source - resrad.evs.anl.govdose mrem/yr per dpm/cm2 cumulative probability 36 m2 area 200 m2 area...

7.2.3.2 Dominant Pathways and Sensitive Parameters in AreaSource . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 53

7.2.4 Parameter Correlation Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 55

8 SUMMARY AND DISCUSSIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18.1 HIGHLIGHTS OF RESIDENTIAL SCENARIO RESULTS . . . . . . . . . . . . . . . . . 28.2 HIGHLIGHTS OF BUILDING OCCUPANCY SCENARIO RESULTS . . . . . . . . 4

9 REFERENCES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1

7.44 Ratio of Dose Distribution with and without Uncertainty on Shielding Thickness for a Volume Source in Building Occupancy Scenario . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 54

7.46 Ratio of Dose Distribution with and without Uncertaintyon Source Erosion Rate for a Volume Source in BuildingOccupancy Scenario . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 55

7.47 Ratio of Dose Distribution with and withoutUncertainty on Shielding Thickness for a Surface Sourcein Building Occupancy Scenario . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 62

7.48 Ratio of Dose Distribution with and without Uncertainty onRoom Area for a Surface Source in Building Occupancy Scenario . . . . . . . . . . . . 62

7.49 Ratio of Dose Distribution with and withoutUncertainty on Removable Fraction for a Surface Sourcein Building Occupancy Scenario . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 63

7.50 Ratio of Dose Distribution with and without Uncertainty onSource Life-Time for a Surface Source in Building Occupancy Scenario . . . . . . . 63

7.51 Ratio of Dose Distribution with and without Uncertainty onDeposition Velocity for a Surface Source in Building Occupancy Scenario . . . . . 64

7.52 Ratio of Dose Distribution with and without Uncertainty onResuspension Rate for a Surface Source in Building Occupancy Scenario . . . . . 64

7.53 Ratio of Dose Distribution with and without RankCorrelation between Deposition Velocity and ResuspensionRate for a Surface Source in Building Occupancy Scenario . . . . . . . . . . . . . . . . . . 65

Figure 7.34 Dose Variability of Am-241 for a Surface Sourcewith Three Source Areas in Building Occupancy Scenario . . . . . . . . . . . . . . 42

Figure 7.35 Dose Variability of C-14 for a Surface Sourcewith Three Source Areas in Building Occupancy Scenario . . . . . . . . . . . . . . 42

Figure 7.36 Dose Variability of Co-60 for a Surface Source

with Three Source Areas in Building Occupancy Scenario . . . . . . . . . . . . . . 43

Figure 7.37 Dose Variability of Cs-137 for a Surface Sourcewith Three Source Areas in Building Occupancy Scenario . . . . . . . . . . . . . . 43

Figure 7.38 Dose Variability of H-3 for a Surface Source with Three SourceAreas in Building Occupancy Scenario . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 44

Figure 7.39 Dose Variability of Pu-239 for a Surface Source with ThreeSource Areas in Building Occupancy Scenario . . . . . . . . . . . . . . . . . . . . . . . . 44

Figure 7.40 Dose Variability of Ra-226 for a Surface Source with ThreeSource Areas in Building Occupancy Scenario . . . . . . . . . . . . . . . . . . . . . . . . 45

Figure 7.41 Dose Variability of Sr-90 for a Surface Source with ThreeSource Areas in Building Occupancy Scenario . . . . . . . . . . . . . . . . . . . . . . . . 45

Figure 7.42 Dose Variability of Th-230 for a Surface Source with ThreeSource Areas in Building Occupancy Scenario . . . . . . . . . . . . . . . . . . . . . . . . 46

Figure 7.43 Dose Variability of U-238 for a Surface Source with ThreeSource Areas in Building Occupancy Scenario . . . . . . . . . . . . . . . . . . . . . . . . 46

7.8. Four Most Sensitive Parameters Based on SRRC Analysis and Dominant Pathways for a Volume Source of 36-m2 Area in a Building Occupancy Scenario . . . . . . . . . . . . . . . . . . . . 47

7.9. Four Most Sensitive Parameters Based onSRRC Analysis and Dominant Pathways for a VolumeSource of 200-m2 Area in a Building Occupancy Scenario . . . . . . . . . . . . . . . . . . 49

7.10. Four Most Sensitive ParametersBased on SRRC Analysis and Dominant Pathways for a Volume Source of 900-m2

Area in a Building Occupancy Scenario . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 517.11. Four Most Sensitive Parameters Based

on SRRC Analysis and Dominant Pathways for an Area Source of 36-m2 Area in a Building Occupancy Scenario . . . . . . . . . . . . . . . . . . . . . . . . . . 56

7.12. Four Most Sensitive Parameters Based on SRRC Analysis and Dominant Pathwaysfor an Area Sourceof 200-m2 Area in a Building Occupancy Scenario . . . . . . . . . . . . . . . . . . . . . . . . . 58

7.13. Four Most Sensitive Parameters Based on SRRC Analysis and Dominant Pathwaysfor an Area Source of 900-m2 Area in a Building Occupancy Scenario. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 60

7-38

Dose Variability for Am-241 Surface Source

0.00.10.20.30.40.50.60.70.80.91.0

0.0001 0.001 0.01 0.1 1 10

Dose mrem/yr per dpm/cm2

Cu

mu

lativ

e P

rob

abili

ty36 m2 area

200 m2 area

900 m2 area

Figure 7.34 Dose Variability of Am-241 for a Surface Sourcewith Three Source Areas in Building Occupancy Scenario

Dose Variability for C-14 Surface Source

0.00.10.20.30.40.50.60.70.80.91.0

1E-09 1E-08 1E-07 1E-06 0.00001 0.0001 0.001 0.01


Cu

mu

lativ

e P

rob

abili

ty

36 m2 area

200 m2 area

900 m2 area

Figure 7.35 Dose Variability of C-14 for a Surface Sourcewith Three Source Areas in Building Occupancy Scenario

7-39

Dose Variability for Co-60 Surface Source

0.00.10.20.30.40.50.60.70.80.91.0

1.00E-03 1.00E-02 1.00E-01 1.00E+00


Cu

mu

lativ

e P

rob

abili

ty36 m2 area

200 m2 area

900 m2 area

Figure 7.36 Dose Variability of Co-60 for a Surface Sourcewith Three Source Areas in Building Occupancy Scenario

