ML061640242

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Tn Calculation 1121-0401, Revision 1, OS197L Ton Transfer Cask Thermal Analysis to Be Used with OPPD Exemption Request (18.4 Kw/Dsc & 11.0 Kw/Dsc).
ML061640242
Person / Time
Site: Fort Calhoun, 07201004  Omaha Public Power District icon.png
Issue date: 06/06/2006
From: Axline J, Guzeyev S, Qi D
Transnuclear
To:
Office of Nuclear Reactor Regulation
References
1121-010, LIC-06-056 1121-0401, Rev 1
Download: ML061640242 (26)
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Text

LIC-06-056 Page 1 TN Calculation 1121-0401, Revision 1, 0S197L 75 Ton Transfer Cask Thermal Analysis to be used with OPPD Exemption Request (18.4 kWIDSC & 11.0 kWIDSC

A TRANS NUC LEAR Form 3.2-1 Calculation Cover Sheet Calculation No.: 1121-0401 AN AREVA ComPAy Revision No.: 1 CALCULATION TITLE: Page: Ilof 25 0S1 97L 75 Ton Transfer Cask Thermal Analysis to be Project No.: 1121 Used With OPPID Exemption Request (18.4 kW/DSC & 11. 0 kW/DSC) DCR No.: 1121-010 PROJECT NAME:

Fort Calhoun Station Spent Fuel Storage Project Number of CDs attached:

2 CDs If original Issue, Is licensing review per TIP 3.5 required?

ZNo (explain) 0Yes Licensing Review No.:

This calculation determines maximum fuel cladding temperature within the OS1 97L TO in support of an exemption request by OPPID to be submitted to the NRC. OPPD) Isplanning to load the NUHOMS4) 32PT DSC using the 051 97L Transfer Cask. These calculations are NOT the design basis for the NUHOMSO 32PT System Configurations. Therefore, a 72.48 licensing review per TIP 3.5 Isnot required.

Software Uitilized: Version:

ANSYS 8.1 Calculation is complete:

0r i1nator Signature: Davy Qi Date:

Calcuiation has been checked for consistency, completeness and correctness:

Checker Signature: S lava Guzeyev Date:

Calculation Is approved for use:

6 Date ý0 I-

A TRANSNUCLEAR Calculation Calculation No.:

Revision No.:

1121-0401 1

K AN ARVA CoPANYPage: 2 of25 REVISION

SUMMARY

DESRIPIONAFFECTED AFFECTED DESRIPIONPAGES Discs Initial issue - Calculation of maximum fuel clad All All temperatures for 18.4 kW heat load per DSC _____ ___

To incorporate Appendix A, which calculates maximum fuel cladding temperature within the OS 197L TC based on OPPID candidate fuel 1-6, 9, 13, assemblies with maximum 11 kW heat load per DSC. 62 2 This revision also uses the fuel properties of the 1-OPPD fuel assembly (CE 14x14 FC). Minor editorial corrections are Incorporated. __________

A TRANSNUCLEAR Calculation Calculation No.: 1121-0401 Revision No.: 1 AN AREVA COMPANY Page: 3 of 25 TABLE OF CONTENTS Page 1.0 PURPOSE....................................................................................... 7 2.0 ASSUM PTIONS/CONSERVATISMS.......................................................... 7 3.0 DESIGN INPUT - 18.4 kW..................................................................... 7 4.0 METHODOLOGY............................................................................... 8 5.0 FINITE ELEMENT MODELS ................................................................... 9 5.1 2D 0S197L Cask Thermal Model ....................................................... 9 5.2 3D 32PTDSC Thermal Model......................................................... 11 5.3 Methodology to Determine Maximum Fuel Cladding Temperatures in 0S197L Transfer Cask with Skid Shielding ..................................................... 12

