
5.0 Conclusions ~.
[
. A criticality analysis for the Crystal River Unit 3 Spent Fuel Pool B storage racks was completed and shows that a nominal fuel enrichment increase up to 5.0 wt% U235 is allowed
[.:
provided specified minimum spent fuel burnup limits are met. The msults show that Region I will allow a checkerboard pattern of up to a maximum 5.05 wt% fresh fuel and burned fuel. For the Region 1 burned fuel, the mquired minimum burnup versus initial fuel enrichment is shown in Figure 1, and the calculated values are tabulated in Table 1. For Region 2, the results show that burned fuel with initial enrichments up to 5.00 wt% U235
[-
can be safely stored. The Region 2 burned fuel requires the minimum burnup versus initial i
t fuel enrichment curve as shown in Figure 2. The calculated values are tabulated in Table 1.
At lower enrichments, it should be noted that this curve is more conservative than the curve
{- ~
obtained in the previous analysis because of the penalties for potential Boraflex gap formation and non-uniform axial fuel burnup.
i r
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B&W Fuel Company BAW-2209. Rev 1 l
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B&W Fuel Company BAW-2209. Rev 1 1
6.0 References 1.
ANSI /ANS-57.2-1983, " Design Requirements for Light Water Reactor Spent Fuel j
Storage Facilities at Nuclear Power Plants", ANS, October 7,1983.
2.
ANSI /ANS-57.3-1983, " Design Requirements for New Fuel Storage Facilities at
-l Light Water Reactor Plants", ANS, January 13, 1983.
3.
ANSI /N16.9-1975/ANS-8-11, " Validation of Calculational Methods for Nuclear Criticality Safety", ANS,1975.
4.
Request for Proposal from B. L. Hernandez (FPC) to T. N. Wampler (BWFC), FPC File No. N573, February 22,1993, BWFC Doc. 38-1210386.
5.
NRC Regulatory Guide 1.13, Revision 2, USNRC,1982.
6.
L. A. Hassler & N. M. Hassan, " KENO 4 - B&W Version", NPGD-TM-503,Rev G, September 1987.
l 7.
W. A. Wittkopf & N. M. Hassan, "NITAWL - B&W Version", NPGD-TM-505,Rev 8, December 1988.
l 8.
W. R. Cable, "123 Group Neutron Cross Section Data Generated from ENDF/BII Data for Use in the XSDRN Discrete Ordinates Spectral Arraying Code", RSIC-DLC-16, ORNL 1971.
9.
W. A. Wittkopf & K. J. Firth, "CASMO3 User's Manual - B&W Version", BWNT-TM-58, January 1991.
10.
G. H. Hobson, et al, "NEMO - Nodal Expansion Method Optimized", BAW-10180A,
[
Rev.1, March 1993.
11.
BAW-1484-7, " Critical Experiments Supporting Close Proximity Water Storage of Power Reactor Fuel", N. M. Baldwin, et al, Babcock & Wilcox Co., July,1979.
12.
EPRI NP-6159, "An Assessment of Boraflex Performance in Spent-Nuclear-Fuel Storage Racks", EPRI, December,1988.
i 13.
EPRI TR-101986, "Boraflex Test Results and Evaluation", EPRI, February,1993.
14.
Ibid, page 6-9.
t 15.
Ibid, page 4-15.
I I
0 0'
- Ii B&W Fuel Company BAW-2209. Rev 1 16.
Ibid, Figure 3-5.
17.
Ibid, Figure 4-5.
i 18.
Request for Proposal from B. L. Hernandez (FPC) to T. N. Wampler (BWFC), FPC File No. N573, Febniary 22,1993.
19.
Annual Book of ASTM Standards, vol 01.03,1990, Designation A240-89b.
20.
Annual Book of ASTM Standards, vol 01.03,1990, Designation A480/A480M-89a, Table A.
21.
Op Cit, EPRI NP-6159, Appendix A, page A-6.
22.
Ibid.
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1 1
B&W Fuel Company BAW-2209. Rev 1 l
Appendix A. Region 2 Axial Burnup Profile Discussion i
A.1 Axial Profile Generation A unifonn, average burnup distribution over the entire length of the assembly is typically l
used for burnup credit rack analysis with KENOIV. Such a distribution under predicts the burnup at the center of the assembly and over predicts the burnup at the top and bottom of the assembly. To adequately utilize burnup credit, an estimate of the reactivity effects of the k
axial bumup distribution relative to a unifonn burnup distribution must be detennined and appropriately applied to the results. This section provides an assessment of a method to detennine the axial effects of burnup.
There are two major sources of uncenainty associated with the use of bumup credit: the p
measured burnup and the axial shape. The administrative controls applied to the burnup L
credit will associate a measured bumup with an initial enrichment. Any uncertainty associated with the burnup measurement should be covered in the administrative. controls and measurement specification. It is not included in the enrichment versus minimum burnup curve developed in this analysis. The axial shapes used in the analysis are bounding shapes generated from burnup shapes obtained from NEh10 analyses for the completed cycles I thmugh 9 of CR3. Use of bounding shapes explicitly includes the uncertainty in the axial shapes.
{
The relative axial bumup distributions for each assembly (1/8 core model) for cycles 1 through 9 were obtained from NEhiO calculations. A database file was created from the EOC axial burnups from all assemblies (not just discharged fuel) in 1/8 core. Examination of this data shows that the axial burnup profiles flatten considerably as burnup increases above about 15 GWD/hiTU.
Initial calculations using pmfiles from low (0 - 20 GWD/hiTU), medium (20 - 40 j
GWD/hiTU), and high (40 -60 GWD/hfTU) burnup ranges showed that the NUAB penalty was very much dependent on the axial profiles. Since the pmfiles change with increasing burnup, a sufficient number of profiles are required over the total burnup range to detennine bounding values for the NUAB without being overly conservative. As a practical solution, it was decided to divide the total range into 5 sub-ranges: 0 - 10,10 - 20, 20 - 30, 30 - 40, and l
40 - 50 GWD/hiTU. The calculations are done at 8,15,25,35, and 45 GWD/hiTU to detennine the maximum safe fuel enrichments corresponding to these burnups. Within each bumup range, the bounding (or worst) axial profile was used for conservatism. The minimum to average axial burnup ratios in the top and bottom core nodes for each of the above bumup ranges are tabulated below: l B
l 1
5m B&W Fuel Company BAW-2209mRey__1 Burnup Relative Average Initial Range Axial Axial Burnup U235 Core (MWD /MTm Node Bunns (MWD /MTLD wt%
Cycle 0 - 10 bot 0.4916 3.41 2.64 2
l 0 - 10 top 0.3832 3.92 2.64 2
10 - 20 bot 0.5651 13.16 2.62 4
10 - 20 top 0.2721 14.21 2.00 1
20 - 30 bot 0.6001 22.09 2.54 2
20- 30 top 0.4289 22.15 2.54 2
30 - 40 bot 0.6178 31.90 2.62 6
l 30 - 40 top 0.4671 30.24
-2.83 3
40 - 50 bot 0.6640 41.45 3.84 9
40 - 50 top 0.5889 40.25 3.29 7
The bounding axial bumup profile is obtained by taking several minimum top and bottom E
node values and adjusting the central values such that the integrated relative axial profile is g
unity. As an example, for a 7 axial region KENOIV model, the top 3 minimum node values and the bottom 3 minimum node values am selected. Then the central values (all identical) g am determined by the volume-integrated relative axial distribution being set to unity. Table E
14 lists the minimum top and bottom axial bumup pmfiles along with a bounding profile for each burnup range for the 18 nodes used in the NEMO calculations. In this table, the axial g
spacing for nodes 2 through 17 is 20.003 cm while for nodes 1 and 18 the node spacing is 5
22.352 cm and 17.780 cm, respectively. Plots of the axial profiles and bounding values are shown in Figures 8, 9,10,11, and 12.
p I
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B&W Fuel Comaam BAW-2209. Rev 1 L
Table 14. Minimum Top and Bottom and Bounding Axial Burnup Profiles Node 0 - 10 GWD/MTU 10 - 20 GWD/MTU 20 - 30 GWD/MTU No.
Bot Too Bnd Bot Too Bnd Bot Too Bnd
=
1 0.4916-0.4979 0.491 0.5651 0.6740 0.565 0.6001 0.6032 0.600 2
0.8458 0.8543 0.845 0.9125 1.0772 0.912 0.9079 0.9144 0.908 3
1.0147 1.0237 1.014 1.0560 1.2129 1.056 1.0341 1.0412 1.034 4
1.0859 1.0955 1.137 1.1104 1.2142 1.175 1.0767 1.0848 1.114 g
5 1.1106 1.1210 1.137 1.1253 1.2140 1.175 1.0846 1.0939 1.114 g
6 1.1184 1.1292 1.137 1.1238 1.2067 1.175 1.0842 1.0948 1.114 7
1.1242 1.1348 1.137 1.1172 1.1959 1.175 1.0872 1.0997 1.114 8
1.1335 1.1435 1.137 1.1115 1.1888 1.175 1.0964 1.1114 1.114 9
1.1459 1.1550 1.137 1.1095 1.1881 1.175 1.~1092 1.1260 1.114 10 1.1578 1.1657 1.137 1.1111 1.1922 1.175 1.1208 1.1385 1.114 11 1.1650 1.1717 1.137 1.1141 1.1954 1.175 1.1278 1.1458 1.114 I
12 1.1651 1.1701 1.137 1.1158 1.1882 1.175 1.1393 1.1470 1.114 13 1.1547 1.1571 1.137 1.1122 1.1473 1.175 1.1236 1.1397 1.114 14 1.1270 1.1242 1.137 1.0964 0.9958 1.175 1.1049 1.1159 1.114 15 1.0667 1.0542 1.137 1.0530 0.7308 1.175 1.0505 1.0593 1.114 5
16 0.9468 0.9191 0.919 0.9537 0.6026 0.602 0.96C5 0.9342 0.934 17 0.7290 0.6904 0.690 0.7561 0.4615 0.461 0.7831 0.7046 0.704 18 0.4115 0.3832 0.383 0.4457 0.2721 0.272 0.4938 0.4289 0.429 I
Node 30 - 40 GWD/MTU 40 - 50 GWD/MTU No.