Dose Variability for Cs-137 Surface Source

0.00.10.20.30.40.50.60.70.80.91.0

0.0001 0.001 0.01 0.1


Cum

ulat

ive

Pro

babi

lity

36 m2 area

200 m2 area

900 m2 area

Figure 7.37 Dose Variability of Cs-137 for a Surface Sourcewith Three Source Areas in Building Occupancy Scenario

7-40

Dose Variability for H-3 Surface Source

0.00.10.20.30.40.50.60.70.80.91.0

1E-10 1E-09 1E-08 1E-07 0.000001 0.00001 0.0001


Cum

ulat

ive

Pro

babi

lity

36 m2 area

200 m2 area

900 m2 area

Figure 7.38 Dose Variability of H-3 for a Surface Source with Three SourceAreas in Building Occupancy Scenario

Dose Variability for Pu-239 Surface Source

0.00.10.20.30.40.50.60.70.80.91.0

0.0001 0.001 0.01 0.1 1 10 100


Cum

ulat

ive

Pro

babi

lity

36 m2 area

200 m2 area

900 m2 area

Figure 7.39 Dose Variability of Pu-239 for a Surface Source with Three SourceAreas in Building Occupancy Scenario

7-41

Dose Variability for Ra-226 Surface Source

0.00.10.20.30.40.50.60.70.80.91.0

0.001 0.01 0.1 1 10


Cu

mu

lativ

e P

rob

abili

ty36 m2 area

200 m2 area

900 m2 area

Figure 7.40 Dose Variability of Ra-226 for a Surface Source with ThreeSource Areas in Building Occupancy Scenario

Dose Variability for Sr-90 Surface Source

0.00.10.20.30.40.50.60.70.80.91.0

0.000001 0.00001 0.0001 0.001 0.01 0.1 1


Cum

ulat

ive

Pro

babi

lity

36 m2 area

200 m2 area

900 m2 area

Figure 7.41 Dose Variability of Sr-90 for a Surface Source withThree Source Areas in Building Occupancy Scenario

7-42

Dose Variability for Th-230 Surface Source

0.00.10.20.30.40.50.60.70.80.91.0

0.0001 0.001 0.01 0.1 1 10 100


Cum

ulat

ive

Pro

babi

lity

36 m2 area

200 m2 area

900 m2 area

Figure 7.42 Dose Variability of Th-230 for a Surface Source with ThreeSource Areas in Building Occupancy Scenario

Dose Variability for U-238 Surface Source

0.00.10.20.30.40.50.60.70.80.91.0

0.0001 0.001 0.01 0.1 1 10


Cu

mu

lati

ve P

rob

abili

ty

36 m2 area

200 m2 area

900 m2 area

Figure 7.43 Dose Variability of U-238 for a Surface Source withThree Source Areas in Building Occupancy Scenario

7-43

Table 7.8. Four Most Sensitive Parameters Based on SRRC Analysis and Dominant Pathways for a Volume

Source of 36-m2 Area in a Building Occupancy Scenario

Four Most Sensitive Parametersb Based on SRRC Analysis

RadionuclideDominantPathwaya 1 2 3 4

Ac-227+Dc ext DSTH EROS0 AREAAg-108m+D ext DSTHAg-110+D ext DSTHAl-26 ext DSTH THICK0Am-241 inh + ext EROS0 DSTH AREA HAm-243+D ext DSTHAu-195 ext DSTHBi-207 ext DSTHC-14 ext DSTH EROS0 DKSUS UDCa-41 inh + ing EROS0 AREA DKSUS UDCd-109 ext DSTHCe-144+D ext DSTHCf-252 inh EROS0 AREA HCl-36 ext DSTHCm-243 ext DSTHCm-244 inh EROS0 AREA HCm-248 inh EROS0 AREA H DKSUSCo-57 ext DSTHCo-60 ext DSTH THICK0Cs-134 ext DSTHCs-135 ext DSTH DKSUS EROS0 UDCs-137+D ext DSTHEu-152 ext DSTHEu-154 ext DSTHEu-155 ext DSTHFe-55 inh EROS0 AREA H UDGd-152 inh EROS0 AREA HGd-153 ext DSTHGe-68+D ext DSTHH-3 inh + ing AREA DKSUS UD HI-129 ext DSTH EROS0 DKSUS UDK-40 ext DSTH THICK0Mn-54 ext DSTHNa-22 ext DSTHNb-94 ext DSTHNi-59 inh EROS0 AREA DKSUS HNi-63 inh EROS0 AREA DKSUS HNp-237+D ext DSTHPa-231 ext DSTH AREA EROS0

7-44

Table 7.8. Four Most Sensitive Parameters Based on SRRC Analysis and Dominant Pathways for a Volume

Source of 36-m2 Area in a Building Occupancy Scenario (Continued)



Pb-210+D ext DSTH EROS0 AREA DKSUSPm-147 ext DSTH EROS0 AREAPu-238 inh EROS0 AREA HPu-239 inh EROS0 AREA HPu-240 inh EROS0 AREA HPu241+D inh EROS0 AREA H DSTHPu-242 inh EROS0 AREA HPu-244+D ext DSTHRa-226+D ext DSTHRa-228+D ext DSTHRu-106+D ext DSTHSb-125 ext DSTHSm-147 inh EROS0 AREA HSm-151 inh EROS0 AREA HSr-90+D ext DSTH UD DSDENTc-99 ext DSTH EROS0Th-228+D ext DSTH THICK0Th-229+D ext DSTHTh-230+D inh AREA EROS0 DSTH HTh-232 ext DSTH AREA EROS0Tl-204 ext DSTH DSDENU-232 ext DSTH THICK0U-233 inh EROS0 AREA DSTH HU-234 inh EROS0 AREA HU-235+D ext DSTHU-236 inh EROS0 AREA HU-238+D ext DSTHZN-65 ext DSTH

a Pathways: ext = external, inh = inhalation, ing = ingestion.

b Parameters are only listed if SRRC was greater than 0.1. Descriptive name of theparameter is given in Table B.1.

c +D indicates that associated radionuclides with half-lives less than 6 months arein secular equilibrium with the principal radionuclides.