6.0 REFERENCES

................................................................................ 13 7.0 COMPUTATIONS............................................................................. 14 8.0 RESULTS and Summary ..................................................................... 15 8.1 Temperature of 0S197L Components, and 18.4 kW DSC Shell .................... 15 8.2 Evaluation of Maximum Fuel Cladding Temperature during Transfer in 0S197L ... 17 8.3 Effect of Skid Shielding on Thermal Analysis Results ................................ 18 APPENDIX A EVALUATION OF MAXIMUM FUEL CLADDING TEMPERATURE FOR 11 KWIDSC TOTAL HEAT LOAD WITH IN 0 197L ......................... 19 A.1 Purpose..................................................................................... 20 A.2 Assumptions/Conservatisms .............................................................. 20 A.3 Design Input - 11.0 kW .................................................................... 20 A.4 Methodology................................................................................ 23 A.5 Finite Element Models ..................................................................... 23 A.6 References ................................................................................. 23 A.7 Computations............................................................................... 23 A.8 Results and Summary ................................. ~......................... i.........23

A TRANSNUCLEAR Calculation Calculation No.: 1121-0401 Revision No.: I AN AREVA COMPANY Page: 4 of 25 LIST OF TABLES Page Table 3-1 Ambient Conditions Considered in 0S197L Thermal Analyses.................... 7 Table 7-1 Summary of ANSYS runs - 11.0 kW and 18.4 kW................................ 13 Table 8-1 DSC Shell and 0S197L Cask Component Maximum Temperatures, ANSYS Results (18.4 kW/DSC) .................................................... 16 Table 8-2 DSC Shell and Fuel Cladding Maximum Temperatures for 0S197L Cask ANSYS Results (18.4 kW/DSC) .................................................... 17 Appendix Table A-I Effective Fuel Thermal Conductivities (CE 14x14-FC) in Helium .... 19 Appendix Table A-2 DSC Shell Temperatures, Average Outer Neutron Shield Panel Temperatures and Maximum Fuel Cladding Temperatures (11 kW/DSC)............................................................. 25 LIST OF FIGURES Page Figure 3-1 Fuel Loading Configuration (18.4 kW/DSC) ......................................... 5 Figure 5-1 081 97L (75 ton) Transfer Cask ANSYS Model..................................... 7 Figure 5-2 Details of OS 197L (75 ton) Transfer Cask ANSYS Model ......................... 8 Figure 8-1 Temperature Plot for 18.4 kW DSC in 051 97L, TaMb=100 0OF, insolation......... 13 Figure 8-2 Temperature Plot for 18.4 kW DSC in 0S197L, Tamb=1 170F, No Solar.......... 14 Appendix Figure A-I Fuel Loading Configuration (11 kW/DSC) ............................ 20 Appendix Figure A-2 Temperature Plot for 11 kW/DSC in OS1I97L, Tamb= 117 0 F, No Solar................................................................. 22 Appendix Figure A-3 Temperature Plot for 11 kW/DSC in OS1I97L, TamblO10 0F, with insolation ........................................................... 22 Appendix Figure A-4 Temperature Plot for Transfer of 11 kW/DSC within 08 197L for Off-Normal Conditions (1170F, No Solar), No Skid Shielding....23 Appendix Figure A-5 Temperature Plot for Transfer of 11 kW/DSC within OS 197L for Normal Conditions (100 0F, Insolation), No Skid Shielding......24

A TRANSNLJCLEAR ICalculationCalculation No.: 1121-0401 Revision No.: 1 AN ARE VA COMPANY Page: 5 of 25 1.0 PURPOSE The purpose of the calculation is determine 32PT DSC basket components and fuel cladding temperatures within the 0S1 97L (75 ton) cask with 18.4 kW/DSC and 11.0 kW/DSC total heat load for off-normal transfer condition. This isthe controlling case (lowest margin to fuel cladding temperature limit) during fuel load and transfer operation. The body of the calculation addresses the 16.4 kW heat load case and Appendix A addresses the

11. 0 kW condition.

2.0 ASSUMPTIONS/CONSERVATISMS The assumptions and conservatism described in NUHOMS0 32PT DSC thermal evaluation

[11 are applied in this calculation.