Bot Too Bnd Bot Too Bnd 1
0.6178 0.6653 0.617 0.6640 0.6652 0.664 I
2 0.9282 0.9971 0.928 0.9453 0.9462 0.945 3
1.0386 1.1003 1.038 1.0369 1.0452 1.037 4
1.0778 1.1112 1.104 1.0657 1.0805 1.074 I
5 1.0900 1.1073 1.104 1.0736 1.0887 1.074 6
1.0921 1.1012 1.104 1.0751 1.0820 1.074 7
1.0909 1.0942 1.104 1.0751 1.0705 1.074 8
1.0893 1.0892 1.104 1.0750 1.0628 1.074 I
9 1.0886 1.0873 1.104 1.0750 1.0599 1.074 10 1.0886 1.0889 1.104 1.0752 1.0623 1.074 11 1.0890 1.0924 1.104 1.0754 1.0702 1.074 12 1.0888 1.0943 1.104 1.0754 1.0775 1.074 13 1.0864 1.0904 1.104 1.0745 1.0802 1.074 14 1.0784 1.0729 1.104 1.0702 1.0768 1.074 I
15 1.0558 1.0320 1.104 1.0550 1.0602 1.074 16 0.9962 0.9387 0.938 1.0085 1.0078 1.007 17 0.8474 0.7503 0.750 0.8781 0.8685 0.868 18 0.5511 0.4671 0.467 0.5965 0.5889 0.589 -
q O
Ili B&W Fuel Company BAW-2209. Rev 1 The minimum number of axial regions to be used in the KENOIV rack criticality calculations is limited by the requirement to perform an accurate 3D calculation. Examination of the axial burnup profiles indicates that essentially all of the bias due to non-uniform axial burnup is caused by the low-burned fuel near the top and bottom of the core. Based on the above profiles, it seems prudent to keep at least 3 nodes at the top and 3 nodes at the bottom for the KENOIV calculations. This suggests that a minimum of 7 axial regions may be adequate for the KENOIV calculations. A study varying the number of axial mgions verified this thesis and confirmed that within the KENOIV statistical uncertainty there was no difference between using 7,9, or 11 axial nodes pmvided that the top 3 nodes and the bottom 3 nodes were included.
Based on the above study, the KENOIV axial bumup calculations used 7 axial regions. With 7 axial nodes, the bounding profiles of Figures 8,9,10,11, and 12 are defined by the top 3 and bottom 3 node values and the requirement that the volume integrated relative axial node values be unity. When performing the axial burnup calculations, for conservatism, the base g
fuel assembly length is increased to 360.18 cm, using the axial spacings specified from the g
NEMO axial burnup pmfiles. Except for the first range which is calculated at 8 GWD/MTU, the burnups are calculated at the midpoint of each range. Table 15 provides E
the KENOIV axial region burnups for each burnup range.
3 Table 15. Axial Burnups and Profiles Used For Axial Burnup Effects 3-D g
Calculations u,
0 - 10 10 - 20 20 - 30 30 - 40 40 50 Axial Bnd Ax Bnd Ax Bnd Ax Bnd Ax Bnd Ax Node Prof
- Bu*
Prof Bu Prof Bu Prof Bu Prof Bu 1
0.491 3.93 0.565 8.48 0.600 15.00 0.617 21.60 0.664 29.88 2
0.845 6.76 0.912 13.68 0.908 22.70 0.928 32.48 0.945 42.53 3
1.014 8.11 1.056 15.84 1.034 25.85 1.038 36.33 1.037 46.66 4
1.137 9.10 1.175 17.62 1.114 27.85 1.104 38.64 1.074 48.33 5
0.919 7.35 0.602 9.03 0.934 23.35 0.938 32.83 1.007 45.31 i
6 0.690 5.52 0.461 6.92 0.704 17.60 0.750 26.25 0.868 39.06 7
0.383 3.06 0.272 4.08 0.429 10.73 0.467 16.35 0.589 26.51
- "Bnd Prof" is the bounding axial profile and "Ax Bu" is the axial burnup in GWD/MTU.
I, The KENOIV axial spacing for nodes 2,3,5, and 6 is 20.003 cm. For nodes I,4, and 7 the spacing is 22.352 cm, 240.036 cm, and 17.780 cm, mspectively. CASMO3 uses these nodal axial burnup values to obtain the axial fuel concentrations for the KENOIV 3-D analysis to determine the minimum burnup versus enrichment for the CR3 Pool B Region 2 fuel storage racks. Tables 16,17,18,19, and 20 provide the isotopic concentrations obtained fmm CASMO3 for the above burnup ranges at selected enrichments. u m
I
- B&W Fuel Company BAW-2209. Rev 1 l
Figure 8.
0 - 10 GWD/MTU Axial Profiles
~
t
-l l
l CR3 Axial Burnup Profiles 0-10 GWD/MTU j
l
'j ua+****
+ 1, 1 e
s
/
\\
!'8
/
\\\\
)
/
)
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0.5 O.4 a
0.3 0
50 100 150 200 250-300 350 400 Axial Height.- cm I
l l
+ bottom -*- top
-*- bounding l
7,
=f I
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O E-T B&W Fuel Company BAW-2209. Rev 1 E
Figure 9. '10 - 20 GWD/MTU Axial Profiles l
I; CR3 Axial Burnup Profiles 10-20 GWD/MTU g
1.3 E,
?)] $kn~t i _.is"
\\
f f TM l
[8
//
7
\\X ha
//
\\ \\\\
m.
ff g
4 g
37 9
8 0
8 i
\\ \\
m a: 0.5 4 g g
0.4 O.3 a
0.2 0
50 100 150 200 250 300 350 400 Axict Height - cm I>
-*- bottom
-A-top
-*- bounding I
I E
~
i I.
I 1 a
I B&W Fuel Comnany BAW-2209. Rev 1 I
g Figure 10. 20 - 30 GWD/MTU Axial Profiles i
I CR3 Axial Burnu Profiles 20-30 GWD TU 1.2 w
w=
_"VM=k~
l 1.1 1.--
-=~
l.9
/
1 0
g 8
m 0.8 I
15 0.7 0.6
\\\\
0.5 f
0.4 0
50 100 150 200 250 300 350 400 l
Axiol Height - cm lI
-*- bottom -*- top
-*- bounding 8
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=
B&W Fuel ComDany BAW-2209. Rev 1 E
Figure 11. 30 - 40 GWD/MTU Axial Profiles l,l lIl CR3 Axial Burnup Profiles.
l 30-40 GWD/MTU 1.2 l
1.1 A AL4-4 fi 1 -L
=
0.9
//
\\%
8
//
w ll' j
J h
7 O.6 -
0.5 g
0.4 0
50 100 150 200 250 300 350 400 Axial Hei t.t - cm l
L 1-
-*- bottom -*- lop
-*- bounding I'
i I
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E.,
.i l
B&W Fuel Comnany BAW-2209. Rev 1 -
Figure 12. 40 - 50 GWD/MTU Axial Profiles CR3 Axial 'Burnup Profiles 40-50 : GWD/MTU 1*1 N
-m -
- = -
-3 1
c k0.9 C-l R
08 3
0.7 0.6
~
\\
j m
0.5 0
50 100 150 200 250 300 350 400 Axiol Height '- cm
-*- bottom -*- top
-*- bounding p
[-
45 -
B B
B&W Fuel Company BAW-2209. Rev 1 Table 16. Axial Number Densities,2.0 Wi%,8 GWD/MTU Bumun. GWD/MTU Isotope 3.93 6.76 8.I1 9.10 t
ll O
4.55362E-02 4.55362E-02 4.55362E-02 4.55362E-02 U235 3.71008E-04 3.19829E-04 2.98181E-04 2.83278E-04 U236 1.62168E-05 2.52158E-05 2.89425E-05 3.14722E-05 g
U238 2.22293E-02 2.21712E-02 2.21436E-02 2.21234E-02 g
Pu239 5.20413E-05 7.47605E-05 8.26979E-05 8.75374E-05 Pu240 5.37097E-06 1.19074E-05 1.52043E-05 1.75837E-05 g
Pu241 1.30394E-06 4.25179E-06 5.98733E-06 7.39283E-06 g
Sml49 5.29596E-08 6.02999E-08 6.27764E-08 6.43095E-08 B10' 2.58633E-06 4.14724E-06 4.87732E-06 5.40340E-06 Bumup, GWD/MTU holong 7.35 5.52 3.06 f
O 4.55362E-02 4.55362E-02 4.55362E-02 U235 3.10173E-04 3.41190E-04 3.88663E-04 5
U236 2.68849E-05 2.14897E-05 1.30629E-05 g
U238 2.21591E-02 2.21966E-02 2.22473E-02 Pu239 7.84260E-05 6.59992E-05 4.28189E-05 Pu240 1.33419E-05 8.96118E-06 3.58907E-06 Pu241 4.99367E-06 2.79603E-06 7.06522E-07 Sml49 6.14854E-08 5.75475E-08 4.98962E-08 B10' 4.46511E-06 3.47371E-06 2.08758E-06 BIO number density pmviding reactivity equivalent to bumt fuel isotopes not listed.
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B&W Fuel Company BAW-2209. Rev 1 l
Table 17. Axial Number Densities,2.4 Wt%,15 GWD/MTU L
Bumup. GWD/MTU 119199g 8.48 13.65 15.84 17.62 0
4.55362E-02 4.55362E-02 4.55362E-02 4.55362E-02 U235 3.73f02E-04 2.94559E-04 2.66316E-04 2.44813E-04 U236 3.24078E-05 4.53844E-05 5.04674E-05 5.38573E-05 U238 2.20'i78E-02 2.19580E-02 2.19162E-02 2.18815E-02 Pu239 8.34415E-05 1.04091E-04 1.09210E-04 1.12404E-04 Pu240 1.40284E-05 2.54874E-05 3.01238E-05 3.36834E-05 Pu241 5.52790E-06 1.25897E-05 1.54617E-05 1.78612E-05 Sml49 7.22516E-08 7.80898E-08 7.89819E-08 7.98629E-08 B10' 5.26370E-06 8.07519E-06 9.22556E-06 1.01629E-05 Bumup, GWD/MTU Isolegg 9.03 6.92 4.08 i
0 4.55362E-02 4.55362E-02 4.55362E-02 U235 3.64396E-04 4.00987E-04 4.56378E-04 U236 3.40673E-05 2.76602E-05 1.77444E-05 U238 2.20473E-02 2.20877E-02 2.21419E-02 Pu239 8.63464E-05 7.39528E-05 5.09976E-05 Pu240 1.52534E-05 1.05826E-05 4.76291E-06 Pu241 6.22394E-06 3.70199E-06 1.12208E-06 Sml49 7.31218E-08 6.93017E-08 6.18015E-08 B10" 5.56228E-06 4.39824E-06 2.78202E-06 B10 number density providing reactivity equivalent to bumt fuel isotopes not listed.