7-45

Table 7.9. Four Most Sensitive Parameters Based onSRRC Analysis and Dominant Pathways for a Volume




Ac-227+Dc ext DSTH AREA EROS0 HAg-108m+D ext DSTHAg-110+D ext DSTHAl-26 ext DSTHAm-241 inh EROS0 AREA DSTH HAm-243+D ext DSTH EROS0 AREAAu-195 ext DSTHBi-207 ext DSTHC-14 ext DSTH EROS0 DKSUS AREACa-41 inh + ing EROS0 AREA DKSUS UDCd-109 ext DSTHCe-144+D ext DSTHCf-252 inh EROS0 AREA HCl-36 ext DSTHCm-243 ext DSTH EROS0 AREACm-244 inh EROS0 AREA HCm-248 inh EROS0 AREA HCo-57 ext DSTHCo-60 ext DSTHCs-134 ext DSTHCs-135 ext DSTH DKSUS EROS0 UDCs-137+D ext DSTHEu-152 ext DSTHEu-154 ext DSTHEu-155 ext DSTHFe-55 inh EROS0 AREA H UDGd-152 inh EROS0 AREA H DENSI0Gd-153 ext DSTHGe-68+D ext DSTHH-3 inh + ing AREA DKSUS UD HI-129 ext EROS0 DSTH DKSUS AREAK-40 ext DSTHMn-54 ext DSTHNa-22 ext DSTHNb-94 ext DSTHNi-59 inh EROS0 AREA DKSUS HNi-63 inh EROS0 AREA DKSUS HNp-237+D ext DSTH AREA EROS0Pa-231 ext DSTH AREA EROS0 H

7-46

Table 7.9. Four Most Sensitive Parameters Based onSRRC Analysis and Dominant Pathways for a Volume




Pb-210+D ext DSTH EROS0 AREA DKSUSPm-147 ext DSTH EROS0 AREAPu-238 inh EROS0 AREA HPu-239 inh EROS0 AREA HPu-240 inh EROS0 AREA HPu241+D inh EROS0 AREA HPu-242 inh EROS0 AREA HPu-244+D ext DSTHRa-226+D ext DSTHRa-228+D ext DSTHRu-106+D ext DSTHSb-125 ext DSTHSm-147 inh EROS0 AREA HSm-151 inh EROS0 AREA HSr-90+D ext DSTH AREA DSDEN UDTc-99 ext DSTH EROS0 AREA DKSUSTh-228+D ext DSTHTh-229+D ext DSTH AREA EROS0Th-230+D inh EROS0 AREA H DSTHTh-232 ext DSTH AREA EROS0Tl-204 ext DSTHU-232 ext DSTHU-233 inh EROS0 AREA H DSTHU-234 inh EROS0 AREA HU-235+D ext DSTH AREAU-236 inh EROS0 AREA HU-238+D ext DSTH AREA EROS0ZN-65 ext DSTH



c +D indicates that associated radionuclides with half-lives less than 6 months are insecular equilibrium with the principal radionuclides.

7-47

Table 7.10. Four Most Sensitive ParametersBased on SRRC Analysis and Dominant Pathways for a Volume




Ac-227+Dc ext DSTH EROS0 AREA HAg-108m+D ext DSTHAg-110+D ext DSTHAl-26 ext DSTHAm-241 inh EROS0 AREA HAm-243+D ext DSTH EROS0 AREAAu-195 ext DSTHBi-207 ext DSTHC-14 ext DSTH EROS0 DKSUS AREACa-41 inh + ing EROS0 AREA DKSUS UDCd-109 ext DSTH EROS0 AREACe-144+D ext DSTHCf-252 inh EROS0 AREA HCl-36 ext DSTHCm-243 ext DSTH EROS0 AREACm-244 inh EROS0 AREA HCm-248 inh EROS0 AREA HCo-57 ext DSTHCo-60 ext DSTHCs-134 ext DSTHCs-135 ext DSTH DKSUS EROS0Cs-137+D ext DSTHEu-152 ext DSTHEu-154 ext DSTHEu-155 ext DSTHFe-55 inh EROS0 AREA H UDGd-152 inh EROS0 AREA HGd-153 ext DSTHGe-68+D ext DSTHH-3 inh + ing AREA DKSUS UD HI-129 inh + ing EROS0 DKSUS AREA UDK-40 ext DSTHMn-54 ext DSTHNa-22 ext DSTHNb-94 ext DSTHNi-59 inh EROS0 AREA DKSUS HNi-63 inh EROS0 AREA DKSUS HNp-237+D ext DSTH AREA EROS0Pa-231 inh EROS0 AREA DSTH H

7-48

Table 7.10. Four Most Sensitive ParametersBased on SRRC Analysis and Dominant Pathways for a Volume




Pb-210+D inh EROS0 AREA DKSUS UDPm-147 ext DSTH EROS0 AREA HPu-238 inh EROS0 AREA HPu-239 inh EROS0 AREA HPu-240 inh EROS0 AREA HPu241+D inh EROS0 AREA HPu-242 inh EROS0 AREA HPu-244+D ext DSTHRa-226+D ext DSTHRa-228+D ext DSTHRu-106+D ext DSTHSb-125 ext DSTHSm-147 inh EROS0 AREA HSm-151 inh EROS0 AREA HSr-90+D ext DSTH AREA EROS0 DSDENTc-99 ext DSTH EROS0 AREA DKSUSTh-228+D ext DSTHTh-229+D ext DSTH AREA EROS0 HTh-230+D inh EROS0 AREA HTh-232 inh + ext AREA EROS0 DSTH HTl-204 ext DSTHU-232 ext DSTH AREA EROS0U-233 inh EROS0 AREA HU-234 inh EROS0 AREA HU-235+D ext DSTH EROS0 AREAU-236 inh EROS0 AREA HU-238+D ext DSTH AREA EROS0ZN-65 ext DSTH


b Parameters are only listed if SRRC was greater than 0.1. Descriptive name ofthe parameter is given in Table B.1.

c +D indicates that associated radionuclides with half-lives less than 6 months arein secular equilibrium with the principal radionuclides.

7-49

and without the uncertainty on shieldingthickness is shown in Figure 7.44.

For radionuclides for which inhalation was thedominant pathway, room area and source erosionrate were two dominant parameters thatcontributed to large dose variability. Threeradionuclides (Am-241, Cm-244, and Pu-238)were selected to study the effect of room areaand erosion rate on the dose variability.Figures 7.45 and 7.46 show the dose ratio(95th percentile dose to 50th percentile dose)with and without the uncertainty on room areaand source erosion rate.

7.2.3.2 Dominant Pathways and Sensitive Parameters in Area Source

Tables 7.11 through 7.13 list the four mostsensitive parameters based on SRRC along withthe dominant pathway for the three sources.Tables C.7 through C.9 in Appendix C presentdetailed information, including SRRC values. Onlysensitive parameters with SRRC values of $0.1are only listed in these tables. An SRRC value of0.1 means that one standard deviation change inthe parameter value will change the resultantdose by 0.1 times the standard deviation of thedose.