3.0 DESIGN INPUT - 18.4 KW The material properties listed in [1] are used in the analysis.

1) The fuel assembly used in [11 is used as the limiting assembly type inthis calculation based on the determination of limiting fuel effective conductivity among the fuel assemblies that are considered to be stored in 32PT DSC. Total heat load is 18.4 kW/DSC. The heat zone configuration is shown in Figure 3-1.

- I. - .1-i -

0.50 0.50 0.50 0.50 0.50 0.70* 0.70 0.70 0.70* 0.50 0.50 0.710. 0.70- 0.70 0.70 0.50 0.50 0.70. 0.70 0.70, 0.70 0.50 0.50 0.70* 0.70 0.70, 0.70* 0.150 0.50050.50 0.50 0.50~

Figure 3-1 Fuel Loading Configuration (18.4 kWIDSC)

  • This Is a very conservative assumption for the fuel assemblies (CE 14x14) to be loaded at OPPID In the 32PT DSC. Based on Reference

[1], CE 14x14 fuel assembly has higher effective fuel conductivities compared to design basis fuel assembly used In [1]. Moreover, the use of 0.7 I(W/FA for fuel assemblies In all basket center locations Is also very conservative for OPPD fuel loading. It is expected that fuel assemblies to be loaded at OPPD site will have significantly lower decay heat than 0.7 kW.

A TRANSNUCLEAR Calculation JCalculationNo.: 1121-0401 Revision No.: 1 AN AREVA CommAyj Page: 6of 25

2) Summary of ambient conditions considered in the analysis is shown in Table 3-1 below.

Table 3-1 Ambient Conditions Considered in 0S1971 Thermal Analyses Ambient Average Insolation Rate during Operating Conditions Temperature, 12 (24) Hour Period, OF Btulhr-ft2 Off-Normal Transfer 117* 0 Normal Transfer 100 123 1 0F shall be used as the average ambient air temperature for the steady state

~07 maximum off-normal condition [1].

4.0 METHODOLOGY The methodology used for thermal analysis is the same as described in [3]. The DSC shell temperature profile is calculated using a two dimensional thermal model of the OS1 97L cask and DSC shell, and uses the ANSYS [2] computer pro gram. These DSC shell temperatures are than used as a constant temperature boundary condition in an ANSYS model of the 32PT DSC and basket to calculate the fuel cladding temperature [1]. These fuel cladding temperatures are then used to calculate the effect of the transfer cask skid shielding as described in Section 5.3.

A TRANSNUCLEAR Calculation Calculation No.: 1121-0401 Revision No.: I AN ARE VA COMPANY Page: 7 of 25 5.0 FINITE ELEMENT MODELS 5.1 2D 0S197L Cask Thermal Model The DSC shell within the 0S197L cask is analyzed for the operating conditions listed in Table 3-1 for 18.4 kW/DSC heat load.

The ANSYS models of the 0S197L (75 ton) transfer cask including the DSC shell represent a two-dimensional slice of the OS 197L cask at the axial centerline as shown in Figure 5-1 through Figure 5-2.

AN~

05197L TC =~del 0S97L5-(75 ton) Transfer Cask ANSYS Model Figure 5-1 FigureO

A Calculation Calculation No.:

Revision No.: 1 1121-0401 TRANSNUCLEAR AN AREVACOMPANY Page: 8 of 25 Figure 5-2 below shows details of the OS 197L transfer cask ANSYS model.

Figure 5-2 Details of 0S197L (75 ton) Transfer Cask ANSYS Model The material properties and cask dimensions are taken from [3]. Only the total heat load per DSC is changed to 18.4 kW from 24 kW The method of the heat flux calculation is consistent with the OS 197L analysis methodology

[3]. Note that any heat removed by the ends of DSC is conservatively neglected in calcula-tion of heat flux. The heat flux is calculated based on the 32PT DSC shell length [1] as:

Btu/

18.4W.34112.3 hnr qW -0.0277 *ti minmn-n h0-(r66n12)

A TRANSNUCLEAR Calculation Calculation No.: 1121-0401 Revision No.: 1 AN ARE VA COMPANY Page: 9 of 25 The radiation is modeled by overlaying surface elements and using the /AUXI2 processor to compute view factors. Radiation to the environment is modeled with SURF1 51 elements in ANSYS. Radiation between the OSO shell and cask structural shell, between the cask structural shell and the cask inner neutron shield panel (or steel shielding) is also modeled using the /AUXI 2 processor inANSYS [3].

