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{{#Wiki_filter:Calculation No. L-003388, Rev. 0    Attachment E (Page E1 of E246) Attachment E  MCNP Assessment of "Hiding" Containers Behind Containers Adjacent to IRSF Outer Walls  This attachment contains 1 MicroShield and 6 MCNP runs as outlined here and in the following page. These analyses are performed to assess the contact dose rate limits for containers in the immediate vicinity of outside walls. These analyses also assess dose contributions from the row behind that nearest to the wall. Source Strength Assessment Page E2 is a simple MicroShield container model that shows a correlation between source strength in photons/second and container contact dose rate for a nominal source specific gravity of 0.9. No container wall is modeled, but since the source strength is controlled on a contact dose basis in any case, the particulars of density and container materials is considered insignificant. The results are that a source strength of 1.024e13 photons per second yield a 100 R/hr contact dose rate (modeled at 1 inch from the wall). In the MCNP models the same source only geometry with a 5 foot diameter, 6 foot height, and 0.9 sp.gr. is used. The MCNP models are run on a 1 photon/sec basis so the results must be scaled up with the actual source terms. MCNP Cases The MCNP run names, and purposes are as follows: File Name Purpose TidD.o Models doses through an IRSF 30" thick concrete wall from 13 containers, 7 along the wall and 6 behind, centered in the gap between the front row containers. Contact dose rate limits are selected based on a full array of containers, stacked two high. TidDB.o Same as above but source is only in the back six containers. This is to allow the contribution of the back containers to be separated. TidA1.o Models dose from a single stack of containers, to help illustrate that dose rates outside of the building will build slowly. TidA2.o Models dose from a single container, again to help illustrate that dose rates outside of the building will build slowly. TidA3.o Provides a basis for estimating axial peaking for stacked containers. TidA4.o Provides a basis for estimating axial peaking for a single container or single layer. TidA5.o Provides a basis for estimating the effect of a shield bell  The figures that follow this page show the MCNP Vised geometry screen images for these cases. Container separation and distance from outside walls are in accordance with plant procedures and crane indexing. The 13 container model is considered sufficient for this analyses, and containers behind these two rows are assumed to make a negligible contribution to doses from radiation through an outside wall, as long as intervening containers are present. Dose rates are calculated using a surface corossing detector on the outside wall surface. This surface is segmented vertically to calculate dose rate directly in front and between containers. For axial peaking assessments, this surface is segmented horizontally as shown and discussed. Shield density reflected as-poured data with rebar blending.   
Calculation No. L-003388, Rev. 0    Attachment E (Page E3 of E246) MCNP Vised Geometry with source particle plotting on left, TidD.o with source in all containers  MCNP Vised Geometry with source particle plotting, TidDB.o with source in back containers only Calculation No. L-003388, Rev. 0    Attachment E (Page E4 of E246) MCNP Vised Geometry with source particle plotting, single stack, TidA1.o and TidA3.o  MCNP Vised Geometry with source particle plotting, single container, TidA2.o and TidA4.o Calculation No. L-003388, Rev. 0    Attachment E (Page E5 of E246)
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Attachment F:  IRSF - Credit for Decay in Storage - Nominal Assessment  Discussion of Decay Credit  High Dose Rate HICs placed in the IRSF can immediately challenge the dose limits for through wall shielding, and limits have been established based on three stacks of two containers. Decay credit may be beneficial to a limited extent but is not evaluated specifically herein. However, dose rates from upwardly exposed containers such as roof scatter into the truckbay and skyshine to outside of the IRSF will tend to increase slowly as the IRSF accumulates stored radwaste. At the nominal postulated 4 container per year loading rate, accumulation will be slow, and decay potentially significant. The spreadsheet on the following page tests this effect with a container added quarterly. At that rate, for the first layer, when the last position is filled, the first container will have been aged for 31.25 years. Co-60 tends to dominate package doses, so this evaluation is on an all Co-60 basis. As shown, if all containers were prepared with the same initial contact dose rate, the average dose rate once the first layer was filled would be less than 25% of the initial value. For this reason, it may be procedurally beneficial to track loaded container characteristics in terms of initial dose rates, loading date, placement position, etc. in assessing the approach to loading limits for truckbay or external dose control. Discussion of all Co-60 Assumption . A single sample Quad Cities RWCU waste package characterization report was supplied and evaluated herein. The supplied isotopic mix was evaluated using MicroShield for the initial loading condition, and then for the oldest package, when the first layer is 1/3, 2/3, and 3/3 full. Initially the all Co-60 approximation is slightly conservative because of the decay of shorter lived isotopes. Even at the final package loading, the approximation is only slightly non-conservative in its prediction for packages that are well decayed in any case. On this basis, an all Co-60 basis may be sufficient for tracking decay effects, although other contributors could also be included.
