Title: ASSESSMENT OF OCCUPATIONAL EXPOSURE DUE TO INTAKE OF RADIONUCLIDES
1ASSESSMENT OF OCCUPATIONAL EXPOSURE DUE TO INTAKE
OF RADIONUCLIDES
2Biokinetic Models - Unit Outline
- Ingestion
- Entry through Wounds and Skin
- Systemic Activity
- Excretion
3Ingestion
4Ingestion - Gastrointestinal tract model
- ICRP 30 model has 4 compartments,
- Stomach,
- Small intestine,
- Upper large intestine and
- Lower large intestine
- Uptake to blood in the small intestine -
specified by fractional uptake (f1) values
5Gastrointestinal tract model ICRP 30
Transfer constant, ? 1/residence time
All tabulated values for ingestion are based on
this model
6New Human Alimentary Tract (HAT) model - ICRP
100
- ICRP 60 introduced specific risk estimates and wT
for radiation-induced cancer of the oesophagus,
stomach and colon - Dose estimates needed for each region
- ICRP 30 model
- Did not include the oral cavity or the oesophagus
- Treated the colon as two regions - upper and
lower large intestine.
7New HAT model ICRP 100 /2
- Considerable data is now available on material
transit times through the different regions of
the gut using non-invasive techniques - Information has become available on the location
of the sensitive cells and retention of
radionuclides in different regions - New data includes
- Differences between solid and liquid phases
- Age and sex related differences
- Effect of disease conditions
8New HAT model ICRP 100 /3
- Data are being used
- to determine default transit rates for the
defined regions of the alimentary tract - for the 6 age groups given in ICRP 56
- New information
- For morphometrical and physiological parameters,
- On the location of sensitive cells and in
different regions of the alimentary tract
9Anatomy and physiology of HAT
- Primary functions
- To move the food
- Digestive function
- Absorptive function
- Excretion function via liver and biliary tract.
- Additional functions
- Defensive functions to protect the body from
colonization by bacteria - Contains microbial population that produces
vitamins
10Anatomy and physiology of HAT
- Overall structure
- Detailed structure of different epitelia
- Oral cavity, pharynx, oesophagus
- Stomach, small and large intestines
- Villi and crypts structure in small intestine
11Structure of the HAT Model ICRP 100
- Deposition and retention on teeth.
- Entry per ingestion, from Respiratory Tract
- Deposition in oral mucosa or wall of the Stomach
and intestine - Transfer back from the oral mucosa or walls of ST
and intestine back in the lumen - Transfer from various secretory organs or blood
into the contents of certain segments of HAT.
12Main differences with previous model /1
- Oral cavity not present in the ICRP30 model
- In ICRP30 model the division of large intestine
is in only 2 regions ULI and LLI. (in HATM
there are 3 regions for the colonic transit) - The ICRP30 model takes into account only decays
of the radionuclide occurring during transit. In
HATM it has been taken into account also
transformations of the radionuclide due to
retention in tissues.
13Main differences with previous model /2
- In ICRP30 model absorption of a radionuclide is
supposed to occur only in Small intestine. HATM
includes pathways to account for absorption from
- Oral mucosa
- Stomach,
- Specific segment of colon
- HATM provides age- and gender-specific transit
times for all segments of the tract and for the
upper segments (oral cavity, oesophagus and
stomach) it provides also material specific
transit times.
14Transit times
- Extremely large deviation from the norm can be
found from constipation or diarrhoea, unusual
diet or pharmaceuticals which can affect the
actual transit times. - So the default transit times may not be
appropriate for individual specific applications.
- Uncertainties and variability in transit times
are reported in ICRP 100. - Within a first-order kinetics a transit time of T
days corresponds to a transfer coefficients of
1/T per day (d-1) - The review of data has been done for the transit
times of all segments of HAT.
15Transit times and tranfer coefficients for Adult
Males
ORGAN TRANSIT TIMES TRANSFER COEFFICIENTS 1/T (d-1)
Mouth Total diet 12 s Total diet 7200
Oesophagus Total diet Fast Slow 90 10 7 s 40 s Total diet Fast Slow 90 10 12343 2160
Stomach Total diet 70 min Total diet 20.57
Small Intestine 4 h 6
Right Colon 12 h 2
Left Colon 12 h 2
Recto sigmoid 12 h 2
16Absorption from content of HAT
- Even if the absorption predominantly took place
in the small intestine, provision is made for
the inclusions of components of absorption from - oral cavity,
- stomach or
- any segment of the colon.