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O E
B&W Fuel CompaDI BAW-2209. Rev 1 Table 18. Axial Number Densities,3.2 Wt%,25 GWD/MTU I
Bumup, GWD/MTU g
Isotope 15.00 22.70 25.85 27.85 g
O 4.55362E-02 4.55362E-02 4.55362E-02 4.55362E-02 g
U235 4.27476E-04 3.17794E-04 2.79647E-04 2.57339E-04 3
U236 5.67503E-05 7.47172E-05 8.05188E-05 8.37566E-05 U238 2.17815E-02 2.16447E-02 2.15871E-02 2.15499E-02 g
Pu239 1.09735E-04 1.25415E-04 1.28532E-04 1.29956E-04 5
Pu240 2.34695E-05 3.76037E-05 4.30683E-05 4.61222E-05 Pu241 1.21053E-05 2.17379E-05 2.50395E-05 2.71812E-05 g
Sml49 9.93384E-08 1.00594E-07 9.90413E-08 9.89942E-08 m
B10' 9.36713E-06 1.35767E-05 1.52411E-05 1.62880E-05 Bumup, GWD/MTU Isotope 23.35 17.60 10.73 0
4.55362E-02 4.55362E-02 4.55362E-02 U235 3.09569E-04 3.87616E-04 5.00091E-04 U236 7.59983E-05 6.34698E-05 4.40769E-05 U238 2.16330E-02 2.37358E-02 2.18556E-02 Pu239 1.26140E-04 1.It688E-04 9.31401E-05 l
Pu240 3.89136E-05 2.83903E-05 1.53490E-05 Pu241 2.22942E-05 1.54794E-05 6.60765E-06 Sml49 9.94867E-08 1.00473E-07 9.47908E-08 l
B10' l.39183E-05 1.08094E-05 6.96091E-06 BIO number density pmviding reactivity equivalent to bumt fuel isotopes not listed.
I I
I I !
t.
B&W Fuel Company BAW.2209. Rev 1 Table 19. Axial Number Densities,4.1 Wi%,35 GWD/MTU Burnup, GWD/MTU Isotope 21.60 32.48 36.33 38.64 O
4.55362E-02 4.55362E-02 4.55362E-02 4.55362E-02 U235 4.96339E-04 3.44411E-04 2.99452E-04 2.74621E-04 U236 8.32182E-05 1.07184E-04 1.13496E-04 1.16756E-04 I
U238 2.14950E-02 2.13117E-02 '2.12438E-02 2.12021E-02 Pu239 1.29159E-04 1.42050E-04 1.43566E-04 1.44124E-04 Pu240 3.08566E-05 4.75786E-05 5.29559E-05 5.57396E-05 Pu241 1.78999E-05 2.98914E-05 3.31398E-05 3.50862E-05 Sml49 1.25499E-07 1.21330E-07 1.17462E-07 1.16348E-07 B10" 1.38887E-05 1.98750E-05 2.18724E-05 2.30512E-05 I
Bumup, GWD/MTU Isotope 32.83 26.25 16.35 I
O 4.55362E-02 4.55362E-02 4.55362E-02 U235 3.40057E-04 4.26613E-04 5.84440E-04 I
U236 1.07825E-04 9.46453E-05 6.79970E-05 U238 2.13057E-02 2.14182E-02 2.15797E-02 Pu239 1.42134E-04 1.36578E-04 1.15368E-04 I
Pu240 4.83226E-05 3.84677E-05 2.20385E-05 Pu241 2.99772E-05 2.32468E-05 1.14371E-05 Sml49 1.19416E-07 1.23814E-07 1.24012E-07 I
B10' 2.00485E-05 1.64934E-05 1.08584E-05 B10 number density providing reactivity equivalent to burnt fuel isotopes not listed.
I I
I 49 g
I i
O<
m.
I B&W Fuel Company BAW-2209. Rev 1 Ii Table 20. Axial Number Densities,5.0 Wi%,45 GWD/MTU Bumup, GWD/MTU Isotone 29.88 42.53 46.66 48.33 0
4.55362E-02 4.55362E-02 4.55362E-02 4.55362E-02 U235 5.35275E-04 3.63566E-04 3.16626E-04 2.98898E-04 U236 1.15024E-04 1.40611E-04 1.46619E-04 1.48731E-04 U238 2.I1888E-02 2.09821E-02 2.09111E-02 2.08817E-02 g!
Pu239 1.47518E-04 1.55633E-04 1.55834E-04 1.55784E-04 3
Pu240 3.93807E-05 5.58554E-05 6.06465E-05 6.23594E-05 Pu241 2.51184E-05 3.70827E-05 3.98743E-05 4.0075E-05 Sml49 1.49196E-07 1.38534E-07 1.32596E-07 1.31115E-07 B10' 1.96660E-05 2.65746E-05 2.86512E-05 2.94701E-05 Burnup, GWD/MTU Isotope 45.31 39.06 26.51 0
4.55362E-02 4.55362E-02 4.55362E-02 U235 3.31462E-04 4.06424E-04 5.88544E-04 U236 1.44786E-04 1.34696E-04 1.06233E-04 g
U238 2.09346E-02 2.10404E-02 2.12414E-02 4
Pu239 1.55785E-04 1.54693E-04 1.42621E-04 Pu240 5.92191E-05 5.15479E-05 3.45439E-05 Pu241 3.89193E-05 3.43408E-05 2.12647E-05 Sm149 1.33591E-07 1.42700E-07 1.49890E-07 B10' 2.79751E-05 2.47626E-05 1.77177E-05 B10 number density providing reactivity equivalent to burnt fuel isotopes not listed.
I' I:
i
- a:
L r'
L B&W Fuel Company BAW-2209. Rev 1 A.2 Minimum Burnup Versus Enrichment Interpolation Method
[
When calculating the allowed enrichment at a selected average bumup, the calculated 3-D multiplication (Kmx) may be slightly above or below the allowed value of 0.9499. Rather than repeating the 3-D calculations for small reactivity diffemnces, the difference dK =
~
l-0.9499 - Kmx is divided by S (where S= dK/dE) to give the dE cormction to the enrichment, so that the burnup versus enrichment curve is based on a constant Kmx =
0.9499. Hem S is the slope of the K versus E curve at the specified burnup. This method is L
used only for enrichment adjustments less than 0.1 % for the enrichment range from 0 to 5.0 wt% U235. The curve'of S versus burnup (B) is used to determine the enrichment change r
(for small changes, < 0.1 wt% U235) for a given change in multiplication. Since this method is used only for small changes in enrichment, the adjustment is not critical for reasonable accuracy. For example, an error in S of as much as 20% msults in only a 0.02 wt% error in enrichment. For a fixed rack geometry, the S is a function of E and B; L
however, B and E are related through the curve of minimum burnup versus enrichment, Figure 2. The points on the S versus B curve are generated fmm CASMO3 data recovery p
reactivity at Pool rack conditions. Tabulated below are dK/dE values calculated from L
CASMO3 depletion-mcovery runs.
F L
dK/dB Fuel Burnup
{
0.208 0
0.138 8
0.111 16 r
0.093 25 l
0.076 35 0.064 44 A - nooth curve drawn through the data is shown on Figure 13 which is used to determine hange in enrichment for small values of A Kmx.
r l
T KENOIV 3-D criticality calculations were made for each axial mgion using the CASMO3 burned fuel concentrations for selected enrichments at each average burnup. The KENOIV N
't calculated multiplication factors for each average burnup and initial fuel enrichments are tabulated below.,
O O
B&W Fuel Company BAW-2209. Rev 1 i
r Average Bumup Enrichment
. KENOIV Results GWD/MTU wt% U235 k_,r + 1.763cr l
0.0 1.62 0.93351 0.00194 0.0 1.64 0.93857 0.00201 8.0 2.00 0.93071 t 0.00182 l
15.0 2.40 0.94714 0.00215 25.0 3.20 0.93700 i 0.00203 l
35.0 4.10 0.93898 0.00210 g
45.0 5.00 0.92400 0.00215 5
I For the point at zero burnup Kmx = 0.9335 + 0.0100 + [(0.00194)2 + (0.00264)2)ii2 = 0.9468.
Kmx = 0.9386 + 0.0100 + [(0.00201)2 + (0.00264)2]ir2 = 0.9519.
This indicates that the maximum enrichment at zero burnup is -1.63 wt% U235 based on a maximum Kmx of 0.9499.
For the point at 8 GWD/MTU, I
Kmx = 0.9307 + 0.0100 + h0.00182)2 + (0.00264)2)ir2 = 0.9440.
From Figure 14, S = 0.14,
- thus, dB = (0.9499 - 0.9440)/0.14 = 0.04.
This indicates that the maximum enrichment at 8 GWD/MTU burnup is 2.04 wt% U235 ll l
based on a maximum Kmx of 0.9499.
Similar calculations are done for burnups from 15 to 45 GWD/MTU to generate the li enrichment values in Table 13.
1 ll I.t
I B&W Fuel Company EAW-2209. Rev 1 Figure 13. dk/dE Versus Burnup Interpolation Curve I-dK/dE versus Burnup
- l 0.22
. 1 0.2 0.18
\\
0.16
\\
y 0.14 5 \\
0.12 I
x 0.1 g
0.08 0.06
~
0.04 0
5 10 15 20 25 30 35 40 45 50 Fuel Burnup (GWD/MTU)
I I
I I
I I,I
Rl Ol IJ B&W Fuel Company BAW-2209. Rev 1 Appendix B. KENOIV Input File Listings l,
B.1 Region 1 Sample KENOIV Input Files A schematic of the KENOIV box geometry for Region 1 is shown in Figure 14. The
- r. umbers refer to each box description for the following mgions:
Box Region Described 1
Fuel pin cell, fuel region I g
3,4,5,6 1/2 fuel pin cell, fuel Region 1 3
2 Fuel pin cell, fuel region 2 7,8,9,10 1/2 fuel pin cell, fuel region I g
27 Guide tube cell 5
28 Instrument tube cell 13,14,18,20 Cell gap, steel, poison material regions g
11,12,17,18 1/2 Cell gap, steel, poison material regions W:
15,16,21,22 Cell gap, steel region 23,24,25,26 Intersection region, water & steel For the KENOIV cases the material numbers are specified as follows:
Material Number Material 1
Fresh fuel enrichment 1 2
Zircaloy-4 3
Water 4
Stainless steel 5
Boraflex 6
Homogenized instrument tube (Zr + water) 7 Fresh fuel enrichment 2 I
The above boxes and material specifications are used in the cases executed for this analysis for which sample input fi!es am listed below.
I E=
l I
k B&W Fuel Company BAW-2209. Rev 1 Figure 14. KENOIV Region 1 Box Geometry Model l
28 10 10 10 10 10 10 10 11 12 6
6 6
6 6
6 6 28 7
2 2
2 2
2 2
2 13 14 1
1 1
1 1
1 1
5 B.
7 2 27 2
2 27 2
2 13 14 1
1 27 1
1 27 1
5 i
7 2
2 2
2 2
2 2 13 14 1
1 1
1 1
1 1
5 7
2 2
2 27 2
2 2 13 14 1
1 1 27 1
1 1
5 7
2 27 2
2 2
2 2 13 14 1
1 1
1 1 27 1
5 7
2 2
2 2
2 2
2 13 14 1
1 1
1 1
1 1
5 I
7 2
2 2
2 2
2 2 15 16 1
1 1
1 1
1 1
5 I
18 20 20 20 20 20 20 22 24 26 22 20 20 20 20 20 20 18 j
17 19 19 19 19 19 19 21 23 25 21 19 19 19 19 19 19 17 i
j 3
1 1
1 1
1 1
1 15 16 2
2 2
2 2
2 2
9 3
1 1
1 1
1 1
1 13 14 2
2 2
2 2
2 2
9 3
1 27 1
1 1
1 1 13 14 2
2 2
2 2 27 2
9 I
3 1
1 1 27 1
1 1 13 14 2
2 2 27 2
2 2
9 1
3 1
1 1
1 1
1 1 13 14 2
2 2
2 2
2 2
9 I
3 1 27 1
1 27 1
1 13 14 2
2 27 2
2 27 2
9 3
1 1
1 1
1 1
1 13 14 2
2 2
2 2
2 2
9
(.
