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College of EngineeringOregon State University
DOE’s Graded Approach for Evaluating Radiation Doses to Biota: Derivation of Screening and Analysis
Methodologies
KA Higley, Oregon State University;
Oregon State University
Nuclear engineering & Radiation Health Physics
Overview Technical Marching Orders
Goals Limitations Conditions
Derivation of Technical Method Assumptions Screening Phase Analysis Phase
Product: Electronic Spreadsheets Ongoing Development / Implementation Issues
Oregon State University
Nuclear engineering & Radiation Health Physics
Technical Marching Orders Goal:
Simple, defensible, user friendly method
Limitations & Conditions: Utilize existing generic & site-specific data Broad-based application (mice to elephants) Provide departure point for in-depth analysis
Applicable to multiple media: Soil Sediment Water
Oregon State University
Nuclear engineering & Radiation Health Physics
Biota Dose Evaluation Methodology Technical Approach
Basic method & assumptions External dose calculation Internal dose calculation
Screening phase (Lumped Parameter) Detailed Analysis (Kinetic/Allometric)
Quality Assurance Uncertainty analysis Real-world verification
Oregon State University
Nuclear engineering & Radiation Health Physics
Basic Method
Dose: function of contaminant concentration in environment sum of internal & external contributions
Evaluate for unit contaminant concentration (e.g., 1 Bq g-1) single media (e.g., soil)
Ratio calculated dose to standard (e.g., 0.01 Gy d-1) Back calculate media limit Use sum of fractions approach for:
multiple media multiple nuclides
Oregon State University
Nuclear engineering & Radiation Health Physics
External Dose Calculations Homogeneous nuclide distribution Infinite source Infinitesimal receptor organism Source & receptor geometry:
water & soil sediment
Oregon State University
Nuclear engineering & Radiation Health Physics
Internal Dose Assumptions Organism is a “blob” of tissue
All decay energies retained in tissue (i.e., infinite receptor)
Alpha dose-modifying factors (i.e., wR = 20)*
Chain-decay progeny included (E.F. = 1)* Nuclides homogeneously distributed
* user can modify
Oregon State University
Nuclear engineering & Radiation Health Physics
Screening Phase Calculations
Predictive (empirical) parameters Ratios concentration in organism to surrounding media CR Biv
Literature values available Many nuclides Plant to soil Aquatic species to water
Allows back-calculation of media concentration corresponding to limiting internal dose
Oregon State University
Nuclear engineering & Radiation Health Physics
Selecting Target Organisms Dose standard
aquatic animals terrestrial plants terrestrial animals
Anything left out?
Oregon State University
Nuclear engineering & Radiation Health Physics
Screening Method Example - Plant Utilizes lumped parameter, Biv
Derives limiting soil value
Allows modification of screening limit where data on Biv available
isoilextiiniiv
planti
DCFDCFB
kgBqS
ps ,,,,
1
,
01.0
)(
Oregon State University
Nuclear engineering & Radiation Health Physics
Site Specific Screen (Fail Initial Screen) Step 1
lumped parameters too restrictive Examine and modify Bivs using general literature
Step 2 No literature values available or no benefit Begin more detailed analysis
Step 3 Secondary method Choose kinetic/allometric approach Consider site-specific parameters Re-visit estimate of internal tissue concentration Account for finite contamination Point of departure - lumped parameter values
Oregon State University
Nuclear engineering & Radiation Health Physics
Analysis Phase: Areas of Modification
inhalationingestion
external
Internalpathways are reexaminedfirst
Oregon State University
Nuclear engineering & Radiation Health Physics
Kinetic Approach, Internal Exposure
Input Rate Loss RateBody
Burden
ee TimExposureConstantRateLoss
RateLoss
RateInputBurdenBody 1
Oregon State University
Nuclear engineering & Radiation Health Physics
Body Burden Estimates
time
q
Function of: Body mass Intake rate Loss rate Exposure time
Need to address: varying mass intake exposure period
Oregon State University
Nuclear engineering & Radiation Health Physics
Useful Relationships Allometric Relationships
Y = X
Cross species relationships Empirically obtained Derived from energy/nutrient transport limitations
Mass and Metabolic Rate M3/4 (Ingestion, Inhalation) M1/4 (Life-span) aMx (biological elimination rate)
Mass and Home Range M~3/4 (Defining exposure areas)
Oregon State University
Nuclear engineering & Radiation Health Physics
Combining Kinetic & Allometric Methods
Allows prediction of body burden for any body mass lifespan loss rate
Can be tailored to specific species Stochastic analysis used to ground truth
approach and compare to “lumped” parameters
Oregon State University
Nuclear engineering & Radiation Health Physics
