ML033510563
| ML033510563 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 12/10/2003 |
| From: | Canady K Duke Energy Corp |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| TAC MB7863, TAC MB7864 | |
| Download: ML033510563 (22) | |
Text
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Duke Duke Energy Corporation 526 South Church St.
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~~~~~~~~~~Charlotte, NC 28202 A Duke Energy Company EC08H P.O. Box 1006 Ken S. Canady (704) 382-4712 OFFICE Vice President (704) 382-7852 FAX Nuclear Engineering December 10, 2003 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555
Subject:
Duke Energy Corporation Catawba Nuclear Station Units 1 & 2, Docket Nos. 50-413, 50-414 Response to Request for Additional Information dated November 21, 2003 Regarding Mixed Oxide Fuel Lead Assemblies (TAC Nos. MB7863, MB7864)
By letter dated February 27, 2003 Duke Energy submitted an application to amend the licenses of McGuire and Catawba to allow the use of four mixed oxide fuel lead assemblies. As part of the review of this application the Nuclear Regulatory Commission staff in a letter dated November 21, 2003 requested that Duke provide additional information related to the application. The response to the NRC questions related to radiological consequences is attached to this letter. The remaining responses to questions relating to the NRC staff's environmental review should be provided by January 9, 2004.
This submittal includes information that is proprietary to Framatome ANP and in accordance with 10 CFR 2.790, Duke requests that this information be withheld from public disclosure. is the proprietary version of the response and Attachment 2 is a non-proprietary version. An affidavit attesting to the proprietary nature of this information from Framatome ANP, the owner of the information, is included. Pages that contain proprietary information are marked and the specific information that is proprietary is enclosed in [brackets].
Inquiries on this matter should be directed to G. A. Copp at (704) 373-5620.
K. S. Canady attachments ADD b
PROPRIETARY INFORMATION ATTACHED
U.S. Nuclear Regulatory Commission December 10, 2003 Page 2 Oath and Affirmation I affirm that I, K. S. Canady, am the person who subscribed my name to the foregoing, and that all the matters and facts set forth herein are true and correct to the best of my knowledge.
K. SCanady(
Subscribed and sworn to before me on this day of eo3.
Notary Public My Commission expires:
Date I-
U.S. Nuclear Regulatory Commission December 10, 2003 Page 3 cc: Nv/attachments I & 2 L. A. Reyes U. S. Nuclear Regulatory Commission Regional Administrator, Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 R. E. Martin (addressee only)
NRC Project Manager U. S. Nuclear Regulatory Commission Mail Stop O-8G9 Washington, DC 20555-0001 E. F. Guthrie Senior Resident Inspector U. S. Nuclear Regulatory Commission Catawba Nuclear Station J. B. Brady Senior Resident Inspector U. S. Nuclear Regulatory Commission McGuire Nuclear Station cc: Nv/attachment 2 Diane Curran Harmon, Curran, Spielberg & Eisenberg, LLP 1726 M Street, N.W.
Suite 600 Washington, DC 20036 Mary Olson Director, Southeast Office Nuclear Information and Resource Service P.O. Box 7586 Asheville, NC 28802 H. J. Porter, Director Division of Radioactive Waste Management Bureau of Land and Waste Management Department of Health and Environmental Control Columbia, SC 29201
U.S. Nuclear Regulatory Commission December 10, 2003 Page 4 bcc: 'v/attachment 2 Richard Clark-DCS Patrick Rhoads-DOE David Alberstein-DOE Don Spellman-ORNL NCMPA-1 NCEMC PMPA SRE bcc: wv/attachments 1 & 2 (via email)
S. P. Nesbit M. T. Cash F. J. Verbos J. L. Eller S. P. Schultz L. F Vaughn M. W. Scott L. J. Rudy J. Hoerner - Framratome ANP G. A. Meyer - Framatome ANP bcc: wv/attachments 1 & 2 (paper copy)
NRIA File/ELL - ECO50 MOX File 1607.2304 Catawba Document Control File 801.01-CN04DM Catawba RGC Date File (J. M. Ferguson - CNOISA)
AFFIDAVIT COMMONWEALTH OF VIRGINIA
)
) ss.
CITY OF LYNCHBURG
)
- 1.
My name is Gayle F. Elliott. I am Manager, Product Licensing in Regulatory Affairs, for Framatome ANP ("FANP"), and as such I am authorized to execute this Affidavit.