28 4
4 4
4 4
4 4 11 12 8
8 8
8 8
8 8 28 I
1 B.I.1. Base case for Boraflex gap evaluation (see section 3.4)
(
INF XY,checkbrd,4 qtr assy,50F,5.05E+1.8E 300 0503 0601 3 123 75 12 07 021 102 28 18 18 1 -12 102000001 11000 0000
-1.0-1.0-1.0-1.00.00.0 1 -922351 0.00116438 j
i 922381 0.0216162 1
80003 0.0455362 2 400000 0.0435745 3
10001 0.0668571 3 S0003 0.0334308 4 240003 0.0177597 4 250005 0.00176933 4 260001 0.0600483 4 280003 0.00827827 5 010001 0.0304711 5 050000 0.0323611 5 060002 0.0161958 5 080003 0.0140785 5 140005 0.00795638 6 010001 0.0503327 6 080003 0.0251680 6 400000 0.0107699 7 -922351 0.000415027 7 922381 0.0223561 E
C3 I
B&W Fuel Company BAW-2209. Rev 1 l
7 80003 0.0455362 BOX TYPE 1 W
CYLINDER 1 0.46990 357.110.0123Z CYLINDER 0 0.47879 357.I10.0123Z g
CYLINDER 2 0.54610 357.110.0123Z g
CUBOID 3 0.72136 -0.72136 0.72136 -0.72136 357.110.0123Z BOX TYPE 2 CYLINDER 7 0.46990 357.110.0123Z l
CYLINDER 0 0.47879 357.110.0123Z W
CYLINDER 2 0.54610 357.110.0123Z CUBOID 3 0.72136 -0.72136 0.72136 -0.72136 357.110.0123Z g
DOX TYPE 3 g
ZHEMICYL+X 1 0.46990 357.110.0123Z ZHEMICYL+X 0 0.47879 357.110.0123Z l
ZHEMICYL+X 2 0.54610 357.110.0123Z CUBOID 3 0.72136 0.0 0.72136 -0.72136 357.110.0123Z W
BOX TYPE 4 ZHEMICYL+Y I 0.46990 357.110.0123Z g
ZHEMICYL+ Y 0 0.47879 357.110.0123Z E
ZHEMICYL+Y 2 0.54610 357.110.0123Z CUBOID 3 0.72136 -0.72136 0.72136 0.0 357.110.0123Z l
BOX TYPE 5 ZHEMICYL-X 1 0.46990 357.110.0123Z um ZHEMICYL-X 0 0.47879 357.110.0123Z ZHEMICYL-X 2 0.54610 357.110.0123Z g
CUBOID 3 0.0 -0.72136 0.72136 0.72136 357.110.0123Z g
DOX TYPE 6 ZHEMICYL-Y I 0.46990 357.110.0123Z ZHEMICYL-Y 0 0.47879 357.110.0123Z l
ZHEMICYL-Y 2 0.54610 357.110.0123Z W
CUBOID 3 0.72136 -0.72136 0.0 -0.72136 357.110.0123Z DOX TYPE 7 g
ZHEMICYL+X 7 0.46990 357.110.0123Z g
ZHEMICYL+X 0 0.47879 357.110.0123Z ZHEMICYL+X 2 0.54610 357.110.0123Z CUBOID 3 0.72136 0.0 0.72136 -0.72136 357.110.0123Z l
BOX TYPE 8 5,
ZHEMICYL+ Y 7 0.46990 357.110.0123Z ZHEMICYL+Y 0 0.47879 357.110.0123Z g
ZHEMICYL+Y 2 0.54610 357.110.0123Z g
CUBOID 3 0.72136 -0.72136 0.72136 0.0 357.110.0123Z BOX TYPE 9 l"
ZHEMICYL.X 7 0.46990 357.110.0123Z ZHEMICYL-X 0 0.47879 357.110.0123Z W.
ZHEMICYL-X 2 0.54610 357.110.0123Z CUBOID 3 0.0 -0.72136 0.72136 -0.72136 357.110.0123Z BOX TYPE 10 ZHEMICYL-Y 7 0.46990 357.110.0123Z ZHEMICYL-Y 0 0.47879 357.110.0123Z ZHEMICYL-Y 2 0.54610 357.110.0123Z l'
CUBOID 3 0.72136 -0.72136 0.0 -0.72136 357.110.0123Z W,
s
=
C
^
u B&W Fuel Company BAW-2209. Rev 1 j.
BOX TYPE 11 CUBOID 3 0.72136 0.0 0.72136 0.0 357.110.0123Z F
CUBOID 4 0.93980 0.0 0.72136 0.0 357.110.0123Z L
CUBOID 51.15570 0.0 0.72136 0.0 357.110.0123Z CUBOID 3 2.52984 0.0 0.72136 0.0 357.110.0123Z BOX TYPE 12 b
CUBOID 3 0.0 -0.72136 0.72136 0.0 357.110.0123Z I
CUBOID 4 0.0 -0.93980 0.72136 0.0 357.110.0123Z CUBOID 5 0.0 -1.15570 0.72136 0.0 357.110.0123Z CUBOID 3 0.0 -2.52984 0.72136 0.0 357.110.0123Z L
BOX TYPE 13 CUBOID 3 0.72136 0.01.44272 0.0 357.110.0123Z CUBOID 4 0.93980 0.01.44272 0.0 357.110.0123Z yl' CUBOID 51.15570 0.01.44272 0.0 357.110.0123Z CUBOID 3 2.52984 0.01.44272 0.0 357.110.0123Z BOX TYPE 14 r
CUBOID 3 0.0 -0.721361.44272 0.0 357.110.0123Z CUBOID 4 0.0 -0.939801.44272 0.0 357.110.0123Z CUBOID 5 0.0 -1.155701.44272 0.0 357.110.0123Z CUBOID 3 0.0 -2.529841.44272 0.0 357.110.0123Z BOX TYPE 15 CUBOID 3 0.72136 0.01.44272 0.0 357.110.0123Z CUBOID 4 0.93980 0.01.44272 0.0 357.110.0123Z CUBOID 3 2.52984 0.01.44272 0.0 357.110.0123Z L
BOX TYPE 16 CUBOID 3 0.0 -0.721361.44272 0.0 357.110.0123Z g
CUBOID 4 0.0 -0.939801.44272 0.0 357.110.0123Z CUBOID 3 0.0 -2.529841.44272 0.0 357.110.0123Z BOX TYPE 17 CUBOID 3 0.72136 0.0 0.72136 0.0 357.110.0123Z r
CUBOID 4 0.72136 0.0 0.93890 0.0 357.110.0123Z
[
CUBOID 5 0.72136 0.01.15570 0.0 357.110.0123Z CUBOID 3 0.72136 0.0 2.52984 0.0 357.110.0123Z BOX TYPE 18 CUBOID 3 0.72136 0.0 0.0 -0.72136 357.110.0123Z CUBOID 4 0.72136 0.0 0.0 -0.93980 357.110.0123Z CUBOID 5 0.72136 0.0 0.0 -1.15570 357.110.0123Z CUBOID 3 0.72136 0.0 0.0 -2.52984 357.110.0123Z BOX TYPE 19 CUBOID 31.44272 0.0 0.72136 0.0 357.110.0123Z CUBOID 41.44272 0.0 0.93980 0.0 357.110.0123Z r
CUBOID 51.44272 0.01.15570 0.0 357.110.0123Z CUBOID 31.44272 0.0 2.52984 0.0 357.110.0123Z BOX TYPE 20 CUBOID 31.44272 0.0 0.0 -0.72136 357.110.0123Z L
CUBOID 41.44272 0.0 0.0 -0.93980 357.110.0123Z CUBOID 51.44272 0.0 0.0 -1.15570 357.110.0123Z CUBOID 31.44272 0.0 0.0 -2.52984 357.110.0123Z BOX TYPE 21 CUBOID 31.44272 0.0 0.72136 0.0 357.110.0123Z CUBOID 41.44272 0.0 0.93980 0.0 357.1I 0.0123Z _
E as B&W Fuel Company BAW-2209. Rev 1 CUBOID 31.44272 0.0 2.52984 0.0 357.110.0123Z g
BOX TYPE 22 3
CUBOID 31.44272 0.0 0.0 -0.72136 357.110.0123Z CUBOID 41.44272 0.0 0.0 -0.93980 357.110.0123Z g
CsoOID 31.44272 0.0 0.0 -2.52984 357.110.0123Z g
DOX TYPE 23 CUllOID 3 0.72136 0.0 0.72136 0.0 357.110.0123Z CUBOID 4 0.93980 0.0 0.93980 0.0 357.110.0123Z g
CUBOID 3 2.52984 0.0 2.52984 0.0 357.110.0123Z g
BOX TYPE 24 CUBOID 3 0.72136 0.0 0.0 -0.72136 357.110.0123Z g
CUBOID 4 0.93980 0.0 0.0 -0.93980 357.110.0123Z g
CUBOID 3 2.52984 0.0 0.0 -2.52984 357.110.0123Z BOX TYPE 25 CUBOID 3 0.0 -0.72136 0.0 -0.72136 357.110.0123Z g
CUBOID 4 0.0 -0.93980 0.0 -0.93980 357.110.0123Z 3
CUBOID 3 0.0 -2.52984 0.0 -2.52984 357.110.0123Z BOX TYPE 26 CUBOID 3 0.0 -0.72136 0.72136 0.0 357.110.0123Z CUBOID 4 0.0 -0.93980 0.93980 0.0 357.110.0123Z CUBOID 3 0.0 -2.52984 2.52984 0.0 357.110.0123Z BOX TYPE 27 g
CYLINDER 3 0.63246 357.110.0123Z g,
CYLINDER 2 0.67310 357.110.0123Z CUBOID 3 0.72136 -0.72136 0.72136 -0.72136 357.110.0123Z BOX TYPE 28 CUBOID 6 0.72136 0.0 0.72136 0.0 357.110.0123Z CORE BDY 3 26.70048 0.0 26.70048 0.0 357.I10.0123Z CUBOID 3 26.70048 0.0 26.70048 0.0 387.61 -30.5123Z g
01 021701 021701 111 0 3
02 02 08 01 111701 111 0 02 111701 020801 111 0 03 010101 020801 111 0 04 020801 010101 111 0 05 181801 111701 111 0 06 111701 181801 Ii1 0 E
07 010101 111701 111 0 3
08 111701 010101 111 0 09 181801 020801 111 0 10 020801 181801 111 0 11 090901 011817 111 0 12 101001 011817 111 0 13 090901 021701 111 0 g
14 101001 021701 1Ii 0 3
15 090901 081103 111 0 16 101001 081103 111 0 l
17 01 18 17 09 09 01 111 0 18 011817 101001 111 0 19 021701 090901 111 0 20 021701 101001 111 0 21 081103 090901 111 0 "
E 4
R&W Fuel Companv' BAW-2209. Rev 1
.E-22 c81103 1010 01 1 11 0 g
23 090901 090901 111 0 24 090901 101001 111 0
.25 101001 090901 111 0 l-l 26 101001 101001.I11 0 yW 27 031613 031613 111 0 l
27 051409 051409 111 0 g
27 061307 031613 111 0 l g 27 031613 061307 111 0
)
l.