The convection to the ambient is conservatively based on average film temperature for convection coefficient evaluation in the ANSYS model. The convection coefficients are calculated based on correlation of turbulent natural convection for horizontal cylinder [4]:

h = 0.1 8(AT )1I3 Bu = 2.083e - 5(AT )13 Btu 2 fr1'<GL<1" hr - -ft" O min -inch OF fri 9 <GL<02 The heat is applied to the model as a heat flux on the inner surface of the DSC using SURFIS51 elements in ANSYS.

5.2 3D 32PT DSC Thermal Model The DSC outer shell temperatures are based on a 2D DSC/cask model, which assumes no heat transfer inthe axial direction. This 2D 0S1 97L model produces conservative (higher)

DSC shell temperatures, which are used as input to the 3D DSC thermal model, which calculated the fuel clad temperatures. Both the normal (with insolation) and off-normal 0S197L transfer conditions with 18.4 kW/DSC are calculated.

The same basket component and fuel properties from [1 ] are used. Heat generations are calculated based on the dimensions of the fuel and basket. The heat is assumed to be distributed evenly through the 8.7" square nominal fuel cell opening. Axial variations are accounted for in ANSYS by using the peaking factors similar to [1]. The base heat generations with the corresponding peaking factors are applied according to the loading patterns given in Figure 3-1:

For 0.7 kW heat load:

0.7kW - 3414 Bthr lhr

)2 kW 60 min 3.711le -3 Btu (8.7!nf 141 .8in min. in For 0.5 kW heat load:

Stil 0.5kW -3414 - hr. lhrBt kW 6 0Omin= 2 6. 5e - 3Bt (8.7mn . 141 .Bin min. in3

A TRAINSNUCLEAR I ICalculation Calculation Revision No.: 1121-0401 No.: I AN AREVA COMPANY Page: 10 of 25 5.3 Methodology to Determine Maximum Fuel Cladding Temperatures in0S197L Transfer Cask with Skid Shielding An additional skid shielding prevents insolation on the cask surface but effects the convective flow at the outer cask surface. The 3D 051 97L caskIDSC shell CFD model was developed to analyze this effect on the cask component temperatures [5].

The effect of the skid shielding on the maximum fuel cladding temperature was evaluated by the following steps:

1) The average temperature of the outer surface of neutron shield outer panel Tout Ns Paver was calculated by CFD run [5] and used to obtain the average DSC shell temperature Tsh av by extrapolation of the results Tsh av = f(Tout NS paver) available from the 2D ANSYS runs for hot off-normal (1170F ambient, no insolation) and hot normal (100 0OF ambient, insolation) cases calculated in Section 5.1.
2) The average DSC shell temperature TOhv , calculated above, was then used to obtain the maximum fuel cladding temperature Truel max by extrapolation of the results Tfuei max=

f(Tsh av) available from the DSC within 081 97L-1 runs in Section 5.2 for hot off-normal (1170F ambient, no insolation) and hot normal (100 0OF ambient, insolation) for the 08 197L cask with skid shielding (See Section 5.2 above for Tfuel max calculation).

A TRANSNUCLEAR Calculation Calculation No.:

Revision No.:

1121-0401 1

AN AREVA COMPANY Page: 11 of 25

6.0 REFERENCES

1. Calculation, NUHOMSO 32PT DSC Thermal Evaluation for IOCFR, Part 72 Storage Conditions, Transnuclear, Inc. Calculation No. NUH 32PT.0403, Rev 3.
2. On-Line User's Manual for ANSYS, Revision 8.1.
3. Calculation, Thermal Analysis of 0S197L and 0S197L 100 Transfer Cask, Transnuclear, Inc. Calculation No. NUHO6L-0400, Rev 2.
4. Ozisik, N. M., Basic Heat Transfer, McGraw Hill Book Company, 1977.
5. Calculation, Calculation of 0S197L Cask Shell Temperature with 18.4 kW and 11. 0 kWHeat Load, Transnuclear, Inc. Calculation No. 1121.0400. Rev. 1.
6. Calculation, Minimum Fuel Effective Conductivity for 32PT Design, Transnuclear, Inc. Calculation No. 60220-14, Rev 0.