For radionuclides for which external exposurewas the dominant pathway, shielding thicknesswas found to be the dominant contributor to thedose variability. Three radionuclides (Co-60,Al-26, and Eu-152) were selected to study theeffect of shielding thickness. It was observed thatafter removing the shielding thickness fromuncertainty analysis, dose variability wassignificantly reduced. Figure 7.47 shows the doseratio (95th percentile dose to 50th percentiledose) with and without the uncertainty onshielding thickness.

For radionuclides for which inhalation was thedominant pathway, many parameters (e.g., roomarea, removable fraction, source lifetime)contributed to the dose variability. Figures 7.48through 7.50 show the dose ratio (95th percentiledose to 50th percentile dose) with and withoutthe uncertainty for room area, removable fraction,and source lifetime, respectively, for Am-241, Pu-239, and U-238.

For radionuclides with the ingestion pathway asthe dominant contributor to the dose, apart fromthree parameters (room area, removable fraction,source life-time) that contributed to dosevariability in the inhalation pathway, depositionvelocity and resuspension rate also showed highsensitivity. Figures 7.51 and 7.52 show the effectof deposition velocity and resuspension rate onthe dose variability for C-14, I-129, and Cs-135.

7.2.4 Parameter Correlation Results

The results showed that resuspension rate anddeposition velocity were sensitive parameters forsome radionuclides (e.g., C-14, Ca-41, Cs-135,and I-129) in the case of volume sources. Apositive rank correlation of 0.9 was used betweendeposition velocity and resuspension rate. Fourradionuclides (Ca-41, I-129, C-14, and Cs-135)were selected to study the effect of correlation.Figure 7.53 shows the difference in dosevariability with and without correlation betweendeposition velocity and resuspension rate. Dosevariability was considerably reduced by the use ofcorrelation. In the absence of knowledge of realcorrelation between deposition velocity andresuspension rate, rank correlation was not usedin the analysis.

7-50

Ratio of Dose Distribution ( 95% to 50%) with and without Uncertainty on Shielding Thickness

0

24

6

8

Cs-137 Mn-54 Pu-244

Radionuclides

Rat

io o

f Dos

e D

istr

ibut

ion

With shielding thickness uncertainty Without shielding thickness uncertainty

Figure 7.44 Ratio of Dose Distribution with and withoutUncertainty on Shielding Thickness for a Volume

Source in Building Occupancy Scenario

Ratio of Dose Distribution ( 95% to 50%) with and without Uncertainty on Room Area

02468

10

Pu-238 Am-241 Cm-244

Radionuclides

Rat

io o

f D

ose

D

istr

ibu

tio

n

With uncertainty on room area Without uncertainty on room area

Figure 7.45 Ratio of Dose Distribution with and without Uncertainty onRoom Area for a Volume Source in Building Occupancy Scenario

7-51

Ratio of Dose Distribution ( 95% to 50%) with and without Uncertainty on Source Erosion Rate

0

5

10

Pu-238 Am-241 Cm-244

Radionuclides

Rat

io o

f D

ose

D

istr

ibu

tio

n

With uncertainty on source erosion rate

Without uncertainty on source erosion rate

Figure 7.46 Ratio of Dose Distribution with and without Uncertaintyon Source Erosion Rate for a Volume Source in Building

Occupancy Scenario

7-52

Table 7.11. Four Most Sensitive Parameters Basedon SRRC Analysis and Dominant Pathways for an Area Source

of 36-m2 Area in a Building Occupancy Scenario



Ac-227+Dc inh AREA RF0 RMVFR HAg-108m+D ext DSTHAg-110+D ext DSTHAl-26 ext DSTHAm-241 inh AREA RF0 RMVFR HAm-243+D inh AREA RF0 RMVFR DSTHAu-195 ext DSTHBi-207 ext DSTHC-14 inh + ing AREA DKSUS RF0 RMVFRCa-41 inh + ing AREA DKSUS RF0 RMVFRCd-109 ext DSTH AREA RF0 RMVFRCe-144+D ext DSTHCf-252 inh AREA RF0 RMVFR HCl-36 ext DSTH AREA RF0 UDCm-243 inh AREA RF0 RMVFR DSTHCm-244 inh AREA RF0 RMVFR HCm-248 inh AREA RF0 RMVFR HCo-57 ext DSTHCo-60 ext DSTHCs-134 ext DSTHCs-135 inh + ing DKSUS AREA RF0 DSTHCs-137+D ext DSTHEu-152 ext DSTHEu-154 ext DSTHEu-155 ext DSTHFe-55 inh AREA RF0 RMVFR HGd-152 inh AREA RF0 RMVFR HGd-153 ext DSTHGe-68+D ext DSTHH-3 inh + ing AREA RF0 RMVFR DKSUSI-129 ing DKSUS AREA RF0 RMVFRK-40 ext DSTHMn-54 ext DSTHNa-22 ext DSTHNb-94 ext DSTHNi-59 inh AREA RF0 RMVFR HNi-63 inh AREA RF0 RMVFR HNp-237+D inh AREA RF0 RMVFR DSTHPa-231 inh AREA RF0 RMVFR H

7-53

Table 7.11. Four Most Sensitive Parameters Basedon SRRC Analysis and Dominant Pathways for an Area Source

of 36-m2 Area in a Building Occupancy Scenario (Continued)



Pb-210+D inh AREA RF0 RMVFR DKSUSPm-147 inh AREA RF0 RMVFR DSTHPu-238 inh AREA RF0 RMVFR HPu-239 inh AREA RF0 RMVFR HPu-240 inh AREA RF0 RMVFR HPu241+D inh AREA RF0 RMVFR HPu-242 inh AREA RF0 RMVFR HPu-244+D ext DSTH AREA RF0 RMVFRRa-226+D ext DSTHRa-228+D ext DSTH AREA RF0 RMVFRRu-106+D ext DSTHSb-125 ext DSTHSm-147 inh AREA RF0 RMVFR HSm-151 inh AREA RF0 RMVFR HSr-90+D inh AREA RF0 DSTH RMVFRTc-99 inh + ext DSTH AREA RF0 RMVFRTh-228+D ext DSTH AREA RF0 RMVFRTh-229+D inh AREA RF0 RMVFR HTh-230+D inh AREA RF0 RMVFR HTh-232 inh AREA RF0 RMVFR HTl-204 ext DSTH AREA RF0 UDU-232 inh AREA RF0 RMVFR DSTHU-233 inh AREA RF0 RMVFR HU-234 inh AREA RF0 RMVFR HU-235+D inh + ext DSTH AREA RF0 RMVFRU-236 inh AREA RF0 RMVFR HU-238+D inh AREA RF0 RMVFR HZN-65 ext DSTH



c +D indicates that associated radionuclides with half-lives less than 6 months are insecular equilibrium with the principal radionuclides.