- 2.
1 am familiar with the criteria applied by FANP to determine whether certain FANP information Is proprietary. I am familiar with the policies established by FANP to ensure the proper application of these criteria.
- 3.
I am familiar with the table listing the parameters that the NRC staff will use in assessing fission gas release and fission gas pressure in the lead test assemblies provided as an attachment to a letter from M.S. Tuckman, Duke Energy Corporation, to the U.S. Nuclear Regulatory Commission entitled "Duke Energy Corporation, Catawba Nuclear Station Units I &
2, Docket Nos. 50413, 50-414, Response to Request for Additional Information dated November 21, 2003, Regarding Mixed Oxide Fuel Lead Assemblies (TAC Nos. MB7863, MB7864)" and referred to herein as wDocument.' Information contained In this Document has been classified by FANP as proprietary In accordance with the policies established by FANP for the control and protection of proprietary and confidential information.
- 4.
This Document contains information of a proprietary and confidential nature and is of the type customarily held In confidence by FANP and not made available to the public.
Based on my experience, I am aware that other companies regard information of the kind contained in this Document as proprietary and confidential.
- 5.
This Document has been made available to the U.S. Nuclear Regulatory Commission in confidence with the request that the information contained in this Document be withheld from public disclosure.
- 6.
The following criteria are customarily applied by FANP to determine whether information should be classified as proprietary:
(a)
The information reveals details of FANP's research and development plans and programs or their results.
(b)
Use of the information by a competitor would permit the competitor to significantly reduce its expenditures, in time or resources, to design, produce, or market a similar product or service.
(c)
The information includes test data or analytical techniques concerning a*
process, methodology, or component, the application of which results In a competitive advantage for FANP.
(d)
The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides a competitive advantage for FANP in product optimization or marketability.
(e)
The information is vital to a competitive advantage held by FANP, would be helpful to competitors to FANP, and would likely cause substantial harm to the competitive position of FANP.
- 7.
In accordance with FANP's policies governing the protection and control of information, proprietary information contained in this Document have been made available, on a limited basis, to others outside FANP only as required and under suitable agreement providing for nondisclosure and limited use of the information.
- 8.
FANP policy requires that proprietary information be kept in a secured file or area and distributed on a need-to-know basis.
r
- 9.
The foregoing statements are true and correct to the best of my knowledge, information, and belief.
SUBSCRIBED before me this day of 2003.
Ella F. Carr-Payne NOTARY PUBLIC, STATE OF VIRGINIA MY COMMISSION EXPIRES: 8/31105 ELLA F. CARR-PAYNE I
@1 Notary Public Comrnornealth of Vrginia My Cormdnion Exps. Aug. 31. 2005
Table 2 MOX Fuel Lead Assembly Peak Pin Relative Power vs Fuel Cycle Exposure (burnup)