A TRANSNUCLEAR Calculation Calculation No.:

Revision No.:

1121-0401 I

AN AREVA COMPANY Page: 12 of 25 7.0 COMPUTATIONS The ANSYS 8.1 [2] model was runs on Xeon 3.2 GHz platform. The runs are summarized in Table 7-1 below. The input, output ANSYS database, and result files are located on the CD, which accompany this calculation.

Table 7-1 Summary of ANSYS runs - 11.0 kW and 18.4 kW Operating Conditions TaF j Insolation Run ID Datie 2D OS197L Cask ANSYS Thermal Models, 18.4 kW Off-normal, transfer OS I97L caskl32 PT DSC, w/o skid shielding Iqax 117 1o 05/no0 Normal, transfer OS1I97L cask/32PT 10 yesax 16:08:42 DSC, w/o skid shieldingJ10ye 3D DSC ANSYS Thermal Model, 18.4 kW Off-normal, transfer OS 197L caskl32 PT DSC, w/o skid shielding Normal, transfer OS 197L cask/32PT j 117 11I no e

o j T32sOS197L 18kw 05/31/06 18:21 :23 T32s...OS1 97L 05/31/06 DSC, Wlo skid shielding 11 ye l8kwn 19:32:02 2D 0S197L Cask ANSYSThermal Models, 11.0 kW Off-normal, transfer OS197L cask/32 PT DSC, w/o skid shielding Normal, transfer OS1I97L caskI32PT I 117 10 no yesx1k 1o 06/02/06 20:52:37 DSC, w/o skid shielding10ye 3D DSC ANSYS Thermal Model, 11.0 kW ___

Off-normal, transfer OS I97L caskl,32 117 no T32sOPPD_ 06/02/06 PT DSC, w/o skid shielding no 1kw -22:33:01 Normal, transfer OS I 7L cask./32PT 117 yes T32sOPPD_ 06/02/06 DSC, w/o skid shielding ___ _____ lkwri 23:22:38

A TRANSNUCL IEAR Calculation aclto o.11100 Revision No.: 1 AN AREVA COMPANY Pg:1 f2 8.0 RESULTS AND

SUMMARY

8.1 Temperature of 0S197L Components, and 18.4 kW DSC Shell The temperature plots for the DSC shell and the 0S197L transfer cask for normal operating conditions (with insolation) and off-normal (Without insolation) are shown in Figure 8-1 and Figure 8-2, respectively.

1 ANSYS 8.1 14AY,31 2006 NODAL SOLUTION TEP-3 BUDh =1 ElFACET-1 AVAIS=Mtt SM =185.286 WUC=401.308 185.286 233.291

~ 257.293 281.295 r 305.298 329.3 353.303 377.305 401.308 05197-1., NS: water/ax stifo 100F axab, +/-nso., ac axe Flgure 8-1 Temperature Plot for 18.4 kW DSC In 0S197L, TamblOO00 F, insolation

A TRANSNUCLEAR Calculation TCalculationNo.:

Revision No.:

1121-0401 1

AN AREVA COMPAY ______ ______J Page: 14 of 25 ANSYS 9. 1 MAY 31 2006 20:2.0 NODAL SOLUTION STEP=4 SUB =1 PowerGraphlcs 5MB =189.997 SN! =397.091 255.69.5 321.393 ED343.293 365.192 387.091 05197-I., IS: water/ax st~f, 117r amb, no inso, Lo-axc Figure 8-2 Temperature Plot for 18.4 kW DSC In 051971, Tamb=117 0F, No Solar

A Calculation Calculation No.: 1121-0401 Revision No.: 1 TRANSNUCLEAR AN AREVA COMPANY Page: 15 of 25 Summary of the 18.4 kW DSC shell, and maximum 0S197L transfer cask component temperatures are shown in Table 8-1 below.