7-54

Table 7.12. Four Most Sensitive Parameters Based on SRRC Analysisand Dominant Pathways for an Area Source

of 200-m2 Area in a Building Occupancy Scenario



Ac-227+Dc inh AREA RF0 RMVFR HAg-108m+D ext DSTHAg-110+D ext DSTHAl-26 ext DSTHAm-241 inh AREA RF0 RMVFR HAm-243+D inh AREA RF0 RMVFR HAu-195 ext DSTH AREA RF0 RMVFRBi-207 ext DSTHC-14 inh + ing AREA DKSUS RF0 RMVFRCa-41 inh + ing AREA DKSUS RF0 RMVFRCd-109 ext DSTH AREA RF0 RMVFRCe-144+D ext DSTHCf-252 inh AREA RF0 RMVFR HCl-36 ext DSTH AREA RF0 RMVFRCm-243 inh AREA RF0 RMVFR HCm-244 inh AREA RF0 RMVFR HCm-248 inh AREA RF0 RMVFR HCo-57 ext DSTHCo-60 ext DSTHCs-134 ext DSTHCs-135 inh + ing DKSUS AREA RF0 RMVFRCs-137+D ext DSTHEu-152 ext DSTHEu-154 ext DSTHEu-155 ext DSTH AREA RF0 RMVFRFe-55 inh AREA RF0 RMVFR HGd-152 inh AREA RF0 RMVFR HGd-153 ext DSTH AREA RF0 RMVFRGe-68+D ext DSTHH-3 inh + ing AREA RF0 RMVFR DKSUSI-129 inh + ing DKSUS AREA RF0 RMVFRK-40 ext DSTHMn-54 ext DSTHNa-22 ext DSTHNb-94 ext DSTHNi-59 inh AREA RF0 RMVFR H

7-55

Table 7.12. Four Most Sensitive Parameters Based on SRRC Analysisand Dominant Pathways for an Area Source

of 200-m2 Area in a Building Occupancy Scenario (Continued)



Ni-63 inh AREA RF0 RMVFR HNp-237+D inh AREA RF0 RMVFR HPa-231 inh AREA RF0 RMVFR HPb-210+D inh + ing AREA RF0 RMVFR DKSUSPm-147 inh AREA RF0 RMVFR HPu-238 inh AREA RF0 RMVFR HPu-239 inh AREA RF0 RMVFR HPu-240 inh AREA RF0 RMVFR HPu241+D inh AREA RF0 RMVFR HPu-242 inh AREA RF0 RMVFR HPu-244+D inh AREA DSTH RF0 RMVFRRa-226+D ext DSTH AREA RF0Ra-228+D ext DSTH AREA RF0 RMVFRRu-106+D ext DSTHSb-125 ext DSTHSm-147 inh AREA RF0 RMVFR HSm-151 inh AREA RF0 RMVFR HSr-90+D inh AREA RF0 RMVFR UDTc-99 inh AREA RF0 RMVFR DSTHTh-228+D ext DSTH AREA RF0 RMVFRTh-229+D inh AREA RF0 RMVFR HTh-230+D inh AREA RF0 RMVFR HTh-232 inh AREA RF0 RMVFR HTl-204 ext DSTH AREA RF0 UDU-232 inh AREA RF0 RMVFR HU-233 inh AREA RF0 RMVFR HU-234 inh AREA RF0 RMVFR HU-235+D inh AREA RF0 RMVFR DSTHU-236 inh AREA RF0 RMVFR HU-238+D inh AREA RF0 RMVFR HZN-65 ext DSTH


b Parameters are only listed if SRRC was greater than 0.1. Descriptive nameof the parameter is given in Table B.1.

c +D indicates that associated radionuclides with half-lives less than6 months are in secular equilibrium with the principal radionuclides.

7-56

Table 7.13. Four Most Sensitive Parameters Based on SRRC Analysisand Dominant Pathways for an Area Source of 900-m2 Area in a

Building Occupancy Scenario



Ac-227+Dc inh AREA RF0 RMVFR HAg-108m+D ext DSTHAg-110+D ext DSTHAl-26 ext DSTHAm-241 inh AREA RF0 RMVFR HAm-243+D inh AREA RF0 RMVFR HAu-195 ext DSTH AREA RF0 RMVFRBi-207 ext DSTHC-14 inh +ing AREA DKSUS RF0 RMVFRCa-41 inh + ing AREA DKSUS RF0 RMVFRCd-109 inh AREA DSTH RF0 RMVFRCe-144+D ext DSTH AREA RF0 RMVFRCf-252 inh AREA RF0 RMVFR HCl-36 inh AREA DSTH RF0 RMVFRCm-243 inh AREA RF0 RMVFR HCm-244 inh AREA RF0 RMVFR HCm-248 inh AREA RF0 RMVFR HCo-57 ext DSTHCo-60 ext DSTHCs-134 ext DSTHCs-135 ing DKSUS AREA RF0 RMVFRCs-137+D ext DSTHEu-152 ext DSTHEu-154 ext DSTHEu-155 ext DSTH AREA RF0 RMVFRFe-55 inh AREA RF0 RMVFR HGd-152 inh AREA RF0 RMVFR HGd-153 ext DSTH AREA RF0 RMVFRGe-68+D ext DSTHH-3 inh + ing AREA RF0 RMVFR DKSUSI-129 inh + ing DKSUS AREA RF0 RMVFRK-40 ext DSTHMn-54 ext DSTHNa-22 ext DSTHNb-94 ext DSTHNi-59 inh AREA RF0 RMVFR HNi-63 inh AREA RF0 RMVFR HNp-237+D inh AREA RF0 RMVFR H

7-57

Table 7.13. Four Most Sensitive Parameters Based on SRRC Analysisand Dominant Pathways for an Area Source of 900-m2 Area in a

Building Occupancy Scenario (Continued)