Fuel Cycle MOX Fuel Lead Assembly MOX Fuel Lead Assembly Exposure Peak Pin Exposure Peak Pin Relative Power EFPD GWd / Mthm F delta-h Cycle 1 1t Cycle 2 4
0.246 1.426 12 0.711 1.403 25 1.448 1.372 50 2.814 1.327 100 5.411 1.273 150 7.883 1.245 200 10.272 1.230 250 12.601 1.223 300 14.928 1.222 350 17.292 1.222 400 19.653 1.225 450 22.010 1.230 470 22.953 1.231 490 23.895 1.232 495 24.131 1.233 4
25.233 1.363 12 25.621 1.361 25 26.247 1.345 50 27.430 1.315 100 29.728 1.267 150 31.955 1.233 200 34.130 1.212 250 36.265 1.193 300 38.370 1.179 350 40.449 1.167 400 42.505 1.157 450 44.544 1.148 487 46.060 1.144 507 46.916 1.142 512 47.131 1.142 4
47.210 0.675 12 47.317 0.664 25 47A88 0.651 50 47.808 0.629 100 48.422 0.600 150 49.265 0.588 200 50.254 0.586 250 51.252 0.593 300 52.316 0.603 350 53.425 0.616 400 54.564 0.630 450 55.735 0.647 467 56.141 0.654 487 56.623 0.661 492 56.746 0.662 If Cycle 3 It 7
Table 3 MOX Fuel Lead Assembly Axial Power Profile Fuel Cycle Exposure EFPD 4
100 200 300 400 490 4
100 200 300 400 507 4
100 200 300 400 487 A-1-1 I -..-
I IlfV I lAE A-d-1 Dn-I n-V.1-Top of Core Bottom of Core Average MAIaI Ltvel IVI_ JjA L. I IucIAd rUWe5 rIUiIII 24 0.540 0.466 0.479 0.530 0.591 0.647 0.579 0.479 0.497 0.559 0.631 0.705 0.561 0.468 0.492 0.554 0.622 0.679 23 0.755 0.669 0.681 0.731 0.780 0.815 0.848 0.721 0.733 0.793 0.851 0.895 0.848 0.729 0.755 0.819 0.876 0.910 22 0.909 0.832 0.845 0.892 0.931 0.951 1.001 0.885 0.895 0.949 0.992 1.013 0.999 0.892 0.920 0.980 1.022 1.039 21 1.009 0.954 0.965 1.002 1.025 1.029 1.079 0.992 0.998 1.038 1.062 1.063 1.066 0.990 1.016 1.062 1.086 1.086 20 1.046 1.016 1.022 1.044 1.052 1.043 1.101 1.049 1.047 1.069 1.076 1.063 1.091 1.049 1.065 1.094 1.100 1.088 19 1.059 1.053 1.050 1.057 1.052 1.036 1.107 1.085 1.070 1.076 1.069 1.048 1.101 1.089 1.093 1.103 1.095 1.075 18 1.079 1.091 1.079 1.071 1.056 1.035 1.116 1.118 1.090 1.078 1.061 1.036 1.106 1.118 1.109 1.102 1.083 1.060 17 1.086 1.115 1.093 1.072 1.050 1.028 1.117 1.138 1.098 1.073 1.050 1.025 1.107 1.140 1.118 1.095 1.070 1.045 16 1.096 1.138 1.108 1.077 1.050 1.028 1.120 1.156 1.106 1.070 1.042 1.019 1.108 1.156 1.123 1.088 1.058 1.034 15 1.081 1.134 1.100 1.062 1.034 1.014 1.104 1.155 1.100 1.058 1.029 1.009 1.103 1.165 1.123 1.080 1.047 1.026 14 1.099 1.160 1.121 1.076 1.045 1.026 1.110 1.171 1.111 1.061 1.030 1.011 1.101 1.173 1.124 1.074 1.040 1.021 13 1.098 1.165 1.125 1.077 1.046 1.028 1.103 1.173 1.114 1.060 1.028 1.011 1.097 1.176 1.125 1.070 1.035 1.018 12 1.082 1.154 1.118 1.069 1.038 1.022 1.085 1.162 1.109 1.055 1.024 1.008 1.090 1.173 1.123 1.066 1.032 1.015 11 1.096 1.168 1.136 1.087 1.055 1.038 1.085 1.165 1.120 1.064 1.031 1.015 1.084 1.168 1.122 1.065 1.031 1.015 10 1.095 1.166 1.142 1.096 1.064 1.047 1.075 1.156 1.123 1.071 1.037 1.020 1.076 1.157 1.119 1.066 1.032 1.017 9
1.089 1.155 1.142 1.103 1.072 1.056 1.061 1.140 1.124 1.078 1.045 1.027 1.068 1.143 1.117 1.070 1.037 1.023 8
1.072 1.129 1.130 1.101 1.075 1.060 1.040 1.114 1.118 1.083 1.053 1.034 1.058 1.122 1.111 1.075 1.046 1.032 7
1.086 1.128 1.142 1.125 1.104 1.089 1.038 1.098 1,123 1.100 1.073 1.053 1.050 1.096 1.101 1.078 1.056 1.044 6
1.084 1.103 1.131 1.131 1.119 1.109 1.026 1.066 1.112 1.108 1.089 1.072 1.038 1.061 1.084 1.079 1.067 1.059 5