28 011817 011817 111 1 END CASE l
END KENO B.I.2. Boraflex gap case -2 panels (see section 3.4)
,I INF XY,checkbrd,4 qtr assy,50F,5.05E+1.8E,2 panels-4 inch gap j
300 0503 0601 3 123 75 12 07 021 118 32 18 18 1 -12 j
.I 102000001 11000 0000 1
-1.0-1.0-1.0 1.00.00.0 1 -922351 0.00116438 I 922381 0.0216162 I
1 80003 0.0455362 2 400000 0.0435745 3 10001 0.0668571 I
3 80003 0.0334308 4 240003 0.0177597 4 250005 0.00176933 4 260001 0.0600483 I
4 280003 0.00827827 5 010001 0.0304711 5 050000 0.0323611 I
5 060002 0.0161958 5 080003 0.0140785 5 140005 0.00795638 6 010001 0.0503327 I
6 080003 0.0251680 6 400000 0.0107699 7 -922351 0.000415027 I
7 922381 0.0223561 7 80003 0.0455362 BOX TYPE 1 CYLINDER 1 0.46990 357.110.0123Z I
CYLINDER 0 0.47879 357.110.0123Z CYLINDER 2 0.54610 357.110.0123Z CUBOID 3 0.72136 -0.72136 0.72136 -0.72136 357.110.0123Z
. I BOX TYPE 2 CYLINDER 7 0.46990 357.110.0123Z CYLINDER 0 0.47879 357.110.0121Z CYLINDER 2 0.54610 357.110.0123Z I
CUBOID 3 0.72136 -0.72136 0.72136 -0.72136 357.110.0123Z I
o,_J O
- B&W Fuel Company BAW-2209. Rev 1 BOX TYPE 3 g
ZHEMICYL+X 1 0.46990 357.110.0123Z g
ZHEMICYL+X 0 0.47879 357.110.0123Z ZHEMICYL+X 2 0.54610 357.110.0123Z i '
CUBOID 3 0.72136 0.0 0.72136 -0.72136 357.110.0123Z f
DOX TYPE 4 t
ZHEMICYL+Y I 0.46990 357.110.0123Z f
ZHEMICYL + Y 0 0.47879 357.110.0123Z l
ZHEMICYL+Y 2 0.54610 357.110.0123Z CUBOID 3 0.72136 -0.72136 0.72136 0.0 357.110.0123Z BOX TYPE 5 ZHEMICYL-X 1 0.46990 357.110.0123Z
=)
ZHEMICYL-X 0 0.47879 357.110.0123Z ZHEMICYL-X 2 0.54610 357.110.0123Z i
CUBOID 3 0.0 0.72136 0.72136 -0.72136 357.110.0123Z g
BOX TYPE 6 g
ZHEMICYL-Y I 0.46990 357.110.0123Z l
l ZHEMICYL-Y 0 0.47879 357.110.0123Z ZHEMICYL-Y 2 0.54610 357.110.0123Z CUBOID 3 0.72136 -0.72136 0.0 -0.72136 357.110.0123Z I
BOX TYPE 7 gj ZHEMICYL+X 7 0.46993 357.110.0123Z ZHEMICYL+X 0 0.47879 357.110.0123Z gl ZHEMICYL+X 2 0.54610 357.110.0123Z CUBOID 3 0.72136 0.0 0.72136 -0.72136 357.110.0123Z DOX TYPE 8 ZHEMIC', L + Y 7 0.46990 357.110.0123Z "l
ZHEMICYL+Y 0 0.47879 357.110.0123Z ZHEMICYL+Y 2 0.54610 357.110.0123Z g
CUBOID 3 0.72136 -0.72136 0.72136 0.0 357.110.0123Z g
BOX TYPE 9 ZHEMICYL-X 7 0.46990 357.110.0123Z ZHEMICYL-X 0 0.47879 357.110.0123Z
=
ZHEMICYL-X 2 0.54610 357.110.0123Z CUBOID 3 0.0 -0.72136 0.72136 -0.72136 357.110.0123Z BOX TYPE 10 g
ZHEMICYL-Y 7 0.46990 357.110.0123Z g,
ZHEMICYL-Y 0 0.47879 357.110.0123Z ZHEMICYL-Y 2 0.54610 357.110.0123Z CUBOID 3 0.72136 -0.72136 0.0 -0.72136 357.110.0123Z 7
DOX TYPE II CUBOID 3 0.72136 0.0 0.72136 0.0 357.110.0123Z CUBOID 4 0.93980 0.0 0.72136 0.0 357.110.0123Z g
CUBOID 51.15570 0.0 0.72136 0.0 357.110.0123Z 3
CUBOID 3 2.52984 0.0 0.72136 0.0 357.!! 0.0123Z BOX TYPE 12 gg CUBOID 3 0.0 -0.72136 0.72136 0.0 357.110.0123Z CUBOID 4 0.0 -0.93980 0.72136 0.0 357.110.0123Z i
CUBOID 5 0.0 -1.15570 0.72136 0.0 357.110.0123Z CUBOID 3 0.0 -2.52984 0.72136 0.0 357.110.0123Z BOX TYPE 13 J.E
~-
g 1 B&W Fuel Company BAW-2209. Rev 1
.g CUBOID 3 0.72136 0.01.44272 0.0 357.110.0123Z
- g CUBOID 4 0.93980 0.01.44272 0.0 357.110.0123Z CUBOID 51.15570 0.01.44272 0.0 357.110.0123Z CUBOID 3 2.52984 0.01.44272 0.0 357.110.0123Z
.l BOX TYPE 14 3
. CUBOID 3 0.0 -0.721361.44272 0.0 357.110.0123Z CUBOID 4 0.0 -0.939801.44272 0.0 357.110.0123Z CUBOID 5 0.0 -1.155701.44272 0.0 357.110.0123Z I-CUBOID 3 0.0 -2.529841.44272 0.0 357.110.0123Z
. BOX TYPE IS l
CUBOID 3 0.72136 0.01.44272 0.0 357.110.0123Z
[g CUBOID 4 0.93980 0.01.44272 0.0 357.110.0123Z g
CUBOID 3 2.52984 0.01.44272 0.0 357.110.0123Z BOX TYPE 16 3
CUBOID 3 0.0 0.721361.44272 0.0 357.110.0123Z E
c"" '
4
8
'.44272 0.0 357.i> 0.0 >23z CUBOID 3 0.0 -2.529841.44272 0.0 357.110.0123Z BOX TYPE 17
.. I CUBOID 3 0.72136 0.0 0.72136 0.0 357.110.0123Z CUBOID 4 0.72136 0.0 0.93P,90 0.0 357.110.0123Z CUBOID 5 0.72136 0.01.15570 0.0 357.110.0123Z CUBOID 3 0.72136 0.0 2.52984 0.0 357.110.0123Z I
BOX TYPE 18 CUBOID 3 0.72136 0.0 0.0 -0.72136 357.110.0123Z CUBOID 4 0.72136 0.0 0.0 -0.93980 357.110.0123Z CUBOID 5 0.72136 0.0 0.0 -1.15570 357.110.0123Z CUBOID 3 0.72136 0.0 0.0 -2.52984 357.110.0123Z BOX TYPE 19 CUBOID 31.44272 0.0 0.72136 0.0 357.1I 0.0123Z I
CUBOID 41.44272 0.0 0.93980 0.0 357.110.0123Z CUBOID 51.44272 0.01.15570 0.0 357.110.0123Z CUBOID 31.44272 0.0 2.52984 0.0 357.110.0123Z j
'I BOX TYPE 20 J
CUBOID 31.44272 0.0 0.0 -0.72136 357.110.0123Z
]
CUBOID 41.44272 0.0 0.0 -0.93980 357.110.0123Z CUBOID 51.44272 0.0 0.0 -1.15570 357.110.0123Z I
CUBOID 31.44272 0.0 0.0 -2.52984 357.110.0123Z
{
BOX TYPE 21 l
CUBOID 31.44272 0.0 0.72136 0.0 357.110.0123Z I
CUBOID 41.44272 0.0 0.93980 0.0 357.110.0123Z CUBOID 31.44272 0.0 2.52984 0.0 357.110.0123Z BOX TYPE 22 CUBOID 31.44272 0.0 0.0 -0.72136 357.110.0123Z I
CUBOID 41.44272 0.0 0.0 -0.93980 357.110.0123Z CUEOID 31.44272 0.0 0.0 -2.52984 357.110.0123Z
. BOX TYPE 23 I
CUBOID 3 0.72136 0.0 0.72136 0.0 357.110.0123Z CUBOID 4 0.93980 0.0 0.93980 0.0 357.110.0123Z CUBOID 3 2.52984 0.0 2.52984 0.0 357.110.0123Z BOX TYPE 24 I
CUBOID 3 0.72136 0.0 0.0 -0.72136 357.110.0123Z.I l
g t.;
E B&W Fuel Company BAW-2209. Rev 1 CUBOID 4 0.93980 0.0 0.0 -0.93980 357.I10.0123Z g
CUBO!D 3 2.52984 0.0 0.0 -2.52984 357.110.0123Z g
BOX TYPE 25 CUBOID 3 0.0 -0.72136 0.0 -0.72136 357.110.0123Z Eg CUBOID 4 0.0 -0.93980 0.0 -0.93980 357.110.0123Z CUBOID 3 0.0 -2.52984 0.0 -2.52984 357.110.0123Z BOX TYPE 26 CUBOID 3 0.0 -0.72136 0.72136 0.0 357.110.0123Z g
CUBOID 4 0.0 -0.93980 0.93980 0.0 357.110.0123Z E
CUBOID 3 0.0 -2.52984 2.52984 0.0 357.110.0123Z BOX TYPE 27 CYLINDER 3 0.63246 357.110.0123Z CYLINDER 2 0.67310 357.110.0123Z CUBOID 3 0.72136 -0.72136 0.72136 -0.72136 357.110.0123Z BOX TYPE 28 g
CUBOID 6 0.72136 0.0 0.72136 0.0 357.110.0123Z B
BOX TYPE 29 CUBOID 3 0.72136 0.0 0.21590 0.0 5.08 -5.08123Z B
CUBOID 5 0.72136 0.0 0.21590 0.0182.I1 -175.00123Z E
CUBOID 4 0.72136 0.0 0.21590 -0.21844182.11 -175.00123Z CUBOID 3 0.72136 0.01.59004 -0.93980182.11 -175.00123Z BOX TYPE 30 CUBOlD 3 0.72136 0.0 0.0 -0.21590 5.08 -5.08 123Z 5
CUBOID 5 0.72136 0.0 0.0 -0.21590182.11 -175.00123Z CUBOID 4 0.72136 0.0 0.21844 -0.21590182.11 -175.00123Z CUBOID 3 0.72136 0.0 0.93980 -1.59004 I82.11 -175.00123Z BOX TYPE 31 CUBOID 3 1.44272 0.0 0.21590 0.0 5.08 -5.08 123Z CUBOID 5 1.44272 0.0 0.21590 0.0182.11 -175.00123Z g
CUBOID 41.44272 0.0 0.21590 -0.21844182.11 -175.00123Z g
CUBOID 31.44272 0.01.59004 -0.93980182.11 -175.00123Z BOX TYPE 32 CUBOID 3 1.44272 0.0 0.0 -0.21590 5.08 -5.08123Z CUBOID 5 1.44272 0.0 0.0 -0.21590182.11 -175.00123Z CUBOID 41.44272 0.0 0.21844 -0.21590182.11 -175.00123Z CUBOID 31.44272 0.0 0.93980 -1.590M 182.11 -175.00123Z g
CORE BDY 3 26.70048 0.0 26.70048 0.0 357.110.0123Z g
CUBOID 3 26.70048 0.0 26.70048 0.0 387.61 -30.5123Z 01 021701 021701 111 0 02 020801 111701 111 0 02 111701 020801 111 0 03 010101 020801 111 0
(
M 02 08 01 010101 111 0 g
05 18 18 01 111701 111 0 3
06 11 17 01 181801 1I1 0 07 010101 111701 111 0 g
(
08 111701 010101 111 0 g
l 09 18 18 01 02 08 01 t il 0 10 02 08 01 181801 111 0 11 090901 O!1817 111 0 12 101001 011817 111 0 E i
l e
I B&W Fuel Company BAW-2209. Rev 1 13 090901 021701 111 0 "E~
14 101001 021701 111 0 15 090901 081103 111 0 16 101001 081103 111 0 l
gl.