123456789101112131415161718192021222324252627282930313233343536373839ABCDEFGHIJKLMNOPQRSTUSample Package Characteristic Report Contact Dose Contributions100Container Initial Contact Dose Rate97.22%Co-604Containers per year2.36%Mn-545.271Co-60 Half-life (reasonable approximation for decay credit)0.37%Cs-137/Ba-137m0.967659Decay factor per nominal container gap period0.06%OtherFrom MicroShield Tests, included on following pages1234567891234567891100.063.139.825.115.910.06.34.02.510.003.507.0010.5014.0017.5021.0024.5028.00296.861.138.524.315.49.76.13.92.420.253.757.2510.7514.2517.7521.2524.7528.25393.659.137.323.514.99.45.93.72.430.504.007.5011.0014.5018.0021.5025.0028.50490.657.236.122.814.49.15.73.62.340.754.257.7511.2514.7518.2521.7525.2528.75587.755.334.922.013.98.85.53.52.251.004.508.0011.5015.0018.5022.0025.5029.00684.853.533.821.313.58.55.43.42.161.254.758.2511.7515.2518.7522.2525.7529.25782.151.832.720.613.08.25.23.32.171.505.008.5012.0015.5019.0022.5026.0029.50879.450.131.620.012.68.05.03.22.081.755.258.7512.2515.7519.2522.7526.2529.75976.948.530.619.312.27.74.93.11.992.005.509.0012.5016.0019.5023.0026.5030.001074.446.929.618.711.87.44.73.01.9102.255.759.2512.7516.2519.7523.2526.7530.251172.045.428.718.111.47.24.52.91.8112.506.009.5013.0016.5020.0023.5027.0030.501269.744.027.717.511.17.04.42.81.8122.756.259.7513.2516.7520.2523.7527.2530.751367.442.526.816.910.76.74.32.71.7133.006.5010.0013.5017.0020.5024.0027.5031.001465.241.226.016.410.36.54.12.61.6143.256.7510.2513.7517.2520.7524.2527.7531.25Average24.2Co-60 Only Decay MicroShield Contact Dose Conservatism Test2.422E+05Dose Rate with Sample Package Isotopics (R/hr)6.188E+04Dose Rate with Sample Package Isotopics (R/hr) & 10.25 years of decay6.292E+04Dose Rate after 10.25 years of decay on simple Co-60 decay basis1.593E+04Dose Rate with Sample Package Isotopics (R/hr) & 20.75 years of decay1.582E+04Dose Rate after 20.75 years of decay on simple Co-60 decay basis4.298E+03Dose Rate with Sample Package Isotopics (R/hr) & 31.25 years of decay3.976E+03Dose Rate after 31.25 years of decay on simple Co-60 decay basis010.2520.7531.25Decay Time (years)1101.7%99.3%92.5%Approximation / Actual RatioContact Dose Rate (R/hr) after nominal decayContainer Ages (yrs) at nominal fill rateIRSF Nominal Decay in Storage Effects AssessmentTherefore, for the sample isotopic mix a simple Co-60 based decay assumption would be reasonable. Other mixes might require tracking of additional isotopes.Co-60 Approximation Impact0.920.940.960.9811.021.0405101520253035Decay Time (yrs)Dose Ratio (approx.l/actual)
LaSalle Nearest Offsite Residence Distance and Direction from IRSF Waste Center 123456789101112131415161718192021222324252627282930313233343536373839404142434445ABCDEFGHIJKLSimplifed Shield Density Assessment, as Used in Calculation AnalysesAreal(b)SpecificThicknessDensityGravity(inches)(lb/ft2)(gm/cc)Lower Wall30369.22.366Used for all walls, since it is lowest value and avoids a geometry refinement of limited benefitUpper Wall151872.397Roof (a)15181.72.329Roof, including blended girder mass but max rather than average thickness (conservative)(a)  Roof thickness actually varies between 12 and 15 inches thick, every three inches. Average is 13.5 inches(b)  Areal Densities from Page I-16.Detailed Density Treatments, Margin Reviews, and Girder Treatment Assessmentsp. gr.gm/cc143.4lb/cu.ft. LaSalle Concrete Mix Design2.29712Rebar spacing, in all cases (inches)109Rebar # for 30 inch wall97Rebar # for 15 inch wall67Rebar # for 12-15 inch roof490lb/cu.ft. for Rebar material0.01704420.013806Rebar volume/sq.ft. for 30 inch wall0.01380580.008352Rebar volume/sq.ft. for 15 inch wall0.00613590.008352Rebar volume/sq.ft. for 12-15 inch roof358.5For 30 inch wall179.25For 15 inch wall161.325For 12-15 inch roof1ReferenceValuegm/ccas-used369.2For 30 inch wall369.2perfect match2.3662.365conservative186.9For 15 inch wall187very close match2.3962.365conservative166.3For 12-15 inch roofnot included2.3692.328conservativeGirders118lb/lineal foot8.6666667Girder spacing (ft)7' 8" possibly used rather than 8' 8"mismatch13.6Girder Adjustment lb/sq.ft.Ref. valuegm/ccas-used180.0For 12-15 inch roof, with blended