| Topic 7 - Dose Limits
         
          | Example calculations using internal dose conversion 
              factors |  |  |  Annual Limit on Intake
         Activity of a radionuclide, which if taken in alone, would irradiate 
          an individual to the limit set by the ICRP for each year of occupational 
          exposure Intake rate: quantity per year Pure parent assumption Can have an ALI each year No time constraint set on exposure period
             (rate can be instantaneous or up to a year) Two limits – stochastic and nonstochastic considered. 
         Secondary limit 
          
             designed to meet the basic limits for occupational exposure derived from the previous two relationships. The ALI is the greatest value of the annual intake, I, which 
              satisfies both of the following inequalities: 
   
  
         Where 
          
             I (Bq) is the annual intake of the specified radionuclide (by 
              ingestion or inhalation). 
              
                 S = stochastic limit N = nonstochastic limit HT,50 per unit intake (Sv Bq-1) is the 
              committed dose equivalent in tissue (T) from the intake of unit 
              activity of the nuclide by the specified route. 
         If Is not exceeded, then stochastic limits met If In not exceeded, then nonstochastic limits met Select value of I which satisfies both inequalities to determine 
          limiting value. Calculating an ALI inhalation- example 239 Pu intake by inhalation
         
          | Tissue | H50,T Sv Bq-1 | WT | H50,T Sv * WT |   
          | Lungs | 3.2 * 10-4 | 0.12 | 309 * 10-5 |   
          | Red Marrow | 7.6 * 10-5 | 0.12 | 9.1 * 10-6 |   
          | Bone surfaces | 9.5 * 10-4 | 0.03 | 2.9 * 10-5 |   
          | Liver | 2.1 * 10-4 | 0.06 | 1.2 * 10-4 |   
          | Sum | 8.9 * 10-5 Sv Bq-1 |  ICRP 30 Calculating ALI (stochastic)  
   Calculating ALI (nonstochastic)  
   Calculating ALI: 239Pu
         Stochastic limit 
          
         Nonstochastic limit 
          
         Uncertainites in metabolic models result in listed ALI at one significant 
          figure: 
          
         Derived Air Concentrations
         Revised version of ICRP 2 MPCair 
          
             Maximum permissible concentration (air) Old MPCs were misused.   They were maximum permissible concentrations intended 
              to control exposure over prolonged periods (> 3 mos). They have been used to infer over-exposure for even short exposure 
              times. The limit for inhalation of a radionuclide is the appropriate 
              ALI. The concentration of a radionuclide in air during any year is 
              limited as follows: That concentration of a radionuclide in air, which if breathed for 
          one working year, would result in one ALI by inhalation: 
   
             2000 hrs per working year 1.2 m3 h-1 working breathing rate Note:  ALI is the main limit and the DAC is a derived limit. DAC’s, alternate calculation
         Calculated based on annual breathing rate: 
   
             2400 m3  annual breathing rate Again Note:  ALI is the main limit and the DAC is a derived 
          limit. Use of Dose Conversion Factors
         Tables generated based on ICRP methodologies Printed by several agencies 
          
         Units may vary (SI vs standard) Methodology may vary 
          
             ICRP 2 ICRP 26/30 ICRP 60 Example to follow 50-Yr committed dose equivalent factors -- rem/ƒΚCi 
        intake: 239Pu
         
          | Class | Ingestion | Inhalation |   
          | f1 | D | W | Y |   
          | Lungs |  |  |  |  | 1.2 * 10+3* |   
          |  |  |  |  |  | 0/0/100 |   
          | Gonads | 9.6 * 10-1* | 9.6 * 10-3* |  | 1.2 * 10+2* |  |   
          |  |  |  |  | 25/33/42 |  |   
          | R Marrow | 5.9 * 100* | 5.9 * 10-2* |  | 7.4 * 10+2* | 2.8 * 10+2* |   
          |  |  |  |  | 25/33/42 | 7/2/91 |   
          | Bone Surf | 7.8 * 101* | 7.8 * 10-1* |  | 9.3 * 10+3* | 3.5 * 10+3* |   
          |  |  |  |  | 25/33/42 | 7/2/91 |   
          | Liver | 1.6 * 101* | 1.6 * 10-1* |  | 2.0 * 10+3* | 7.8 * 10+2* |   
          |  |  |  |  | 25/33/42 | 7/2/91 |   
          | ULI Wall |  | 6.3 * 10-2* |  |  |  |   
          | LLI Wall |  | 2.0 * 10-1* |  |  |  |   
          | C.E.D.E. | 4.3 * 100* | 5.8 * 10-2* |  | 5.1 * 102* | 3.3 * 102* |  * Indicates that <90% of total dose is 
        received in year of intake GI Absorption & Lung Retention
         