Pa-231 inh AREA RF0 RMVFR HPb-210+D inh + ing AREA RF0 RMVFR DKSUSPm-147 inh AREA RF0 RMVFR HPu-238 inh AREA RF0 RMVFR HPu-239 inh AREA RF0 RMVFR HPu-240 inh AREA RF0 RMVFR HPu241+D inh AREA RF0 RMVFR HPu-242 inh AREA RF0 RMVFR HPu-244+D inh AREA RF0 RMVFR HRa-226+D ext DSTH AREA RF0 UDRa-228+D ext DSTH AREA RF0 RMVFRRu-106+D ext DSTH AREA RF0Sb-125 ext DSTHSm-147 inh AREA RF0 RMVFR HSm-151 inh AREA RF0 RMVFR HSr-90+D inh AREA RF0 RMVFR HTc-99 inh + ing AREA RF0 RMVFR DKSUSTh-228+D inh AREA RF0 RMVFR DSTHTh-229+D inh AREA RF0 RMVFR HTh-230+D inh AREA RF0 RMVFR HTh-232 inh AREA RF0 RMVFR HTl-204 ext DSTH AREA RF0 UDU-232 inh AREA RF0 RMVFR HU-233 inh AREA RF0 RMVFR HU-234 inh AREA RF0 RMVFR HU-235+D inh AREA RF0 RMVFR HU-236 inh AREA RF0 RMVFR HU-238+D inh AREA RF0 RMVFR HZN-65 ext DSTH


b Parameters are only listed if SRRC was greater than 0.1. Descriptive nameof the parameter is given in Table B.1.

c +D indicates that associated radionuclides with half-lives less than 6 monthsare in secular equilibrium with the principal radionuclides.

7-58

Ratio of Dose Distribution ( 95% to 50%) with and without Uncertainty on Sheilding thickness

0

2

4

6

Co-60 Al-26 Eu-152

Radionuclides

Rat

io o

f D

ose

D

istr

ibu

tio

n

With uncertainty on shielding thickness

Without uncertainty on shielding thickness

Ratio of Dose Distribution ( 95% to 50%) with and without Uncertainty on Room Area

0

5

10

15

20

Am-241 Pu-239 U-238

Radionuclides

Rat

io o

f D

ose

D

istr

ibu

tio

n

With uncertainty on room area Without uncertainty on room area

Figure 7.47 Ratio of Dose Distribution with and withoutUncertainty on Shielding Thickness for a Surface Source

in Building Occupancy Scenario

Figure 7.48 Ratio of Dose Distribution with and without Uncertainty onRoom Area for a Surface Source in Building Occupancy Scenario

7-59

Ratio of Dose Distribution ( 95% to 50%) with and without Uncertainty on Removable Fraction

05

101520

Am-241 Pu-239 U-238

Radionuclides

Rat

io o

f D

ose

D

istr

ibu

tio

n

With uncertainty on removable fraction

Without uncertainty on removable fraction

Ratio of Dose Distribution ( 95% to 50%) with and without Uncertainty on Source Life-time

0

5

10

15

20

Am-241 Pu-239 U-238

Radionuclides

Rat

io o

f D

ose

D

istr

ibu

tio

n

With uncertainty on source life-time Without uncertainty on source life-time

Figure 7.49 Ratio of Dose Distribution with and withoutUncertainty on Removable Fraction for a Surface Source

in Building Occupancy Scenario

Figure 7.50 Ratio of Dose Distribution with and without Uncertainty onSource Lifetime for a Surface Source in Building Occupancy Scenario

7-60

Ratio of Dose Distribution ( 95% to 50%) with and without Uncertainty on Deposition Velocity

020

40

60

C-14 I-129 Cs-135

Radionuclides

Rat

io o

f D

ose

D

istr

ibu

tio

n

With uncertainty on deposition velocity

Without uncertainty on deposition velocity

Ratio of Dose Distribution ( 95% to 50%) with and without Uncertainty on Resuspension Rate

1

10

100

C-14 I-129 Cs-135

Radionuclides

Rat

io o

f D

ose

D

istr

ibu

tio

n

With uncertainty on resuspension rate

Without uncertainty on resuspension rate

Figure 7.51 Ratio of Dose Distribution with and without Uncertainty onDeposition Velocity for a Surface Source in Building Occupancy Scenario

Figure 7.52 Ratio of Dose Distribution with and without Uncertainty onResuspension Rate for a Surface Source in Building Occupancy Scenario

7-61

Ratio of Dose Distribution ( 95% to 50%) with and without Rank correlation of 0.9 between Deposition Velocity and Resuspension Rate

1

10

100

1000

Ca-41 I-129 C-14 Cs-135

Radionuclides

Rat

io o

f D

ose

D

istr

ibu

tio

n

Without correlation With rank correlation

Figure 7.53 Ratio of Dose Distribution with and without RankCorrelation between Deposition Velocity and ResuspensionRate for a Surface Source in Building Occupancy Scenario

8-1

8 SUMMARY AND DISCUSSION

The probabilistic dose analysis discussed in thisreport was conducted to assess the effects ofparameter distributions on estimated doses forresidual radionuclides as calculated with theRESRAD and RESRAD-BUILD codes for theresidential and building occupancy scenarios,respectively. Parameter distributions developedby Biwer et al. (2000) were successfullyincorporated into the RESRAD and RESRAD-BUILD codes, and the capability of the two codesto conduct site-specific analyses was tested.

The probabilistic dose analysis was performed byusing the stratified sampling of the Latinhypercube sampling (LHS) method to obtain acollection of input distributions. This methodprovides a rather efficient process formultiparameter sampling. In the analysis, thetotal effective dose equivalent (TEDE) wasestimated for an average member of the criticalgroup under the two scenarios used to assesscompliance with the U.S. Nuclear RegulatoryCommission’s (NRC’s) decommissioning andlicense termination criteria. For RESRAD, thepeak dose within a time frame of 1,000 years wascaptured; for RESRAD-BUILD, the dose at time 0was computed.

The dose distribution analysis conducted for thisreport used the generic distributions developed inthe Parameter Distribution Report (Biweret al., 2000) to test the distribution data and todemonstrate the capability of RESRAD andRESRAD-BUILD to perform a site-specificanalysis. The specific strategy used to selectinput values depended on the parametercategories (physical, behavioral, or metabolic).The effect of correlation of input parameterdistribution was studied. In cases when a clearrelationship was identified (such as bulk densityand total porosity and total porosity and effectiveporosity), strong rank correlations were used.