girders181.7mismatch2.5632.328conservativePer ANSI/ANS-6.4-1997, "For gamma ray sources, the presence of rebar may be considered and, if considered, a simple homogenization of the rebar and concrete is sufficient to account for its effect." Attachment IConcrete Shield Densities, Derived from Following ReportStraight Concrete Areal Density lb/sq.ft.Rebar Adjusted Concrete Area Density (lb/sq.ft.)Girders were blended with roof, but with an apparent too tight spacing in following report. Nevertheless, the as-used density, effectively, does not reflect girder mass. Still recoverable conservatisms include miniscule density increases on 30inch wall density, and minor density increases on thin wall and roof densities. It is recommended that any girder effects be addressed not by blending, but by explicit geometry modeling.Rebar diameter treated as 1/8th of Rebar #.}}

Revision as of 20:12, 14 August 2018

LaSalle County Station Analysis L-003388, Revision 0, LaSalle Irsf Shielding Calculations for Class B & C Waste, Attachment E (Page E1 of E246) Through Attachment I (Page I-17 of I-17)
ML110390449
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Calculation No. L-003388, Rev. 0 Attachment E (Page E1 of E246) Attachment E MCNP Assessment of "Hiding" Containers Behind Containers Adjacent to IRSF Outer Walls This attachment contains 1 MicroShield and 6 MCNP runs as outlined here and in the following page. These analyses are performed to assess the contact dose rate limits for containers in the immediate vicinity of outside walls. These analyses also assess dose contributions from the row behind that nearest to the wall. Source Strength Assessment Page E2 is a simple MicroShield container model that shows a correlation between source strength in photons/second and container contact dose rate for a nominal source specific gravity of 0.9. No container wall is modeled, but since the source strength is controlled on a contact dose basis in any case, the particulars of density and container materials is considered insignificant. The results are that a source strength of 1.024e13 photons per second yield a 100 R/hr contact dose rate (modeled at 1 inch from the wall). In the MCNP models the same source only geometry with a 5 foot diameter, 6 foot height, and 0.9 sp.gr. is used. The MCNP models are run on a 1 photon/sec basis so the results must be scaled up with the actual source terms. MCNP Cases The MCNP run names, and purposes are as follows: File Name Purpose TidD.o Models doses through an IRSF 30" thick concrete wall from 13 containers, 7 along the wall and 6 behind, centered in the gap between the front row containers. Contact dose rate limits are selected based on a full array of containers, stacked two high. TidDB.o Same as above but source is only in the back six containers. This is to allow the contribution of the back containers to be separated. TidA1.o Models dose from a single stack of containers, to help illustrate that dose rates outside of the building will build slowly. TidA2.o Models dose from a single container, again to help illustrate that dose rates outside of the building will build slowly. TidA3.o Provides a basis for estimating axial peaking for stacked containers. TidA4.o Provides a basis for estimating axial peaking for a single container or single layer. TidA5.o Provides a basis for estimating the effect of a shield bell The figures that follow this page show the MCNP Vised geometry screen images for these cases. Container separation and distance from outside walls are in accordance with plant procedures and crane indexing. The 13 container model is considered sufficient for this analyses, and containers behind these two rows are assumed to make a negligible contribution to doses from radiation through an outside wall, as long as intervening containers are present. Dose rates are calculated using a surface corossing detector on the outside wall surface. This surface is segmented vertically to calculate dose rate directly in front and between containers. For axial peaking assessments, this surface is segmented horizontally as shown and discussed. Shield density reflected as-poured data with rebar blending.