Table 8-1 DSC Shell and 0S1971 Cask Component Maximum Temperatures, ANSYS Results (18.4 kWIDSC)

Operating Conditions Tob, Ttp T.,d., Tbot, Tout NS po Tsh avo I

_____________OF__ OF___ OF OF OF__OF Off-normal, transfer 08197L w/o 117 387 375(1) 329 215 362 skid shielding______ ______

Normal, transfer OS1I97L w/o 100, 41 38' 2 2 6 skid shielding insolation 41 381 2 2 6 Off-normal, transfer OS 197L 117 - - - 259 388(2) with skid shielding (5]_____ ____ ____ ___ ____ ____

(1) Conservative value isapplied in DSO thermal model.

(2) Extrapolated value based on 2D cask ANSYS runs for off-normal and normal transfer OS197L cases where Ttp Talde, Tbo - DSC shell top, side and bottom maximum temperature, respectively, Tsh av - DSC shell inner surface average temperature, Tout ISS 1) - cask outer NS panel average temperature.

8.2 Evaluation of Maximum Fuel Cladding Tem~erature during Transfer in 0S197L The DSC shell top, side, and bottom temperatures are used inthis calculation. An average DSC shell temperature Tsh av was calculated as the average nodal temperature at the inner DSC shell diameter. This average temperature is then used to calculate maximum fuel cladding temperature for 18.4 kW/DSC transferred within the 0S197L. The results are shown inTable 8-2 below.

A Calculation Calculation No.:

Revision No.:

1121-0401 1

TRANSNUCLEAR AN AREVA COMPANY Page: 16 of25 Table 8-2 DSC Shell and Fuel Cladding Maximum Temperatures for 0S197L Cask ANSYS Results (18.4 kWIDSC)

Operating Conditions Tambf Tt0ps Tolde, TbaTout, NS pg Tsh avg Tfel max Tf.1 1imit F F OF OF OF F OF O Off-normal, transfer OS197L 117 387 375" 329 215 362 678 752 w/o skid shielding ________

Normal, transfer 0S1 97L, 10 w/o skid shielding insolatio 401 388(1) 325 225 368 686 752 1 n _ _ _ I_ _ _ I_ _ _ _ I___ _ _ _ I__

Off-normal, transfer 0S197L 117 - - - 259 388(l) 713 (2) 752 with skid shielding [5] ____________________

(1) See Table 8-1.

(2) Extrapolated value.

6.3 Effect of Skid Shieldingq on Thermal Analysis Results As seen from Table 8-2, the maximum fuel cladding temperature for 18.4 kW /32PT DSC within 0S197L are below allowable limits for normal and off-normal transfer conditions without skid shielding and for off-normal transfer conditions with skid shielding. The normal condition with skid shielding is bounded by the off-normal as the skid shielding eliminates the insolation and the ambient temperature is higher.

A TRANSNUCLEAR Calculation Calculation No.: 1121-0401 Revision No.: 1 AN AREVA COMPANY JPage: 17 of 25 APPENDIX A EVALUATION OF MAXIMUM FUEL CLADDING TEMPERATURE FOR 11 KWIDSC TOTAL HEAT LOAD WITHIN 0S197L

A Calculation Calculation No.: 1121-0401 Revision No.: 1 TRANSNUCLEAR AN ARE VA COMPANY Page: 18 of 25 A.1I Purpose The purpose of this Appendix A is to determine 32PT DSC basket components and fuel cladding temperatures within the OS 197L (75 ton) cask with 11. 0 kW/DSC total heat load for off-normal transfer condition.

A.2 AssumptionslConservatisms There is no change to the assumptions or conservatisms, and those of [1] are applied in this calculation.

A.3 Design Input- 11.0kW This Appendix A provides a thermal evaluation of the maximum fuel cladding temperature for an 11. 0 kW/DSC within OS 197L.