Some parameters previously identified to beimportant to dose values (Cheng et al., 1999)

were confirmed in the analysis. For RESRAD,such parameters include radionuclideconcentrations, source area, and sourcethickness. For RESRAD-BUILD, theseparameters include radionuclide concentrationsand source area. To illustrate the sensitivity ofthe parameters, three source configurations wereanalyzed for RESRAD: (1) area of 100 m2 andthickness of 15 cm; (2) area of 2,400 m2 andthickness of 15 cm; (3) area of 10,000 m2 andthickness of 2 m. For RESRAD-BUILD, threedifferent areas (36 m2, 200 m2, and 900 m2) wereanalyzed for area sources, and the same threeareas (36 m2, 200 m2, and 900 m2) along with theprobability distribution on source thickness wereused for volume sources.

Results for the residential scenario indicate thatfor a change from the baseline configuration(source configuration 1) to an increased area(source configuration 2), a 19-fold increase in theestimated dose could occur, while a change fromthe baseline case to an extended thickness andarea (source configuration 3) could lead a 100-fold increase in the estimated dose. Similarly forthe building occupancy scenario, a change insource area could lead to a 25-fold increase inthe estimated dose.

Quantile values (at 50th percentile and 90thpercentile) of the dose distributions weregenerated. Dose spread for different radionuclideswas identified by the ratio of dose at the 99thpercentile to that at the 50th percentile for theresidential scenario and by the ratio of dose atthe 95th percentile to that at the 50th percentilefor the building occupancy scenario. Regressionanalysis was used to identify sensitiveparameters. The partial rank correlationcoefficients and standardized rank regressioncoefficients were used as illustrative examples inthe residential and building occupancy scenarios,respectively. The effects of sensitive parameterson distribution were studied for selectedradionuclides.

8-2

Results demonstrate the successful integration ofthe parameter distributions developed for theresidential and building occupancy scenarios withthe probabilistic module developed for theRESRAD and RESRAD-BUILD codes to supportNRC’s license termination effort. The resultsdemonstrate that the codes and the developedinput parameter distributions can be used toaccomplish a probabilistic analysis. Applicationof the process is therefore shown to be feasiblefor site-specific modeling and analysis in thefuture when data pertinent to a specific site canbe developed.

In a site-specific application, however, somegeneral aspects must be taken into account toensure accurate modeling and analysis:

• Parameter sensitivity depends on thecontamination configuration, and, therefore, itis site specific. It is important that ranking ofkey parameters be assessed for eachindividual site.

• Potential correlation between a parameterand the estimated dose varies fromradionuclide to radionuclide. Specialconsiderations, experience, and judgmentwould be needed in obtaining an accurateassessment.

• Site-specific data collection may be neededfor parameters consistently identified to beimportant to the dose analysis in this report.

8.1 HIGHLIGHTS OF RESIDENTIALSCENARIO RESULTS

• Probabilistic dose analyses for 90 principalradionuclides in three source configurationswere performed with distributions for33 radionuclide-independent parameters andmany radionuclide-dependent parameters forthe residential scenario.

• Results indicate that the doses calculatedappear reasonable and show a consistent

pattern. The ratio between the 99th percentiledose and 50th percentile dose ranges from2.0 to 79 for all radionuclides. Such variationsdepend on the source configurations and onthe type of radionuclide. For radionuclideswith a dominant external pathway, the ratiobetween the 99th percentile dose and50th percentile dose was close to 2.3(Ag-108m and Eu-152). For radionuclideswith other dominant pathways, dosevariabilities were higher. However, site-specific distributions should be usedwhenever available, especially for sensitiveparameters such as the external shieldingfactor and the plant transfer factor.

• Input rank correlations between total porosityand effective porosity and between bulkdensity and total porosity were studied, andthe results were used in the probabilisticdose analysis to ensure proper pairingbetween the parameters.

• Significant changes in dose values wereobserved among the three sourceconfigurations (i.e., changes in sourcethickness or source area resulted insignificant changes in dose). For someradionuclides (e.g., Ca-145 and H-3), dosevalues changed by an order of magnitude.The dose at 90th percentile increased by12% to 2,900% when the source areachanged from 100 m2 to 2,400 m2 with aconstant source thickness of 15 cm. Whenthe source thickness was changed to 2 mand the source area to 10,000 m2 from asource thickness of 15 cm and an area of2,400 m2, dose at 90th percentile increasedby 5% to 2,600%.

• For about 30 radionuclides, the upper 10% ofthe peak doses occurred at times other thantime 0. For these radionuclides, sensitiveparameters would change with the dosepercentile selected.

• The external shielding factor was the mostsensitive parameter in many cases when

8-3

external exposure was the dominant pathway(this factor accounts for the shielding provided bythe structure of the house when the receptor isinside), and the total dose variability could beexplained with just the variability in the externalshielding factor.

• The plant transfer factor was the mostsensitive parameter in many cases whenplant ingestion was the dominant pathway(such as for Ca-45 and Cs-135).

• It was observed that no single correlation orregression coefficient (e.g., PRCC, SRRC)can be used alone to identify sensitiveparameters in all the cases. The coefficientsare useful guides, but they have to be used inconjunction with other aids, such as scatterplots, and must undergo further analysis.

8.2 HIGHLIGHTS OF BUILDING OCCUPANCYSCENARIO RESULTS

• Probabilistic dose analyses were performedfor 67 principal radionuclides for two sourcetypes (volume and area), with three sourceareas, with distributions for 15 parameters.

• Results indicate that all parameterdistributions are reasonable and consistentfor all cases and radionuclides analyzed.However, site-specific distributions should beused whenever available, especially forsensitive parameters.

• Dose variability in the RESRAD-BUILDresults for the building occupancy scenariofor both volume and area sources was muchmore than the dose variability observed inRESRAD results for the residential scenario.

• Significant changes (by as much as 25-fold)in dose values were observed with change insource area (from 36 m2 to 900 m2) for manyradionuclides (such as Cm-244 and Ni-63).For radionuclides with a dominant externalpathway (e.g., Co-60, Cs-137), dose changeswith source area occurred only at high dosepercentile values. Because of shieldingbetween the source and receptor, dosevalues did not change at low dose percentilevalues.

• For radionuclides with a dominant external

exposure pathway (e.g., Co-60, Cs-137),shielding thickness between the source andreceptor was the dominant contributor to thedose variability (ratio between the 95thpercentile dose and 50th percentile dose) forvolume as well as area sources.