1.058 1.049 1.090 1.109 1.112 1.111 1.001 1.014 1.079 1.098 1.095 1.086 1.022 1.014 1.053 1.069 1.073 1.073 4
1.056 1.009 1.055 1.092 1.112 1.123 0.991 0.965 1.041 1.081 1.095 1.100 0.998 0.953 1.002 1.039 1.061 1.074 3
1.004 0.917 0.960 1.009 1.047 1.075 0.939 0.873 0.949 1.007 1.043 1.069 0.940 0.857 0.909 0.962 1.004 1.034 2
0.875 0.761 0.791 0.840 0.886 0.925 0.782 0.696 0.763 0.829 0.885 0.935 0.787 0.687 0.733 0.793 0.850 0.896 1
0.547 0.469 0.497 0.547 0.604 0.661 0.489 0.426 0.478 0.542 0.609 0.683 0.501 0.425 0.461 0.516 0.577 0.636 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 8
Table 4 SAS2H Input Deck Listing
=sas2h parm=(haltO8,skipshipdata) fuel type=MOX-OBP enr=0.25 puload=5.00 burnup=16.9 gwd/mtu 44groupndf5 latticecell uo2 1 0.8939 1085.34 92234 0.0017 92235 0.2500 92236 0.0012 92238 99.7471 end puo2 1 0.0450 1085.34 94238 0.0250 94239 92.5000 94240 6.9250 94241 0.5000 94242 0.0500 end kr-83 1 0 1-20 1085.34 end kr-85 1 0 1-20 1085.34 end sr-90 1 0 1-20 1085.34 end y-89 1 0 1-20 1085.34 end zr-93 1 0 1-20 1085.34 end zr-94 1 0 1-20 1085.34 end zr-95 1 0 1-20 1085.34 end mo-94 1 0 1-20 1085.34 end nb-94 1 0 1-20 1085.34 end nb-95 1 0 1-20 1085.34 end mo-95 1 0 1-20 1085.34 end tc-99 1 0 1-20 1085.34 end rh-103 1 0 1-20 1085.34 end rh-105 1 0 1-20 1085.34 end ru-106 1 0 1-20 1085.34 end sn-126 1 0 1-20 1085.34 end xe-131 1 0 1-20 1085.34 end xe-132 1 0 1-20 1085.34 end xe-133 1 0 1-20 1085.34 end xe-134 1 0 1-20 1085.34 end xe-135 1 0 1-20 1085.34 end xe-136 1 0 1-20 1085.34 end cs-133 1 0 1-20 1085.34 end cs-134 1 0 1-20 1085.34 end cs-135 1 0 1-20 1085.34 end cs-137 1 0 1-20 1085.34 end ba-136 1 0 1-20 1085.34 end la-139 1 0 1-20 1085.34 end pr-143 1 0 1-20 1085.34 end nd-143 1 0 1-20 1085.34 end ce-144 1 0 1-20 1085.34 end nd-144 1 0 1-20 1085.34 end nd-145 1 0 1-20 1085.34 end nd-146 1 0 1-20 1085.34 end nd-147 1 0 1-20 1085.34 end pm-147 1 0 1-20 1085.34 end sm-147 1 0 1-20 1085.34 end nd-148 1 0 1-20 1085.34 end pm-148 1 0 1-20 1085.34 end 9
Table 4 SAS2H Input Deck Listing sm-148 pm-149 sm-149 nd-150 sm-150 Sm-151 eu-151 sm-152 eu-153 eu-154 gd-154 eu-155 gd-155 gd-157 gd-158 gd-160 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 1-20 1-20 1-20 1-20 1-20 1-20 1-20 1-20 1-20 1-20 1-20 1-20 1-20 1-20 1-20 1-20 1085.34 1085.34 1085.34 1085.34 1085.34 1085.34 1085.34 1085.34 1085.34 1085.34 1085.34 1085.34 1085.34 1085.34 1085.34 1085.34 end end end end end end end end end end end end end end end end arbm-m5 6.50 3 0 0 0 40000 98.873 41000 1.0 8016 0.127 2 1 656.16 end h2o 3 den=0.711 1.0 580.43 end arbm-bormod 0.711 1 1 0 0 5000 100 3 900.0e-6 580.43 end end comp squarepitch 1.2598 0.8191 1 3 0.9500 2 0.8357 0 end npin=264 fuel=365.76 ncyc=2 nlib=4 prin=6 inpl=1 numh=24 numi=1 ortu=0.6121 srtu=0.5715 end power=29.745 burn=233.29 down= 0.00 end power=29.745 burn= 30.30 down= 0.00 tmpfuel=1085.34 tmpclad=656.16 end end 10 Duke Response to NRC Staff Request for Additional Information Dated November 21, 2003 (NON-PROPRIETARY)
Duke Response to NRC Staff Request for Additional Information Dated November 21, 2003
- 1. The table below lists the parameters that the NRC staff will use in assessing fission gas release (isotopic gap fractions) and fission gas pressure in the lead test assemblies (LTAs).