The thermal evaluation is similar to the evaluation described previously in Sections 2.0 through 5.0 for the 18.4 kW/DSC total heat load.

Three different design inputs are used inthis Appendix A:

A.3.I The heat flux applied on DSC shell inner surface for 11 kW/DSC is:

1llkW .3412.3 Bthr kW=0.0166 Btu hr A.3.2 The effective fuel thermal conductivity of the fuel assembly CE 14x14-FC is listed in Appendix Table A-I [61, and was used in the model.

A TRANSNUCLEAR Calculation Calculation No.: 1121-0401 Revision No.: 1 AN ARE VA COMPANY Page: 19 of 25 Appendix Table A-I Effective Fuel Thermal Conductivities (CE 14x14-FC) in Helium T Transverse Effective T Axial Effective (OF 0 Conductivity TOF Conductivity

( F) (Btulmin-ln-0F (F) (Btulmln-In-OF) 136 3.452E-04 200 1.016E-03 231 3.927E-04 300 1.072E-03 326 4.675E-04 400 1.128E-03 422 5.579E-04 500 1.174E-03 519 6.634E-04 600 1.221 E-03 616 7.842E-04 800 1.323E-03 713 9.193E-04 811 1.072E-03 A.3.3 The fuel zoning configuration was redefined to reduce peak fuel clad temperatures and to incorporate the lower 11.0 kW/DSC heat loading. The configuration isshown inAppendix Figure A-I.

A.3.4 The base heat generation with the corresponding axial peaking factor is applied according to the loading pattern given in the fuel loading configuration for I11 kW/DSC, as shown inAppendix Figure A-I.

A Calculation Calculation No.: 1121-0401 Revision No.: 1 TRANSNUCLEAR AN AREVA COMPANY Page: 20 of 25 Heat Zone 1 2 J 3 4 5

  1. of IFuel IAssemblies. 4 8 .8 4 Max Heat Load / Assembly OkW)ý 0.16 0.35 0.40 0.50 0.50 Max Heat Load / Zone (kWN) 0.64 .2.80 3.20 4.00 2.00 Max Heat Load] DSC (kWV) -11.0 Appendix Figure A-I Fuel Loading Configuration (11 kWIDSC)

'This is a bounding fuel toad for the fuel assemblies (CE 14x14) to be loaded at OPPID in the 32PT DSC.

Conservatively, the total heat generation used Inthe 3D DSC thermal model based on the above fuel loading configuration is 12.64 kW/ DSC. The total heat load to be loaded at OPPD site at the Phase I campaign will be less than 11 kW per DSC.

A TRANSNUCLEAR Calculation CluainN. 1100 Revision No.: I AN ARE VA COMPANY Pg:2 f2 A.4 Methodolo-av There is no change to the methodology used to calculate the peak fuel clad temperatures, described previously in Section 4.0.

A.5 Finite Element Models The same models, as were used previously for the 18.4 kW/DSC calculation, were used in this 11.0 kW/DSC calculation. The differences were the reduction in heat flux detailed above and the reduction in base fuel assembly heat generations within the basket, which correspond to the reduced 0.40, 0.35, and 0.16 kW/Assembly Zones (Zones I through 3).

A.6 References There is no change to the references.

A.7 Computations All computer runs for the 11. 0 kW conditions are listed in Section 7.0.

A.8 Results and Summar The ANSYS runs for 11 kW/DSC heat load are listed in Table 7-1.

The temperature plots for the DSC shell and 0S197L transfer cask for normal operating conditions (with insolation) and off-normal (without insolation) for 11 kW/DSC heat load are shown in Appendix Figure A-2 and Appendix Figure A-3, respectively.