Pathways Included in Allometric Method
Riparian Animal TerrestrialAnimal
WaterPath
External External
Ingestion (water,food)
Ingestion (water)
Sediment External ---------Ingestion
Soil -------- ExternalIngestion (soil,food)Inhalation (soil)
Oregon State University
Nuclear engineering & Radiation Health Physics
Allometric & Kinetic Approach
isoilext
eff
iin
animallterrestriai
DCFWk
DCF
kgBqS
,,
,
1
,
001.0
)(
30.002.1
76.0
1
75.0
1
481.0
70
Wk
iv
effe
WMIT
PT
ffBWdc
a
Oregon State University
Nuclear engineering & Radiation Health Physics
Method Assessment Graded Approach provides for consistency
between screening and analysis phase Allometric predictions compared to real data
Uncertainty analysis (90th percentile?) Sensitivity Analysis
Initial results look very promising Additional analysis continuing
Oregon State University
Nuclear engineering & Radiation Health Physics
Input Parameter ValuesAssumption: Ratio of active to basal metabolic rate Cell: B7
Normal distribution with parameters:Mean 2.00Standard Dev. 0.20
Selected range is from 0.50 to 3.00Mean value in simulation was 2.00
Assumption: Fraction of energy ingested that is assimilated Cell: B8
Normal distribution with parameters:Mean 0.65Standard Dev. 0.20
Selected range is from 0.30 to 0.90Mean value in simulation was 0.62
Assumption: Caloric value of food Cell: B9
Normal distribution with parameters:Mean 5.00Standard Dev. 1.00
Selected range is from 4.00 to 9.00Mean value in simulation was 5.29
1.40 1.70 2.00 2.30 2.60
Ratio of activ e to basal metabolic rate
0.05 0.35 0.65 0.95 1.25
Fraction of energy ingested that is assi
2.00 3.50 5.00 6.50 8.00
Calor ic v alue of food
75.070Wdc
ar
Oregon State University
Nuclear engineering & Radiation Health Physics
Output Distributions
Oregon State University
Nuclear engineering & Radiation Health Physics
Electronic Spreadsheets Encodes Method
Microsoft Excel®
Visual Basic®
Undergoing Review
Oregon State University
Nuclear engineering & Radiation Health Physics
Oregon State University
Nuclear engineering & Radiation Health Physics
Oregon State University
Nuclear engineering & Radiation Health Physics
Oregon State University
Nuclear engineering & Radiation Health Physics
Oregon State University
Nuclear engineering & Radiation Health Physics
Oregon State University
Nuclear engineering & Radiation Health Physics
Oregon State University
Nuclear engineering & Radiation Health Physics
Riparian worksheet continued
Oregon State University
Nuclear engineering & Radiation Health Physics
Riparian, continued
Oregon State University
Nuclear engineering & Radiation Health Physics
Oregon State University
Nuclear engineering & Radiation Health Physics
Oregon State University
Nuclear engineering & Radiation Health Physics
Terrestrial Animals, continued
Oregon State University
Nuclear engineering & Radiation Health Physics
Terrestrial Animals, continued
Oregon State University
Nuclear engineering & Radiation Health Physics
Ongoing Issues
Multi-component retention functions Additional Nuclides Technical Accuracy Chain-Decay Nuclides (equilibrium fraction = 1) Internal Dose Factors
Radiation weighting factor for - emitters
Adjustment Factors size of contaminated zone & organism home range subsurface contamination
Oregon State University
Nuclear engineering & Radiation Health Physics
Comparisons - Sediment
A comparison of sediment BCGs
1.E+00
1.E+02
1.E+04
1.E+06
1.E+08
1.E+10
Am-241
Ce-144
Cs-135
Cs-137
Co-60
Eu-154
Eu-155
H-3I-129
I-131Pu-239
Ra-226
Ra-228
Sb-125
Sr-90Tc-99
Th-232
U-233
U-234
U-235
U-238
Zn-65
Zr-95
Nuclides
BC
G(B
q/k
g)
ORNL Sediment Benchmarks BDAC sediment BCGs
Oregon State University
Nuclear engineering & Radiation Health Physics
Comparisons - SoilA comparison of soil BCGs
1.E+00
1.E+01
1.E+02
1.E+03
1.E+04
1.E+05
1.E+06
1.E+07
Am-241
Ce-144
Cs-135
Cs-137
Co-60
Eu-154
Eu-155
H-3I-129
I-131Pu-239
Ra-226
Ra-228
Sb-125
Sr-90Tc-99
Th-232
U-233
U-234
U-235
U-238
Zn-65
Zr-95
Nuclides
BC
G(B
q/k
g)
RESRAD 15 mrem soil BDAC soil BCGs
Oregon State University
Nuclear engineering & Radiation Health Physics
Comparisons - Water
A comparison of water BCGs
1.E+00
1.E+02
1.E+04
1.E+06
1.E+08
1.E+10
Am-241
Ce-144
Cs-135
Cs-137
Co-60
Eu-154
Eu-155
H-3I-129
I-131Pu-239
Ra-226
Ra-228
Sb-125
Sr-90Tc-99
Th-232
U-233
U-234
U-235
U-238
Zn-65
Zr-95
Nuclides
BC
G(B
q/k
g)
DOE 5400l NRC Reg Guide DOE water BCGs
Oregon State University
Nuclear engineering & Radiation Health Physics
Summary & Conclusions Method undergoing QA/QC checks
reality check on lumped parameters
Additional refinement expected: data printouts more logical progression
One-year trial application
Oregon State University
Nuclear engineering & Radiation Health Physics
For further information Contact (in lieu of S. Domotor)
Kathryn Higley
541-737- 0675
Department of Nuclear Engineering
Oregon State University
Corvallis OR 97331-5902