This data has been extracted from the February 27, 2003 submittal. The NRC staff also completed some fields using generic data from NUREG-1754, "A New Comparative Analysis of LWR Fuel Designs." The NRC staff requests that Duke complete the missing data items and confirm that the values in the table are those that have been or will be used for safety analyses and thus become part of the design basis for the LTA irradiation.
Response
Table 1 lists all the parameters identified by the NRC staff as needed to assess the fission gas release and fission gas pressure in the MOX fuel lead assemblies. Previously missing or corrected data items are included in Table 1 in a new column titled "Actual Value." Where the NRC-determined values ("NRC Value" column) in the table were correct, the "Actual Value" column indicates "Same." Proprietary values are enclosed in brackets.
- 2. Please provide projected power histories for the LTAs. These would typically tabulate or plot peak rod average power, kW/fl, versus time (days) since start of irradiation (or versus average burnup, MWd/MThm). If a projected power history specifically for the LTAs is not available, please provide the average kW/ft data and the appropriate peaking factors.
Response
Table 2 provides the fuel pin average burnup and pin average relative power factors for the peak pin in the MOX fuel lead assembly for three cycles of irradiation. The pin average relative power factors are normalized to a core average of 1.0.
- 3. Please provide the axial power profile expected in the LTAs. These would typically tabulate or plot normalized power versus height.
Response
Table 3 contains axial power profiles for the MOX fuel lead assemblies at 18 burnup points over three cycles of irradiation. The MOX fuel lead assembly is located in-core location C08 in the first cycle, E08 in the second cycle, and C14 in the third cycle. See Figure Q1 1-1 in Duke's November 4, 2003 response to the NRC Staff Request for Additional Information dated July 25, 2003 for a quarter-core map showing lead assembly core locations.
- 4. In the response to Question 3(f) in the letter dated 11/3/2003, Duke identified that the SCALE/SAS2H code suite was used to establish the source term used in the safety analyses.
1
Please provide a listing of the SAS2H input data file(s) for the case(s) that generated the fuel assembly inventory used in the fuel handling accident shown in Table Q3(f)-l. The staff is particularly interested in the SAS2H case that would have generated the MOX fuel cross-section library used in the safety analysis work.
Response
Table 4 is a listing of the SAS2H input deck used to generate the isotopic information shown in Table Q3(f)-I of Duke's November 4, 2003 response to the NRC Staff Request for Additional Information dated July 25, 2003.
2
NON-PROPRIETARY Table 1 MOX Fuel Lead Assembly Fuel Parameters NRC Actual Parameter Value Value Number of fuel rods per 264 Same assembly Fuel rod pitch, in.
0.496 Same Cladding OD, in.
0.374 Same Cladding ID, in.
0.329 Same Cladding thickness, in.
0.0225 Same Cladding material M5 Same Fuel diameter, in.
0.3225 Same Fuel pellet length, in.
? 0.45
[
Fuel pellet volume reduction 1.0 1.11 due to dish and chamfer, %.(Note 1)
Fuel pellet dish diameter, in.
? 0.158?
[
Fuel pellet dish depth, in.
? 0.0113?
]
Fuel rod length, in.
152.40 Same Active fuel length, in.
144.0 Same Plenum length, in.
? 10?
[
Pellet initial density, % TD 95 Same Pellet oxygen to metal ratio (a realistic value is preferred to a
?
]
manufacturing limit)
Rod internal void volume, cu.
?
[
]
in.
Plenum spring diameter
? 0.3225?
[
Plenum spring wire diameter,
? 0.05?
in.
Turns in plenum spring
? 28?
[
]
Helium fill gas pressure, psi
? 350 ?
[
] psig 3
NON-PROPRIETARY Table 1 MOX Fuel Lead Assembly Fuel Parameters NRC Actual Parameter Value Value RCS pressure, psia 2310 2250 Reactor Power, MWt 3411 Same Coolant Flow, lb/ft2 - hr
? 2.55E6 ?
1.43E6 Coolant Flow,
~~~~~~~(Note 2)
Coolant inlet temperature, F 555 Same Coolant outlet temperature, F 616 619 Channel temperature rise, F
?