TRA SNJCLARCalculation Revision No.: 1 AN AREVA COMPANY Pg:2 f2 AZSYS 8. 1 TUN 2 2006 20:56:07 NODAL. SOLUTION sTRP=4 SUB -1 TWN (AVG)

RSYS=O R1ACB1T 1 AVRES=Nmt 5W =160.217 sm 301.17-9 20:55:35 U NODAL222.U8IO 2138 2 254PC1V9 Tamb=1 170, No Sola

-UK210807 3214P55VO itf, 3: uaer/ax 051971. 107 ~, lnoj.,La m 11k A-3 igurTempratue Appedix Plt fo 11 W/DSC in 0s19L 00 F, wth inslatio Tsmbl

A Calculation No.: 1121-0401 TRANSNUCLEAR Calculation Revision No.: 1 AN ARVA CoPANYPage: 23 of 25 The summary of the DSC shell and OS 197L transfer cask component temperatures is shown inAppendix Table A-2 below.

Appendix Figure A-4 and Appendix Figure A-5 show DSC component and fuel temperature plots for off-normal and normal transfer conditions for the 11 kW/DSC heat load.

1 ANSYS 8.1 JUN 4 2006 15:12:02 NODAL SOLUTIC STEP 1 SUB =1 TIME=1 2T"N (AVG aAVRES=

PowerGraphIcs EFACET1 SM =179

ýSMX =436.683 179 264.894 293.526 408.052 436:683, DSC In T,11717 aub, No Solar, 116w, C!14x14C/Re, Tab 05197L Appendix Figure A-4 Temperature Plot for Transfer of 11 kWIDSC within 0S1 97L for Off-Normal Conditions (117 0F, No Solar), No Skid Shielding

A TRANSNUCLEAR AN AREVA COMPANY Calculation aclto o.11100 Revision No.:

Pg:2 I

f2 UUN 4 2006 15:05: 14 NODAL SOLUTION STEl4=1 TEM4P (AVG)

Pow.erGraphics EFACET=1 3MX =449.388 236.986 297.672 328.015 449.3B9 DBC in TC, 100r an~b, Solar,llkw, CE14xl4rC/Ke, Tsh 0S197L Appendix Figure A-5 Temperature Plot for Transfer of I11 kWJDSC within 051 971 for Normal Conditions (100OF, Insolation), No Skid Shielding Effect of Skid Shielding on Thermal Analysis Results Appendix Table A-2 shows the DSC shell temperatures, average temperatures of the 0S 1971 outer neutron shield panel, and the maximum fuel cladding temperatures for normal and off-normal transfer conditions with the 11.0 kW/DSC heat load.

Appendix Table A-2 also includes the average DSC shell and maximum fuel cladding temperatures for off-normal transfer within the OS1I97L with skid shielding.

A Calculation Calculation No.: 1121-0401 Revision No.:

TRANSNUCLEAR 1 AN AREVA COMPANY Page: 25 of 25 Appendix Table A-2 DSC Shell Temperatures, Average Outer Neutron Shield Panel Temperatures and Maximum Fuel Cladding Temperatures (11I kWIDSC)

Operating Conditions Tamb, Ttop, TId., TbOt, Tou NS ps Tsh awT~l maxTu~ limit Off-normal, transfer OS1I97L 117 301 291(0) 250 176 279 437 752 w/o skid shielding________

Normal, transfer 0S197L, 100, w/o skid shielding insolatio 321 306(1) 247 189 289 449 752

__ __ _ __ __ _ n _ _ I___

I___ I___ I__

Off-Normal, transfer 0S197L 117 - - - 214(4) 308(2) 472 (3) 752 with skid shielding ____ ______ _______ ______

(1) Conservative value isapplied in DSC thermal model.

(2) Extrapolated value based on 2D cask ANSYS runs for off-normal and normal transfer 0S197L cases (3) Extrapolated value based on 3D DSC ANSYS runs for off-normal and normal transfer 0S197L cases (4) Calculated using CFD model [5)

As seen from Appendix Table A-2, the maximum fuel cladding temperature for 11 kW 132PT DSC within OS1 97L are below allowable limits for normal and off-normal transfer conditions without skid shielding, and for off-normnal conditions with skid shielding. The normal condition with skid shielding is bounded by the off-normal as the skid shielding eliminates the insolation and the ambient temperature is higher.

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