l 17 011817 090901 111 0 3
18 011817 101001 111 0 19 021701 090901 111 0 J
20 021701 101001 111 0
'21 081103 090901 111 0 22 081103 101001 111 0 23 090901 090901 111 0 g
24 090901 101001 111 0 g
25 101001 090901 111 0 26 101001 101001 111 0 l
27 031613 031613 Il1 0 27 051409 051409 111 0 27 061307 031613 111 0 27 031613 061307 111 0
~I 28 011817 011817 111 0 29 010101 090901 111 0 30 010101 101001 111 0 31 020701 090901 111 0 I
32 020701 101001 111 1 END CASE END KENO B.I.3. Typical Case with 2.0 wt% Enrichment, No Burnup I
INF.XY,checkbrd,4 qtr assy,50F,5.05E+2.0E 300 0503 0601 3 123 75 12 07 021 102 28 18 18 1 -12 102000001 11000 0000 I
-1.0-1.0-1.0-1.00.00.0 1 -922351 0.00116438 1 922381 0.0216162 1 _ 80003_0.0455362 I
2 400000 0.0435745 3 10001 0.0668571 3 80003 0.0334308 I
4 240003 0.0177597 4 250005 0.00176933 4 260001 0.0600483 4 280003 0.00827827 I
5 010001 0.0304711 5 050000 0.0323611 t
5 060002 0.0161958 I
5 080003 0.0140785 5 140005 0.00795638 6 010001 0.0503327 6 080003 0.0251680 6 400000 0.0107699 !
I I
CO B&W Fuel Comnany BAW-2209. Rev 1 l
7 -922351 0.00046114I 7 922381 0.0223106 W
7 80003 0.0455362 BOX TYPE 1 g
g!
CYLINDER 1 0.46990 357.110.0123Z CYLINDER 0 0.47879 357.110.0123Z CYLINDER 2 0.54610 357.110.0123Z CUBOID 3 0.72136 -0.72136 0.72136 -0.72136 357.110.0123Z l'
BOX TYPE 2 3
CYLINDER 7 0.46990 357.110.0123Z CYLINDER 0 0.47879 357.110.0123Z CYLINDER 2 0.54610 357.110.0123Z CUBOID 3 0.72136 -0.72136 0.72136 -0.72136 357.110.0123Z l
BOX TYPE 3 ZHEMICYL+X 1 0.46990 357.110.0123Z gl ZHEMICYL+X 0 0.47879 357.110.0123Z EI l
ZHEMICYL+X 2 0.54610 357.110.0123Z CUBOID 3 0.72136 0.0 0.72136 -0.72136 357.110.0123Z g,
El BOX TYPE 4 ZHEMICYL+Y 1 0.46990 357.110.0123Z ZHEMICYL+Y 0 0.47879 357.110.0123Z ZHEMICYL+Y 2 0.54610 357.110.0123Z g
CUBOID 3 0.72136 -0.72136 0.72136 0.0 357.110.0123Z g
BOX TYPE 5 ZHEMICYleX 1 0.46990 357.110.0123Z ZHEMICYL-X 0 0.47879 357.110.0123Z ZHEMICYI X 2 0.54610 357.110.0123Z CUBOID 3 0.0 -0.72136 0.72136 -0.72136 357.110.0123Z BOX TYPE 6 l
ZHEMICYL-Y I 0.46990 357.110.0123Z g
ZHEMICYL-Y 0 0.47879 357.110.0123Z ZHEMICYL-Y 2 0.54610 357.110.0123Z g
CUBOID 3 0.72136 -0.72136 0.0 -0.72136 357.110.0123Z g
BOX TYPE 7 ZHEMICYL+ X 7 0.46990 357.110.0123Z ZHEMICYL+ X 0 0.47879 357.110.0123Z l
ZHEMICYL+X 2 0.54610 357.110.0123Z g
l CUBOID 3 0.72136 0.0 0.72136 -0.72136 357.110.0123Z BOX TYPE 8 g
ZHEMICYL+Y 7 0.46990 357.110.0123Z g
ZHEMICYL+Y 0 0.47879 357.110.0123Z ZHEMICYL+Y 2 0.54610 357.110.0123Z CUBOID 3 0.72136 -0.72136 0.72136 0.0 357.110.0123Z BOX TYPE 9 i
ZHEMICYl X 7 0.46990 357.110.0123Z ZHEMICYL-X 0 0.47879 357.110.0123Z ZHEMICYL-X 2 0.54610 357.110.0123Z i
CUBOID 3 0.0 -0.72136 0.72136 -0.72136 357.110.0123Z DOX TYPE 10 ZHEMICYL-Y 7 0.46990 357.110.0123Z ZHEMICYl Y 0 0.47879 357.110.0123Z E
I
(
B&W Fuel Company BAW-2209. Rev 1
-E ZHEMICYl Y 2 0.54610 357.110.0123Z -
E CUBOID 3 0.72136 -0.72136 0.0 -0.72136 357.110.0123Z
.l BOX TYPE 11
,g CUBOID 3 0.72136 0.0 0.72136 0.0 357.110.0123Z
'g CUBOID 4 0.93980 0.0 0.72136 0.0 357.110.0123Z CUBOID 51.15570 0.0 0.72136 0.0 357.110.0123Z
' CUBOID 3 2.52984 0.0 0.72136 0.0 357.110.012.1Z l
I BOX TYPE 12 CUBOID 3 0.0 -0.72136 0.72136 0.0 357.110.0123Z CUBOID 4 0.0 -0.93980 0.72136 0.0 35*/.110.0123Z CUBOID 5 0.0 -1.15570 0.72136 0.0 357.110.0123Z
,I CUBOID 3 0.0 2.52984 0.72136 0.0 357.110.0123Z BOX TYPE 13 CUBOID 3 0.72136 0.01.44272 0.0 357.110.0123Z
!l CUBOID 4 0.93980 0.01.44272 0.0 357.110.0123Z
'! E CUBOID 51.15570 0.01.44272 0.0 357.110.0123Z CUBOID 3 2.52984 0.01.44272 0.0 357.110.0123Z BOX TYPE 14 I
CUBOID 3 0.0 0.721361.44272 0.0 357.110.0123Z CUBOID 4 0.0 4.939801.44272 0.0 357.110.0123Z CUBOID 5 0.0 -1.155701.44272 0.0 357.110.0123Z I
CUBOID 3 0.0 -2.529841.44272 0.0 357.110.0123Z BOX TYPE 15 CUBOID 3 0.72136 0.01.44272 0.0 357.110.0123Z CUBOID 4 0.93980 0.01.44272 0.0 357.110.0123Z CUBOID 3 2.52984 0.01.44272 0.0 357.110.0123Z BOX TYPE 16 CUBOID 3 0.0 -0.721361.44272 0.0 357.110.0123Z I
CUBOID 4 0.0 -0.939801.44272 0.0 357.110.0123Z l
CUBOID 3 0.0 -2.529841.44272 0.0 357.110.0123Z BOX TYPE 17 CUBOID 3 0.72136 0.0 0.72136 0.0 357.110.0123Z I
CUBOID 4 0.72136 0.0 0.93890 0.0 357.110.0123Z CUBOID 5 0.72136 0.01.15570 0.0 357.110.'O 123Z CUBOID 3 0.72136 0.0 2.52984 0.0 357.11020123Z I
BOX TYPE 18 CUBOID 3 0.72136 0.0 0.0 -0.72136 357.110.0123Z l
CUBOID 4 0.72136 0.0 0.0 -0.93980 357.110.0123Z
)
CUBOID 5 0.72136 0.0 0.0 -1.15570 357.110.0123Z i
I CUBOID 3 0.72136 0.0 0.0 -2.52984 357.110.0123Z BOX TYPE 19 CUBOID 31.44272 0.0 0.72136 0.0 357.110.0123Z I.