(Note 4)
(for the limiting LTA)
Temperature at which pellets
? 2911 ?
were sintered, F Limit on pellet density
? 0.9?
(
l increase, % TD (95/95 limit)
Limit on pellet swelling, %
? 5 ?
(Note 5)
Fuel surface roughness, in.
? 3E-5?
[
Cladding ID surface
? 2E-5?
[
roughness, in.
Initial crud thickness, in.
? 0 ?
0.0 Lattice geometry 17 x 17 Same Maximum fuel rod burnup, 50000 60,000 MWd/MThm (Note 6)
Heavy metal loading per 462.6 Same assembly, kg Hot pin and hot assembly 1.60 Note 7 radial peaking factors Highest allowable total peaking for MOX fuel 2.4 Note 7 assembly (FO)
Core axial peaking factor 2.4 Note 7 4
NON-PROPRIETARY Table 1 MOX Fuel Lead Assembly Fuel Parameters Parameter NRC Actual Parameter Value Value Nominal average Pu concentration, wlo percent 4.37 Same Pu, in a radially zoned fuel assembly containing pellets 4.94 (176 rods)
Same with nominal Pu 3.35 (76 rods)
Same concentration.
2.4 (12 rods)
Same (4.37 x TD = 4.15 w/o-%
24(2rd)
Sm fissile)
Unirradiated isotopic composition, % of base element Pu-238 0.025 Same Pu-239 92.5 Same Pu-240 6.925 Same Pu-241 0.5 Same Pu242 0.05 Same U-235 0.25 Same U-234 0.0017 Same U-236 0.0012 Same U-238 99.741 Same Note 1 - The LAR incorrectly gives only the volume reduction of the end dish. The total volume reduction of the end dish and chamfer is correctly noted in the MOX Fuel Design Report as 1.11 %.
Note 2 - Coolant flow calculated at inlet conditions for the total core cross sectional area.
Note 3 - Core outlet temperature.
Note 4 - This parameter varies as the power distribution changes as follows:
(Cycle 1) 4 100 200 300 400 490 Assembly Peaking 1.291 1.146 1.109 1.107 1.121 1.134 Factor IIII Delta T (cF) 77 70 67 66 67 67 where Delta T is the axial temperature rise predicted for the MOX fuel lead assembly by the core nuclear analysis code.
5
NON-PROPRIETARY Table 1 MOX Fuel Lead Assembly Fuel Parameters Note 5 - No specified limit on pellet swelling. Best estimate value = [
Note 6 - One or more lead assemblies are proposed for a third cycle of operation leading to a maximum peak rod burnup of 60,000 GWd/MThm; whereas batches of MOX fuel will undergo two cycles of irradiation with a maximum peak rod burnup of 50,000 GWd/MThm.
Note 7 - Peaking factors identified in Table 3-2 are conservatively high peaking factors used in LOCA analysis. Realistic peaking factors for a MOX fuel lead assembly in a representative core are provided in the responses to Questions 2 and 3.
6
Table 2 MOX Fuel Lead Assembly Peak Pin Relative Power vs Fuel Cycle Exposure (burnup)
Fuel Cycle Exposure EFPD MOX Fuel Lead Assembly Peak Pin Exposure GWd / Mthm MOX Fuel Lead Assembly Peak Pin Relative Power F delta-h Cycle I I,
I Cycle 2 4
0.246 1.426 12 0.711 1.403 25 1.448 1.372 50 2.814 1.327 100 5.411 1.273 150 7.883 1.245 200 10.272 1.230 250 12.601 1.223 300 14.928 1.222 350 17.292 1.222 400 19.653 1.225 450 22.010 1.230 470 22.953 1.231 490 23.895 1.232 495 24.131 1.233 4