- Absorption from any other segment of the
alimentary tract is depicted as transfer from the
contents to the wall of that segment, followed by
transfer to blood in the portal vein to entry
into the general circulation.
17Absorption from content of HAT / 2
- In the planned ICRP reports that will recommend
the use of the HATM for a range of elements,
information for each element will be given in
terms of fractional absorption, replacing the f1
values of Publication 30 (ICRP, 1979) with fA
values. - Thus, fA denotes total absorption to blood in the
HATM and represents the fraction of the material
entering the alimentary tract. - It is given by the sum of the fractions of the
material entering the alimentary tract, fi,
absorbed in all of the regions of the alimentary
tract
18Absorption from content of HAT / 3
- In the majority of cases, information will only
be available on the total absorption of the
element and its radioisotopes to blood with no
information on regional absorption. As in the
Publication 30 model the standard assumption will
be that this absorption takes place entirely from
the small intestine so fSIfA. - On the contrary if an element is known to be
absorbed from the stomach as well as from the
small intestine, values of fST and fSI would be
specified, where
19Absorption from content of HAT / 4
- For the implementation of the HATM in the absence
of absorption from retention in the walls, teeth
and oral mucosa, the following transfer
coefficient li,B applies for the uptake to blood
from compartment i of the HATM. - Where fi is the fraction of then intake assumed
to be absorbed from compartment i and li,i1 is
the transfer compartment to the next compartment
i1.
20Absorption from content of HAT / 5
- In the most common case with the absorption only
from the small intestine to the blood the
transfer coefficient is given by lSI,B is given
by - Where lSI,RC is the coefficient for transfer from
the small intestine to the right colon (6 d-1).
21Absorption from content of HAT / 6
- In the case of an absorption also from the
stomach fST, the transfer coefficient for uptake
from the stomach is given by lST,B is given by - Where lST,SI is the coefficient for transfer from
the stomach to the small intestine (20.57 d-1 for
adults and total diet). In this case case the
transfer coefficient for uptake from the small
intestine ( lSI,B ) is given by
22Dosimetry of HAT
- Geometric model for the calculation of SEE values
for the tubulus part of the HATM
23Dosimetry of HAT / 2
- Geometric model for the calculation of SEE values
for the epitelial lining of the small intestine
24Dosimetry of HAT / 3
- Depth of target cells in the different
sub-regions of the HATM, in adult male. - The target cells are always the epithelial stem
cells. - For some alpha and beta emitters this change in
respect to ICRP30 model and substantially reduced
dose estimates as the alpha or beta emissions
originating in the content of the HAT do not
penetrate the depth at which the sensitive cells
are thought to reside.
25Dosimetry of HAT / 4
- Comparison in SAF values (g-1) from ICRP 30 and
HATM for the lumen of stomach in adult male. (in
function of electron energy ).
26Dosimetry of HAT / 5
- Comparison of committed equivalent doses and
E(50) for Ru-106 and Pu-239 after ingestion,
using HATM and ICRP 30 models.
27Dosimetry of HAT / 6
- For the dose to the organ colon the mass
weighted mean of the dose coefficients of the 3
sections of the colon i.e. (this implies that the
relative risk of radiation effects is not
significantly different in these 3 regions) - For the time being no calculation has already
been performed with the HATM as the values of fA
have not been indicated by ICRP for the different
elements.
28Entry through Wounds and Skin
29Entry through wounds
- Much of the material may be retained at the wound
site, however - Soluble material can be transferred to other
parts of the body via blood - Insoluble material translocated slowly to
regional lymphatic tissue - Gradually dissolves and eventually enters the
blood - Some insoluble material can be retained at the
wound site or in lymphatic tissue for life - May need to excise contaminated tissues.