• For radionuclides such as Am-241 andPu-238 with a dominant inhalation pathway,room area and source erosion rate were thetwo most sensitive parameters for volumesources. For area sources, the parametersroom area, removable fraction, and sourcelifetime all contributed to the dose variability.

• For a volume source, the ingestion pathwaywas dominant only for two radionuclides (Ca-41 and H-3). For surface sources, theingestion pathway was dominant for a fewmore radionuclides (C-14, Cs-135, I-129).

• For radionuclides with a dominant ingestionpathway (such as C-14 and Cs-135), inaddition to the sensitive parameters identifiedfor the inhalation pathway, deposition velocityand resuspension rate also contributed todose variability.

• When a rank correlation coefficient of 0.9between deposition velocity andresuspension rate was used, the dosevariability was significantly reduced (by afactor of 7).

9-1

9 REFERENCES

Beyeler, W.E., et al. NUREG/CR-5512, SAND99-2148, Vol. 3, “Residual Radioactive Contaminationfrom Decommissioning: Parameter Analysis.”Prepared by Sandia National Laboratories,Albuquerque, N.M., for U.S. Nuclear RegulatoryCommission. October 1999.

Biwer, B.M., et al. “Parameter Distributions forUse in RESRAD and RESRAD-BUILD ComputerCodes, Revision 1.” Letter report prepared byArgonne National Laboratory, Argonne, IL, forU.S. Nuclear Regulatory Commission. March2000.

Cheng, J.-J., et al. “Selection of RESRAD andRESRAD-BUILD Input Parameters for DetailedDistribution Analysis, Revision 1.” Letter reportprepared by Argonne National Laboratory,Argonne, IL, for U.S. Nuclear RegulatoryCommission. October 1999.

Cullen, A.C. and H.C. Frey. ProbabilisticTechniques in Exposure Assessment. PlenumPress: New York, N.Y. 1999.

Haaker, R., et al. NUREG/CR-5512, Vol. 4,“Comparison of Models and Assumptions Used inthe DandD 1.0, RESRAD 5.61 and RESRAD-BUILD 1.50 Computer Codes with Respect to theResidential Farmer and Industrial OccupantScenario Provided in NUREG/CR-5512.” Preparedby Sandia National Laboratories, AlbuquerqueN.M., for U.S. Nuclear Regulatory Commission. October 1999.

Iman, R.L. and J.C. Helton. NUREG/CR-3904,SAND84-1461 RG, “A Comparison of Uncertaintyand Sensitivity Analysis Techniques for ComputerModels.” Prepared by Sandia NationalLaboratories, Albuquerque, N.M., for the U.S.Nuclear Regulatory Commission. March 1985.

Iman, R.L. and M.J. Shortencarier. NUREG/CR-3624, SAND83-2365 RG, “A FORTRAN 77Program and User’s Guide for the Generation of

Latin Hypercube and Random Samples for Usewith Computer Models.” Prepared by SandiaNational Laboratories, Albuquerque, N.M., forU.S. Nuclear Regulatory Commission. March1984.

Iman, R.L., et al. NUREG/CR-4122, SAND85-0044 RG, “A FORTRAN 77 Program and User’sGuide for the Calculation of Partial Correlation andStandard Regression Coefficients.” Prepared bySandia National Laboratories, Albuquerque, N.M.,for U.S. Nuclear Regulatory Commission. June1985.

International Atomic Energy Agency. “EvaluatingReliability of Predictions Made UsingEnvironmental Transfer Models.” Report No. 100.IAEA: Vienna. 1989.

International Commission on RadiologicalProtection. “Principles of Monitoring for theProtection of the Population.” ICRPPublication 43. Pergamon Press: New York, N.Y. 1984.

Kamboj, S., et al. “Parameters and ParameterTypes in RESRAD and RESRAD-BUILD Codes.”Letter report prepared by Argonne NationalLaboratory, Argonne, IL, for U.S. NuclearRegulatory Commission. September 1999.

Kennedy, W.E. and Strenge, D.L. NUREG/CR-5512, PNL 7994, Vol. 1, “Residual RadioactiveContamination from Decommissioning; ATechnical Basis for Translating ContaminationLevels to Annual Total Effective Dose Equivalent.”Prepared by Pacific Northwest Laboratory forU.S. Nuclear Regulatory Commission. October1992.

McKay, M.D., et al. “A Comparison of ThreeMethods for Selecting Values of Input Variables inthe Analysis of Output from a Computer Code.”Technometrics, Vol. 21, pp. 239-245. 1979.

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Nuclear Regulatory Commission (U.S.) (NRC).NUREG-1549, “Decision Methods for DoseAssessment to Comply with Radiological Criteriafor License Termination,” Draft Report forComment, Division of Regulatory Applications,Office of Nuclear Regulatory Research, NRC:Washington, D.C. July 1998a.

Nuclear Regulatory Commission (U.S.) (NRC).Draft Regulatory Guide, DG 4006, “DemonstratingCompliance with the Radiological Criteria forLicense Termination.” Office of Nuclear RegulatoryResearch, NRC: Washington, D.C. August1998b.

Nuclear Regulatory Commission (U.S.) (NRC).NUREG/CP-0163, “Proceedings of the Workshopon Review of Dose Modeling Methods forDemonstration of Compliance With theRadiological Criteria for License Termination.”NRC: Washington, D.C. May 1998c.

Wernig, M.A., et al. NUREG/CR-5512, Vol. 2,“Residual Radioactive Contamination fromDecommissioning.” Office of Nuclear RegulatoryResearch, NRC: Washington, D.C. May 1999.

Yu, C. “RESRAD Family of Codes andComparison with Other Codes forDecontamination and Restoration of NuclearFacilities.” Chapter 11, pp. 207-231, in:Decommissioning and Restoration of NuclearFacilities. M.J. Slobodien (Ed.). Medical PhysicsPublishing: Madison, WI. 1999.

Yu, C., et al. “Manual for Implementing ResidualRadioactive Material Guidelines Using RESRAD,Version 5.0.” ANL/EAD/LD-2. Argonne NationalLaboratory: Argonne, IL. September 1993.

Yu, C., et al. “RESRAD-BUILD: A ComputerModel for Analyzing the Radiological DosesResulting from the Remediation and Occupancyof Buildings Contaminated with RadioactiveMaterial.” ANL/EAD/LD-3. Argonne NationalLaboratory: Argonne, IL. November 1994.

source - resrad.evs.anl.govdose mrem/yr per dpm/cm2 cumulative probability 36 m2 area 200 m2 area...

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