25.233 1.363 12 25.621 1.361 25 26.247 1.345 50 27A30 1.315 100 29.728 1.267 150 31.955 1.233 200 34.130 1.212 250 36.265 1.193 300 38.370 1.179 350 40.449 1.167 400 42.505 1.157 450 44.544 1.148 487 46.060 1.144 507 46.916 1.142 512 47.131 1.142 4
47.210 0.675 12 47.317 0.664 25 47.488 0.651 50 47.808 0.629 100 48.422 0.600 150 49.265 0.588 200 50.254 0.586 250 51.252 0.593 300 52.316 0.603 350 53.425 0.616 400 54.564 0.630 450 55.735 0.647 467 56.141 0.654 487 56.623 0.661 492 56.746 0.662 I
Cycle 3 It 7
Table 3 MOX Fuel Lead Assembly Axial Power Profile Fuel Cycle Exposure EFPD 4
100 200 300 400 490 4
100 200 300 400 507 4
100 200 300 400 487 A,4n1 I -.- I RAnV I TA AerI 0nw, Dfin Top of Core Bottom of Core Average 24 0.540 0.466 0.479 0.530 0.591 0.647 0.579 0.479 0.497 0.559 0.631 0.705 0.561 0.468 0.492 0.554 0.622 0.679 23 0.755 0.669 0.681 0.731 0.780 0.815 0.848 0.721 0.733 0.793 0.851 0.895 0.848 0.729 0.755 0.819 0.876 0.910 22 0.909 0.832 0.845 0.892 0.931 0.951 1.001 0.885 0.895 0.949 0.992 1.013 0.999 0.892 0.920 0.980 1.022 1.039 21 1.009 0.954 0.965 1.002 1.025 1.029 1.079 0.992 0.998 1.038 1.062 1.063 1.066 0.990 1.016 1.062 1.086 1.086 20 1.046 1.016 1.022 1.044 1.052 1.043 1.101 1.049 1.047 1.069 1.076 1.063 1.091 1.049 1.065 1.094 1.100 1.088 19 1.059 1.053 1.050 1.057 1.052 1.036 1.107 1.085 1.070 1.076 1.069 1.048 1.101 1.089 1.093 1.103 1.095 1.075 18 1.079 1.091 1.079 1.071 1.056 1.035 1.116 1.118 1.090 1.078 1.061 1.036 1.106 1.118 1.109 1.102 1.083 1.060 17 1.086 1.115 1.093 1.072 1.050 1.028 1.117 1.138 1.098 1.073 1.050 1.025 1.107 1.140 1.118 1.095 1.070 1.045 16 1.096 1.138 1.108 1.077 1.050 1.028 1.120 1.156 1.106 1.070 1.042 1.019 1.108 1.156 1.123 1.088 1.058 1.034 15 1.081 1.134 1.100 1.062 1.034 1.014 1.104 1.155 1.100 1.058 1.029 1.009 1.103 1.165 1.123 1.080 1.047 1.026 14 1.099 1.160 1.121 1.076 1.045 1.026 1.110 1.171 1.111 1.061 1.030 1.011 1.101 1.173 1.124 1.074 1.040 1.021 13 1.098 1.165 1.125 1.077 1.046 1.028 1.103 1.173 1.114 1.060 1.028 1.011 1.097 1.176 1.125 1.070 1.035 1.018 12 1.082 1.154 1.118 1.069 1.038 1.022 1.085 1.162 1.109 1.055 1.024 1.008 1.090 1.173 1.123 1.066 1.032 1.015 11 1.096 1.168 1.136 1.087 1.055 1.038 1.085 1.165 1.120 1.064 1.031 1.015 1.084 1.168 1.122 1.065 1.031 1.015 10 1.095 1.166 1.142 1.096 1.064 1.047 1.075 1.156 1.123 1.071 1.037 1.020 1.076 1.157 1.119 1.066 1.032 1.017 9
1.089 1.155 1.142 1.103 1.072 1.056 1.061 1.140 1.124 1.078 1.045 1.027 1.068 1.143 1.117 1.070 1.037 1.023 8
1.072 1.129 1.130 1.101 1.075 1.060 1.040 1.114 1.118 1.083 1.053 1.034 1.058 1.122 1.111 1.075 1.046 1.032 7
1.086 1.128 1.142 1.125 1.104 1.089 1.038 1.098 1.123 1.100 1.073 1.053 1.050 1.096 1.101 1.078 1.056 1.044 6
1.084 1.103 1.131 1.131 1.119 1.109 1.026 1.066 1.112 1.108 1.089 1.072 1.038 1.061 1.084 1.079 1.067 1.059 5