          | Element/Symbol | Atomic Number | Compound | f1 | Lung Retention Class |   
          | Neptunium (Np) | 93 | All forms | 1E-3 | W |   
          | Nickel (Ni) | 28 | Oxides, hydroxides | 5E-2 | W |   
          | All others (vapor) | -- | D |   
          | Niobium (Nb) | 41 | Oxides, hydroxides | 1E-2 | Y |   
          | All others | 1E-2 | W |   
          | Osmium (Os) | 76 | Oxides, hydroxides | 1E-2 | Y |   
          | Halides, nitrates | 1E-2 | W |   
          | All others | 1E-2 | D |   
          | Palladium (Pd) | 46 | Oxides, hydroxides | 5E-3 | Y |   
          | Nitrates | 5E-3 | W |   
          | All others | 5E-3 | D |   
          | Phosphorus (P) | 15 | Phosphates | 8E-1 | W or D; dependent upon associated element |   
          | Platinum (Pt) | 78 | All forms | 1E-2 | D |   
          | Plutonium (Pu) | 94 | Oxides, hydroxides | 1E-5 | Y |   
          | Nitrates | 1E-4 | W |   
          | All other (Note: Use same values for ingestion)
 | 1E-3 | W |  Class examples to work
         Show how CEDE obtained Demonstrate particle size correction   
          
         Respiratory Model
         
          | Limits for Intakes of Radionuclides by Workers |   
          |  | Class |   
          | D | W | Y |   
          | Region | Compartment | T day | F | T day | F | T day | F |   
          | N-P (DN-P = 0.30)
 | a | 0.01 | 0.5 | 0.01 | 0.1 | 0.01 | 0.01 |   
          | b | 0.01 | 0.5 | 0.40 | 0.9 | 0.40 | 0.99 |   
          | T-B (DT-B = 0.08)
 | c | 0.01 | 0.95 | 0.01 | 0.5 | 0.01 | 0.01 |   
          | d | 0.2 | 0.05 | 0.2 | 0.5 | 0.2 | 0.99 |   
          | P (DP = 0.25)
 | e | 0.5 | 0.8 | 50 | 0.15 | 500 | 0.05 |   
          | f | n.a. | n.a. | 1.0 | 0.4 | 1.0 | 0.4 |   
          | g | n.a. | n.a. | 50 | 0.4 | 500 | 0.4 |   
          | h | 0.5 | 0.2 | 50 | 0.05 | 500 | 0.15 |   
          | L | i | 0.5 | 1.0 | 50 | 1.0 | 1000 | 0.9 |   
          | j | n.a. | n.a. | n.a. | n.a. | infinity | 0.1 |   
 Fig. 5.2. Mathematical model used to describe clearance from the respiratory 
        system. The values for the removal half-times, Ta-1 and compartmental 
        fractions, Fa-1 are given in the tabular portion of the figure 
        for each of the three cleasses of retained materials. The values given 
        for DN-P, DT-B and DP (left column) are 
        the regional depositions for an aerosol with an AMAD of 1 μm. The 
        schematic drawing identifies the various clearance pathways from compartments 
        a-i in the four respiratory regions, N-P, T-B, P and L. n.a. = not applicable.
   Fig. 5.1. Deposition of dust in the respiratory system. The percentage 
        of activity or mass of an aerosol which is deposited in the N-P, T-B and 
        P regions is given in relation to the Activity Median Aerodynamic Diameter 
        (AMAD) of the aerosol distribution. The model is intended for use with 
        aerosol distributions with AMADs between 0.2 an 10 μm and with geometric 
        standard deviations of less than 4.5. Provisional estimates of deposition 
        further extending the size range are given by the dashed lines. For an 
        unusual distribution with an AMAD of greater than 20 μm, complete 
        deposition in N-P can be assumed. The model does not apply to aerosols 
        with of greater than 20 μm, complete deposition in N-P can be assumed. 
        The model does not apply to aerosols with AMADs of less than 0.1 μm. Particle Size Correction 
 Where DN-P, etc are the deposition probabilities in the respiratory region 
        for a given AMAD (see fig 5.1), and fN-P etc are the fraction of the committed 
        dose in the reference tissue arising from deposition in the N-P, T-B, 
        and P regions (see conceptual model). Tissue Weighting Factors
         
          | Tissue | ICRP26 Wt
 |   
          | Gonads | 0.25 |   
          | Breast | 0.15 |   
          | Lung | 0.12 |   
          | RBM | 0.12 |   
          | Thyroid | 0.03 |   
          | Bone Surfaces | 0.03 |   
          | Remainder* | 0.3 (0.06/tissue) |   
          | Sum Total | 1 |   
          | *To use in calculating the effective dose equlivalent, 
            calculate the dose to the remain g organs, and apply the value of 
            0.06 to the 5 most-dosed of the remainder, then throw out the rest. 
            You are then calculating the HE to include up to 11 tissues. |  
 
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