CUBOID 41.44272 0.0 0.93980 0.0 357.I10.0123Z CUBOID 51.44272 0.01.15570 0.0 357.110.0123Z CUBOID 31.44272 0.0 2.52984 0.0 357.110.0123Z BOX TYPE 20 I
CUBOID 31.44272 0.0 0.0 -0.72136 357.110.0123Z CUBOID 41.44272 0.0 0.0 -0.93980 357.110.0123Z i
CUBOID 51.44272 0.0 0.0 -1.15570 357.110.0123Z i
I CUBOID 31.44272 0.0 0.0 -2.52984 357.110.0123Z BOX TYPE 21 1
O
'O
-B&W Fuel Company BAW-2209. Rev 1 CUBOID 31.44272 0.0 0.72136 0.0 357.110.0123Z g
CUBOID 41.44272 0.0 0.93980 0.0 357.110.0123Z g
' CUBOID 31.44272 0.0 2.52984 0.0 357.110.0123Z BOX TYPE 22 CUBOID 31.44272 0.0 0.0 -0.72136 357.110.0123Z
. CUBOID 41.44272 0.0 0.0 -0.93980 357.110.0123Z CUBOID 31.44272 0.0 0.0 -2.52984 357.110.0123Z BOX TYPE 23 CUBOID - 3 0.72136 0.0 0.72136 0.0 357.110.0123Z CUBOID 4 0.93980 0.0 0.93980 0.0 357.110.0123Z CUBOID 3 2.52984 0.0 2.52984 0.0 357.110.0123Z BOX TYPE 24 CUBOlD 3 0.72136 0.0 0.0 -0.72136 357.110.0123Z CUBOID 4 0.93980 0.0 0.0 -0.93980 357.110.0123Z CUBOID 3 2.52984 0.0 0.0 -2.52984 357.110.0123Z g
BOX TYPE 25 g
CUBOID 3 0.0 -0.72136 0.0 0.72136 357.110.0123Z CUBOID 4 0.0 -0.93980 0.0 -0.93980 357.110.0123Z CUBOID 3 0.0 -2.52984 0.0 -2.52984 357.110.0123Z BOX TYPE 26 CUBOID 3 0.0 -0.72136 0.72136 0.0 357.110.0123Z CUBOID 4 0.0 -0.93980 0.93980 0.0 357.110.0123Z g
CUBOID 3 0.0 -2.52984 2.52984 0.0 357.110.0123Z g
BOX TYPE 27 CYLINDER 3 0.63246 357.110.0123Z CYLINDER 2 0.67310 357.110.0123Z CUBOID 3 0.72136 -0.72136 0.72136 -0.72136 357.110.0123Z BOX TYPE 28 CUBOID 6 0.72136 0.0 0.72136 0.0 357.110.0123Z g
CORE BDY 3 26.70N8 0.0 26.70048 0.0 357.110.0123Z g
CUBOID 3 26.70048 0.0 26.70048 0.0 387.61 -30.5123Z 01 021701 021701 111 0 gg 02 020801 111701 111 0 02 111701 020801 111 0 03 010101 020801 11I O M 02 08 01 010101 1 1 1 0 g
05 181801 111701 1I1 0 g
06 111701 181801 1II O 07 010101 111701 11I O g
08 111701 010101 111 0 g
09 181801 020801 111 0 10 020801 181801 111 0 11 090901 011817 111 0 g
12 101001 011817 111 0 g
13 090901 021701 111 0 14 101001 021701 111 0 15 090901 08!!03 111 0
=
16 101001 081103 111 0 17 011817 090901 111 0 18 011817 101001 111 0 19 021701 090901 111 0 E.
I B&W Fuel Company BAW-2209. Rev 1 20 021701 101001 111 0 21 081103 090901 111 0 22 081103 101001 111 0 23 090901 090901 111 0
/
24 090901 101001 111 0 25 101001 090901 111 0 2.6 101001 101001 111 0
- 27 031613 031613 111 0 27 051409 051409 111 0 27 061307 031613 111 0 27 031613 061307 111 0 l
28 011817 011817 111 1 l
END CASE END KENO 1
l i
i -
r,u
[3 B&W Fuel Company BAW-2209. Rev 1 B.2 Region 2 Sample KENOIV Input Files A schematic of the KENOIV box geometry for Region 1 is shown in Figure 15. The numbers refer to each box description for the following regions:
Bp2 Region Described 1
Fuel pin cell, fuel region 1 3,4,5,6 1/2 fuel pin cell, fuel region 1 l
2 Fuel pin cell, fuel region 2 7,8,9,10 1/2 fuel pin cell, fuel region 1 12 Guide tube cell 1I Instrument tube cell 14,17,20,23 Cell gap, steel, poison material regions g'
13,16,19,22 1/2 cell gap, steel, poison material regions 3
15,18,21,24 Cell gap, steel, partial boraflex regions 25 Intersection region, water & steel For the KENOIV cases the material numbers are specified as follows:
Material Number Material 1
Fresh fuel enrichment 1 2
Zircaloy-4 3
Water 4
Stainless stee1 5
Boraflex 6
Homogenized instmment tube (Zr + water) 7 Fresh fuel enrichment 2 or 7-13 Axial bumup profile isotopics for enrichment 2 The above boxes and material specifications are used in the cases executed for this analysis
.l
- and listed below.
I I '
.E
- r.....
B&W Fuel Company BAW-2209. Rev 1 Figure 15. KENOIV Region 2 Box Geometry Model 11 10 10 10 10 10 10 10 13 6
6 6
6 6
6 6 11 7
2 2
2 2
2 2
2 14 1
1 1
1 1
1 1
5 7
2 12 2
2 12 2
2 14 1
1 12 1
1 12 1
5 7
2 2
2 2
2 2
2 14 1
1 1
1 1
1 1
5 7
2 2
2 12 2
2 2 14 1
1 1 12 1
1 1
5 7
2 12 2
2 2
2 2 14 1
1 1
1 1 12 1
5 7
2 2
2 2
2 2
2 14 1
1 1
1 1
1 1
i 7
2 2
2 2
2 2
2 15 1
1 1
1 1
1 1
5 f
19 20 20 20 20 20 20 21 25 24 23 23 23 23 23 23 22 3
1 1
1 1
1 1
1 18 2
2 2
2 2
2 2
9 3
1 1
1 1
1 1
1 17 2
2 2
2 2
2 2
9 3
1 12 1
1 1
1 1 17 2
2 2
2 2 12 2
9 3
1 1
1 12 1
1 1 17 2
2 2 12 2
2 2
9 3
1 1
1 1
1 1
1 17 2
2 2
2 2
2 2
9 l
3 1 12 1
1 12 1
1 17 2
2 12 2
2 12 2
9 1
3 1
1 1
1 1
1 1 17 2
2 2
2 2
2 2
9 11 4
4 4
4 4
4 4 16 8
8 8
8 8
8 8 11 B.2.1. Axial Burnup Distribution Sample Case,2.00 wt% Enrichment, Burnup = 8.0 INF
(,4 qtr assy,50F, axial 2.0E(OSGWD),7 axial reg 30 ;iO3 0602 3 123 75 18 13 081 127 25 17 17 1 -18 104000001 11000 0000
-1.0-1.0-1.0-1.00.00.0 1 -922351 0.00116438 1 922381 0.0216162 1
80003 0.0455362 2 400000 0.0435745 3
10001 0.0668571 3 80003 0.0334308 4 240003 0.0177597 4 250005 0.00176933 4 260001 0.060M83 4 280003 0.00827827 5 0100010.03M711 5 050000 0.0309300 5 060002 0.0161958 5 080003 0.0140785 5 140005 0.00850730 6 010001 0.0503327 6 080003 0.0251680 6 400000 0.0107699 7 80003 4.55362E-02 _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _
Co B&W Fuel Company BAW-2209. Rev 1 7 -922351 3.71008E-04 g
7 922365 1.62168E-05 g
7 922381 2.22293E-02 7 942392 5.2N13E-05 7 942403 5.37097E-06 7 ~942412 1.30394E-06 7 621490 5.29596E-08 7 50100 2.58633E46 l
8 80003 4.55362E-02 5
8 -922351 3.19829E-04 8 922365 2.52158E-05 g
8 922381 2.21712E-02 g
8 942392 7.47605E-05 8 942403 1.19074E-05 8 942412 4.25179E-06 l
8 621490 6.02999E-08 g
8 50100 4.14724E-06 9 80003 4.55362E-02 9 -922351 2.98181E-04 9 922365 2.89425E-05 9 922381 2.21436E-02 g.
9 942392 8.26979E-05 9 942403 1.52N3E-05 g
9 942412 5.98733E-06 9 621490 6.27764E-08 gg 9 50100 4.87732E-06 10 80003 4.55362E-02 10 -922351 2.83278E-04 10 922365 3.14722E-05 g
10 922381 2.21234E-02 g
10 942392 8.75374E-05 10 942403 1.75837E-05 g
10 942412 7.39283E-06 g
10 621490 6.43095E-08 10 50100 5.40340E-06 11 80003 4.55362E-02 l,
11 -922351 3.10173E-04 3
11 922365 2.68849E-05 11 922381 2.21591E-02 g.
g 1I 942392 7.84260E-05 i1 942403 1.33419E-05 11 942412 4.99367E-06 11 621490 6.14854E-08 l
11 50100 4.46511E-06 3
12 80003 4.55362E-02 12 -922351 3.41190E44 12 922?65 2.14897E-05 12 922381 2.21966E-02 12 942392 6.59992E-05 12 942403 8.96118E-06 12 942412 2.79603E-06 !
=;
[.
L B&W Fuel Company BAW-2209. Rev 1 -
(
12 621490 5.75475E-08 12 50100 3.47371E-06
['
13 80003 4.55362E-02
(
13 -922351 3.88663E-04 13 922365 1.30629E-05 13 922381 2.22473E-02 3
[
13 942392 4.28189E-05 A
13 942403 3.58907E-06 13 942412 7.06522E-07
[.
13 621490 4.98962E-08 L.
13 50100 2.08758E-06 BOX TYPE 1 CYLINDER 1 0.46990 360.18 0.0123Z r
[
CYLINDER 0 0.47879 360.18 0.0123Z CYLINDER 2 0.54610 360.18 0.0123Z CUBOID 3 0.72136 -0.72136 0.72136 -0.72136 360.18 0.0123Z I
BOX TYPE 2 l
CYLINDER 7 0.46990 22.352 0.0123Z CYLINDER 8 0.46990 42.355 0.0123Z CYLINDER 9 0.46990 62.358 0.0123Z I
CYLINDER 10 0.46990 302.394 0.0123Z CYLINDER 11 0.46990 322.397 0.0123Z CYLINDER 12 0.46990 342.400 0.0123Z f
CYLINDER 13 0.46990 360.18 0.0123Z l
CYLINDER 0 0.47879 360.18 0.0123Z CYLINDER 2 0.54610 360.18 0.0123Z CUBOID 3 0.72136 -0.72136 0.72136 -0.72136 360.18 0.0123Z BOX TYPE 3 ZHEMICYL+X 1 0.46990 360.18 0.0123Z ZHEMICYL+X 0 0.47879 360.18 0.0 1237.