Calculation No. L-003388, Rev. 0 Attachment E (Page E3 of E246) MCNP Vised Geometry with source particle plotting on left, TidD.o with source in all containers MCNP Vised Geometry with source particle plotting, TidDB.o with source in back containers only Calculation No. L-003388, Rev. 0 Attachment E (Page E4 of E246) MCNP Vised Geometry with source particle plotting, single stack, TidA1.o and TidA3.o MCNP Vised Geometry with source particle plotting, single container, TidA2.o and TidA4.o Calculation No. L-003388, Rev. 0 Attachment E (Page E5 of E246)

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Attachment F: IRSF - Credit for Decay in Storage - Nominal Assessment Discussion of Decay Credit High Dose Rate HICs placed in the IRSF can immediately challenge the dose limits for through wall shielding, and limits have been established based on three stacks of two containers. Decay credit may be beneficial to a limited extent but is not evaluated specifically herein. However, dose rates from upwardly exposed containers such as roof scatter into the truckbay and skyshine to outside of the IRSF will tend to increase slowly as the IRSF accumulates stored radwaste. At the nominal postulated 4 container per year loading rate, accumulation will be slow, and decay potentially significant. The spreadsheet on the following page tests this effect with a container added quarterly. At that rate, for the first layer, when the last position is filled, the first container will have been aged for 31.25 years. Co-60 tends to dominate package doses, so this evaluation is on an all Co-60 basis. As shown, if all containers were prepared with the same initial contact dose rate, the average dose rate once the first layer was filled would be less than 25% of the initial value. For this reason, it may be procedurally beneficial to track loaded container characteristics in terms of initial dose rates, loading date, placement position, etc. in assessing the approach to loading limits for truckbay or external dose control. Discussion of all Co-60 Assumption . A single sample Quad Cities RWCU waste package characterization report was supplied and evaluated herein. The supplied isotopic mix was evaluated using MicroShield for the initial loading condition, and then for the oldest package, when the first layer is 1/3, 2/3, and 3/3 full. Initially the all Co-60 approximation is slightly conservative because of the decay of shorter lived isotopes. Even at the final package loading, the approximation is only slightly non-conservative in its prediction for packages that are well decayed in any case. On this basis, an all Co-60 basis may be sufficient for tracking decay effects, although other contributors could also be included.

123456789101112131415161718192021222324252627282930313233343536373839ABCDEFGHIJKLMNOPQRSTUSample Package Characteristic Report Contact Dose Contributions100Container Initial Contact Dose Rate97.22%Co-604Containers per year2.36%Mn-545.271Co-60 Half-life (reasonable approximation for decay credit)0.37%Cs-137/Ba-137m0.967659Decay factor per nominal container gap period0.06%OtherFrom MicroShield Tests, included on following pages1234567891234567891100.063.139.825.115.910.06.34.02.510.003.507.0010.5014.0017.5021.0024.5028.00296.861.138.524.315.49.76.13.92.420.253.757.2510.7514.2517.7521.2524.7528.25393.659.137.323.514.99.45.93.72.430.504.007.5011.0014.5018.0021.5025.0028.50490.657.236.122.814.49.15.73.62.340.754.257.7511.2514.7518.2521.7525.2528.75587.755.334.922.013.98.85.53.52.251.004.508.0011.5015.0018.5022.0025.5029.00684.853.533.821.313.58.55.43.42.161.254.758.2511.7515.2518.7522.2525.7529.25782.151.832.720.613.08.25.23.32.171.505.008.5012.0015.5019.0022.5026.0029.50879.450.131.620.012.68.05.03.22.081.755.258.7512.2515.7519.2522.7526.2529.75976.948.530.619.312.27.74.93.11.992.005.509.0012.5016.0019.5023.0026.5030.001074.446.929.618.711.87.44.73.01.9102.255.759.2512.7516.2519.7523.2526.7530.251172.045.428.718.111.47.24.52.91.8112.506.009.5013.0016.5020.0023.5027.0030.501269.744.027.717.511.17.04.42.81.8122.756.259.7513.2516.7520.2523.7527.2530.751367.442.526.816.910.76.74.32.71.7133.006.5010.0013.5017.0020.5024.0027.5031.001465.241.226.016.410.36.54.12.61.6143.256.7510.2513.7517.2520.7524.2527.7531.25Average24.2Co-60 