1.058 1.049 1.090 1.109 1.112 1.111 1.001 1.014 1.079 1.098 1.095 1.086 1.022 1.014 1.053 1.069 1.073 1.073 4
1.056 1.009 1.055 1.092 1.112 1.123 0.991 0.965 1.041 1.081 1.095 1.100 0.998 0.953 1.002 1.039 1.061 1.074 3
1.004 0.917 0.960 1.009 1.047 1.075 0.939 0.873 0.949 1.007 1.043 1.069 0.940 0.857 0.909 0.962 1.004 1.034 2
0.875 0.761 0.791 0.840 0.886 0.925 0.782 0.696 0.763 0.829 0.885 0.935 0.787 0.687 0.733 0.793 0.850 0.896 1
0.547 0.469 0.497 0.547 0.604 0.661 0.489 0.426 0.478 0.542 0.609 0.683 0.501 0.425 0.461 0.516 0.577 0.636 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 8
Table 4 SAS2H Input Deck Listing
=sas2h parm=(haltO8,skipshipdata) fuel type=MOX-OBP enr=0.25 puload=5.00 burnup=16.9 gwd/mtu 44groupndf5 latticecell uo2 1 0.8939 1085.34 92234 0.0017 92235 0.2500 92236 0.0012 92238 99.7471 end puo2 1 0.0450 1085.34 94238 0.0250 94239 92.5000 94240 6.9250 94241 0.5000 94242 0.0500 end kr-83 1 0 1-20 1085.34 end kr-85 1 0 1-20 1085.34 end sr-90 1 0 1-20 1085.34 end y-89 1 0 1-20 1085.34 end zr-93 1 0 1-20 1085.34 end zr-94 1 0 1-20 1085.34 end zr-95 1 0 1-20 1085.34 end mo-94 1 0 1-20 1085.34 end nb-94 1 0 1-20 1085.34 end nb-95 1 0 1-20 1085.34 end mo-95 1 0 1-20 1085.34 end tc-99 1 0 1-20 1085.34 end rh-103 1 0 1-20 1085.34 end rh-105 1 0 1-20 1085.34 end ru-106 1 0 1-20 1085.34 end sn-126 1 0 1-20 1085.34 end xe-131 1 0 1-20 1085.34 end xe-132 1 0 1-20 1085.34 end xe-133 1 0 1-20 1085.34 end xe-134 1 0 1-20 1085.34 end xe-135 1 0 1-20 1085.34 end xe-136 1 0 1-20 1085.34 end cs-133 1 0 1-20 1085.34 end cs-134 1 0 1-20 1085.34 end cs-135 1 0 1-20 1085.34 end cs-137 1 0 1-20 1085.34 end ba-136 1 0 1-20 1085.34 end la-139 1 0 1-20 1085.34 end pr-143 1 0 1-20 1085.34 end nd-143 1 0 1-20 1085.34 end ce-144 1 0 1-20 1085.34 end nd-144 1 0 1-20 1085.34 end nd-145 1 0 1-20 1085.34 end nd-146 1 0 1-20 1085.34 end nd-147 1 0 1-20 1085.34 end pm-147 1 0 1-20 1085.34 end sm-147 1 0 1-20 1085.34 end nd-148 1 0 1-20 1085.34 end pm-148 1 0 1-20 1085.34 end 9
Table 1 MOX Fuel Lead Assembly Fuel Parameters sm-148 pm-149 sm-149 nd-150 Sm-150 Sm-151 eu-151 sm-152 eu-153 eu-154 gd-154 eu-155 gd-155 gd-157 gd-158 gd-160 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1-20 1-20 1-20 1-20 1-20 1-20 1-20 1-20 1-20 1-20 1-20 1-20 1-20 1-20 1-20 1-20 1085.34 1085.34 1085.34 1085.34 1085.34 1085.34 1085.34 1085.34 1085.34 1085.34 1085.34 1085.34 1085.34 1085.34 1085.34 1085.34 end end end end end end end end end end end end end end end end arbm-m5 6.50 3 0 0 0 40000 98.873 41000 1.0 8016 0.127 2 1 656.16 end h2o 3 den=0.711 1.0 580.43 end arbm-bormod 0.711 1 1 0 0 5000 100 3 900.Oe-6 580.43 end end comp squarepitch 1.2598 0.8191 1 3 0.9500 2 0.8357 0 end npin=264 fuel=365.76 ncyc=2 nlib=4 prin=6 inpl=1 numh=24 numi=1 ortu=0.6121 srtu=0'5715 end power=29.745 burn=233.29 down= 0.00 end power=29.745 burn= 30.30 down= 0.00 tmpfuel=1085.34 tmpclad=656.16 end end 10