ZHEMICYL+X 2 0.54610 360.18 0.0123Z CUBOID 3 0.72136 0.0 0.72136 -0.72136 360.18 0.0123Z BOX TYPE 4 ZHEMICYL+Y I 0.46990 360.18 0.0123Z r
[
ZHEMICYL+Y 0 0.47879 360.18 0.0123Z ZHEMICYL+Y 2 0.54610 360.18 0.0123Z CUBOID 3 0.72136 -0.72136 0.72136 0.0 360.18 0.0123Z
[
BOX TYPE 5 L
ZHEMICYL-X 1 0.46990 360.18 0.0123Z ZHEMICYL X 0 0.47879 360.18 0.0123Z ZHEMICYL-X 2 0.54610 360.18 0.0123Z I
CUBOID 3 0.0 -0.72136 0.72136 -0.72136 360.18 0.0123Z BOX TYPE 6 ZHEMICYL-Y 1 0.46990 360.18 0.0123Z l
ZHEMICYL-Y 0 0.47879 360.18 0.0123Z l
ZHEMICYL Y 2 0.54610 360.18 0.0123Z CUBOID 3 0.72136 -0.72136 0.0 -0.72136 360.18 0.0123Z BOX TYPE 7 ZHEMICYL+X 7 0.46990 22.352 0.0123Z ZHEMICYL+X 8 0.46990 42.355 0.0123Z ZHEMICYL+X 9 0.46990 62.358 0.0123Z I l
y-b.
o B&W Fuel Company BAW-2209. Rev 1 l
. ZHEMICYL+X 10 0.46990 302.394 0.0 223Z ZHEMICYL+X 11 0.46990 322.397 0.0123Z W
ZHEMICYL+X 12 0.46990 342.400 0.0123Z ZHEMICYL+X 13 0.46990 360.18 0.0123Z ZHEMICYL+X 0 0.47879 360.18 0.0123Z ZHEMICYL+ X 2 0.54610 360.18 0.0123Z CUBOID 3 0.72136 0.0 0.72136 -0.72136 %0.18 0.0123Z BOX TYPE 8 ZHEMICYL+Y 7 0.46990 22.352 0.0123Z ZHEMICYL+Y 8 0.46990 42.355 0.0123Z ZHEMICYL+Y 9 0.46990 62.358 0.0123Z ZHEMICYL+ Y 10 0.46990 302.394 0.0123Z ZHEMICYL+Y I10.46990 322.397 0.0123Z ZilEMICYL+Y 12 0.46990 342.400 0.0123Z ZHEMICYL+Y 13 0.46990 360.18 0.0123Z l
ZHEMICYL+Y 0 0.47879 360.18 0.0123Z E
ZHEMICYL+Y 2 0.54610 360.18 0.0123Z CUBOID 3 0.72136 -0.72136 0.72136 0.0 360.18 0.0123Z BOX TYPE 9 9
ZHEMICYleX 7 0.46990 22.352 0.0123Z ZHEMICYl X 8 0.46990 42.355 0.0123Z ZHEMICYl X 9 0.46990 62.358 0.0123Z l
ZHEMICYl-X 10 0.46990 302.394 0.0123Z 5
ZHEMICYl X 11 0.46990 322.397 0.0123Z ZHEMICYl X 12 0.46990 342.400 0.0123Z ZHEMICYl X 13 0.46990 360.18 0.0123Z ZHEMICYL-X 0 0.47879 360.18 0.0123Z ZHEMICYleX 2 0.54610 360.18 0.0123Z CUB 01D 3 0.0 -0.72136 0.72136 -0.72136 360.18 0.0123Z BOX TYPE 10 ZHEMICYL-Y 7 0.46990 22.352 0.0123Z ZHEMICYL-Y 5L0.46990 42.355 0.0123Z ZHEMICYL-Y 9 0.46990 62.358 0.0123Z ZHEMICY1-Y 10 0.46990 302.394 0.0123Z ZHEMICYL-Y 11 0.46990 322.397 0.0123Z ZHEMICYL Y 12 0.46990 342.400 0.0123Z ZHEMICYleY 13 0.46990 360.18 0.0123Z ZHEMICYL-Y 0 0.47879 360.18 0.0123Z ZHEMICYl-Y 2 0.54610 360.18 0.0 1232.
CUBOID 3 0.72136 -0.72136 0.0 -0.72136 360.18 0.0123Z BOX TYPE 11 CUBOID 6 0.72136 0.0 0.72136 0.0 360.18 0.0123Z BOX TYPE 12 CYLINDER 3 0.63246 360.18 0.0123Z CYLINDER 2 0.67310 360.18 0.0123Z CUBOID 3 0.72136 -0.L136 0.72136 -0.72136 360.18 0.0123Z BOX TYPE 13 CUBOID 3 0.65024 0.0 0.72136 0.0 360.18 0.0123Z CUBOID 4 0.85344 0.0 0.72136 0.0 360.18 0.0123Z CUBOID 51.00076 0.0 0.72136 0.0 300.18 0.0123Z CUBOID 31.65100 0.0 0.72136 0.0 360.18 0.0123Z a.
l W
B&W Fuel Company BAW-2209. Rev 1 I
l.
1 BOX TYPE 14 CUBOID 3 0.65024 0.01.44272 0.0 360.18 0.0123Z l.
CUBOID 4 0.85344 0.01.44272 0.0 360.18 0.0123Z l
CUBOID 51.00076 0.01.44272 0.0 360.18 0.0123Z CUBOID 31.65100 0.01.44272 0.0 360.18 0.0123Z
.j BOX TYPE 15
{
i l
CUBOID ~
5 0.14732 0.0 0.0 -0.27432 360.18 0.0123Z j
I CUBOID 3 0.79756 0.0 0.0 1.44272 360.18 0.0123Z CUBOID 4 0.79756 -0.20320 0.0 -1.44272 360.18 0.0123Z j
CUBOID 3 0.79756 -0.85344 0.0 -1.44272 160.18 0.0123Z BOX TYPE 16 CUBOID 3 0.0 -0.65024 0.72136 0.0 360.18 0.0123Z 4
CUBOID 4 0.0 -0.85344 0.72136 0.0 360.18 0.0123Z '
l l
CUBOID 5 0.0 -1.00076 0.72136 0.0 360.18 0.0 ?23Z CUBOID 3 0.0 -1.65100 0.72136 0.0 360.18 0.0 1237 BOX TYPE 17 j
CUBOID 3 0.0 -0.650241.44272 0.0 360.18 0.0123Z CUBOID 4 0.0 -0.853441.44272 0.0 360.18 0.0123Z CUBOID 5 0.0 1.000761.44272 0.0 360.18 0.0123Z CUBOID 3 0.0 -1.651001.44272 0.0 360.18 0.0123Z l
BOX TYPE 18 CUBOID 50.i
-0.14732 0.27432 0.0 360.18 0.0123Z CUBOID 3 0.0
-0.797561.44272 0.0 360.18 0.0123Z j
CUBOID 4 0.20320 -0.797561.44272 0.0 360.18 0.0123Z CUBOID 3 0.85344 -0.797561.44272 0.0 360.18 0.0123Z BOX TYPE 19 CUBOID 3 0.72136 0.0 0.0 -0.65024 360.18 0.0123Z CUBOID 4 0.72136 0.0 0.0 -0.85344 360.18 0.0123Z CUBOID 5 0.72136 0.0 0.0 -1.00076 360.18 0.0123Z CUBOID 3 0.72136 0.0 0.0 -1.65100 360,18 0.0123Z l
BOX TYPE 20 CUBOID 31.44272 0.0 0.0 -0.65024 360.18 0.0123Z CUBOID 41.44272 0.0 0.0 -0.85344 360.18 0.0123Z CUBOID 51.44272 0.0 0.0 -1.00076 360.18 0.0123Z l
CUBOID 31.44272 0.0 0.0 -1.65100 360.18 0.0123Z BOX TYPE 21 g
CUDOID 5 0.27432 0.0 0.0
-0.14732 360.I8 0.0123Z l
CUBOID 3 1.44272 0.0 0.0
-0.79756 360.18 0.0123Z l
CUBOID 41.44272 0.0 0.20320 -0.79756 360.18 0.0123Z I
CUBOID 31.44272 0.0 0.85344 -0.79756 360.18 0.0123Z BOX TYPE 22 f
CUBOID 3 0.0 -0.72136 0.65024 0.0 360.18 0.0123Z CUBOID 4 0.0 -0.72136 0.85344 0.0 360.18 0.0123Z CUBOID 5 0.0 -0.721361.00076 0.0 360.18 0.0123Z CUBOD 3 0.0 -0.721361.65100 0.0 360,18 0.0123Z BOX TYPE 23 CUBOID 3 0.0 -1.44272 0.65024 0.0 360.18 0.0123Z CUBOID 4 0.0 -1.44272 0.85344 0.0 360.18 0.0123Z CUBOID 5 0.0 -1.442721.00076 0.0 360.18 0.0123Z CUBOID 3 0.0 -1.442721.65100 0.0 360.18 0.0123Z BOX TYPE 24. _ _ _ _ _ _
EOi ll B&W Fuel Company BAW-2209. Rev 1 CUBOID 5 0.0 -0.27432 0.14732 0.0 360.18 0.0123Z g
CUBOID 3 0.0 -1.44272 0.79756 0.0 360.18 0.0123Z g
CUBOID 4 0.0 -1.44272 0.79756 -0.20320 360.18 0.0123Z CUBOID 3 0.0 -1.44272 0.79756 -0.85344 360.18 0.0123Z g
g DOX TYPE 25 CUBOID 3 0.27240 -0.27240 0.27240 -0.27240 360.18 0.0123Z CUBOID 4 0.47560 -0.47560 0.47560 -0.47560 360.18 0.0123Z CUBOID 3 0.82550 -0.82550 0.82550 -0.82550 360.18 0.0123Z CORE BDY 3 23.29180 0.0 23.29180 0.0 360.18 0.0123Z CUBOID 3 23.29180 0.0 23.29180 0.0 390.68 -30.5123Z 02 021601 021601 111 0 g
07 010101 020801 111 0 g
07 010101 101601 111 0 08 020801 010101 111 0 08 101601 010101 111 0 l
09 17 17 01 101601 111 0 5
09 171701 020801 111 0 10 101601 171701 111 0 gg 10 02 08 01 17 17 01 111 0 11 011716 011716 I I I O 12 031512 031512 111 0 12 051308 051308 111 0 12 061206 031512 111 0 12 031512 061206 111 0 13 090901 171701 111 0 14 09 09 01 11 16 01 Ii10 15 090901 101001 111 0 16 090901 010101 111 0 g
17 09 09 01 02 07 01 111 0 18 090901 080801 111 0 g
19 01 01 01 09 09 01 111 0 20 020701 090901 111 0 g
g>
21 080801 090901 111 0 22 17 17 01 09 09 01 111 0 23 111601 090901 111 0 g
24 101001 090901 111 0 25 090901 090901 111 1 g
END CASE END KENO I
. a.