Only Decay MicroShield Contact Dose Conservatism Test2.422E+05Dose Rate with Sample Package Isotopics (R/hr)6.188E+04Dose Rate with Sample Package Isotopics (R/hr) & 10.25 years of decay6.292E+04Dose Rate after 10.25 years of decay on simple Co-60 decay basis1.593E+04Dose Rate with Sample Package Isotopics (R/hr) & 20.75 years of decay1.582E+04Dose Rate after 20.75 years of decay on simple Co-60 decay basis4.298E+03Dose Rate with Sample Package Isotopics (R/hr) & 31.25 years of decay3.976E+03Dose Rate after 31.25 years of decay on simple Co-60 decay basis010.2520.7531.25Decay Time (years)1101.7%99.3%92.5%Approximation / Actual RatioContact Dose Rate (R/hr) after nominal decayContainer Ages (yrs) at nominal fill rateIRSF Nominal Decay in Storage Effects AssessmentTherefore, for the sample isotopic mix a simple Co-60 based decay assumption would be reasonable. Other mixes might require tracking of additional isotopes.Co-60 Approximation Impact0.920.940.960.9811.021.0405101520253035Decay Time (yrs)Dose Ratio (approx.l/actual)

LaSalle Nearest Offsite Residence Distance and Direction from IRSF Waste Center 123456789101112131415161718192021222324252627282930313233343536373839404142434445ABCDEFGHIJKLSimplifed Shield Density Assessment, as Used in Calculation AnalysesAreal(b)SpecificThicknessDensityGravity(inches)(lb/ft2)(gm/cc)Lower Wall30369.22.366Used for all walls, since it is lowest value and avoids a geometry refinement of limited benefitUpper Wall151872.397Roof (a)15181.72.329Roof, including blended girder mass but max rather than average thickness (conservative)(a) Roof thickness actually varies between 12 and 15 inches thick, every three inches. Average is 13.5 inches(b) Areal Densities from Page I-16.Detailed Density Treatments, Margin Reviews, and Girder Treatment Assessmentsp. gr.gm/cc143.4lb/cu.ft. LaSalle Concrete Mix Design2.29712Rebar spacing, in all cases (inches)109Rebar # for 30 inch wall97Rebar # for 15 inch wall67Rebar # for 12-15 inch roof490lb/cu.ft. for Rebar material0.01704420.013806Rebar volume/sq.ft. for 30 inch wall0.01380580.008352Rebar volume/sq.ft. for 15 inch wall0.00613590.008352Rebar volume/sq.ft. for 12-15 inch roof358.5For 30 inch wall179.25For 15 inch wall161.325For 12-15 inch roof1ReferenceValuegm/ccas-used369.2For 30 inch wall369.2perfect match2.3662.365conservative186.9For 15 inch wall187very close match2.3962.365conservative166.3For 12-15 inch roofnot included2.3692.328conservativeGirders118lb/lineal foot8.6666667Girder spacing (ft)7' 8" possibly used rather than 8' 8"mismatch13.6Girder Adjustment lb/sq.ft.Ref. valuegm/ccas-used180.0For 12-15 inch roof, with blended girders181.7mismatch2.5632.328conservativePer ANSI/ANS-6.4-1997, "For gamma ray sources, the presence of rebar may be considered and, if considered, a simple homogenization of the rebar and concrete is sufficient to account for its effect." Attachment IConcrete Shield Densities, Derived from Following ReportStraight Concrete Areal Density lb/sq.ft.Rebar Adjusted Concrete Area Density (lb/sq.ft.)Girders were blended with roof, but with an apparent too tight spacing in following report. Nevertheless, the as-used density, effectively, does not reflect girder mass. Still recoverable conservatisms include miniscule density increases on 30inch wall density, and minor density increases on thin wall and roof densities. It is recommended that any girder effects be addressed not by blending, but by explicit geometry modeling.Rebar diameter treated as 1/8th of Rebar #.

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