30Entry through wounds. Soluble materials
- Soluble materials may translocate from the wound
site to the blood - Translocation rate depends on solubility
- Distribution of the soluble component similar to
material entering blood from lungs or GI, however
- Some exceptions for radionuclide chemical forms
entering blood directly
31Wound model History
- In the past ICRP and NCRP both developed a
respiratory tract model in parallel - - About 10 years ago they agreed to share tasks
to develop biokinetic models - - ICRP Human Alimentary Tract Model (ICRP 100)
- - NCRP Wound Model
- - Both committees had representation from both
organisations
32Announced Biokinetic NCRP Wound Model
33The SOLUBLE Model
- 4 types of Soluble compounds have been
indicated by NCRP - Avid
- Strong
- Moderate
- Weak
- related to the persistent retention in the wound
site (chemical behavior)
34Retention at the wound site for soluble materials
35The COLLOID Model
As difference from soluble materials the grouping
of insoluble materials in wound are based on the
physical properties of the deposited material.
The three categories indicated by NCRP are
Colloid, Particle and Fragment.
36The PARTICLE Model
In this model particles with diameter less than
20 micrometers are considered
37Characteristics of the Wound Model
- Input material-specific due to its physical and
chemical state soluble, colloids, particles (
20 µm), fragments (gt 20 µm) - Soluble material
may become insoluble due to hydrolysis and vice
versa - Release from the wound site to blood
(soluble materials) and lymph nodes
(particles) - 4 retention classes for soluble
material weak, moderate, strong and avid due to
retention after 1, 16, and 64 d.
38Values of parameters in NCRP wound model
39Status of NCRP wound model
- A set of final transfer rates is given for all
7 default categories - It will be published soon
as NCRP report. - No dosimetric parameters for
wound sources. - ICRP will adopt this model the
revision of ICRP Publication 30/54/68/78 will
contain wound information.
40Entry through intact skin
- Several materials can penetrate intact skin
- Tritium labeled compounds,
- Organic carbon compounds and
- Compounds of iodine,
- A fraction of these activities enter the blood
- Specific models need to be developed to assess
doses from such intakes, e.g. behavior of
tritiated organic compounds (OBT) after direct
absorption is quite different from that after
inhalation or ingestion
41Entry through intact skin
- Both the equivalent dose to the contaminated area
and the effective dose need to be considered
after skin contamination. - ICRP biokinetic models can only be used for the
calculation of the effective dose arising from
the soluble component, once the systemic uptake
has been determined.
42Systemic Activity
43Uptake
- The fraction of an intake entering the systemic
circulation is referred to as the uptake - ICRP models for radionuclides in systemic
circulation are used to calculate dose
coefficients - Following review of data behavior of
radionuclides in the body, a number of elemental
models have been revised - Revised models were also used to calculate dose
coefficients for workers
44Revision of systemic models
- Models for several elements have been revised,
particularly to account for recycling of
radionuclides between compartments (so they are
more complicated!) - The model are more physiologically oriented, can
be applied to calculate bioassay quantities, and
evaluate dose to the general population not only
to workers. - Previously, a number of radionuclides (e.g.
239Pu) were assumed to be retained on bone
surfaces - a conservative assumption - Evidence indicates a fraction of plutonium is
buried as a result of bone growth and turnover
45Revision of systemic models/2
- Another fraction is desorbed and re-enters the
blood - Some may be re-deposited in the skeleton and
liver or be excreted - In contrast, bone volume seeking nuclides, such
as 90Sr and 226Ra, have been assumed to
instantaneously distribute in bone volume
46Revision of systemic models/3
- The process is actually progressive
- Generic models for plutonium, other actinides,
and for the alkaline earth metals have been
developed to - Allow for the known radionuclide behavior
- Account for knowledge of bone physiology
- The model for alkaline earth metals has also been
applied, with some modifications, to lead and to
uranium.
47Revision of systemic models generic model
48Non-recycling generic model
49Iodine
- Description (from ICRP 67)
- Of iodine that reaches the blood
- a fraction equal to 30 is accumulated into the
thyroid gland, - a fraction of 70 is excreted directly in urine.
- The biological half life in blood is taken as
0.25 d. - Iodide incorporated into thyroid hormones leaves
the gland with an half time of 80 d and enters
other tissues where it is retained with a
half-time of 12 d. - Most iodide (80) is subsequently released and is
available in the circulation for uptake in the
gland and urinary excretion. - The remainder (20) is excreted in faeces in
organic form.
50Iodine
ULI LLI
51Iodine
52Caesium
- Description (from ICRP 67)
- Systemic caesium is taken to be distributed
uniformly throughout all body tissues - 10 of activity is assumed to be retained with a
biological half life of 2 days (A) - 90 of activity is assumed to be retained with a
biological half life of 110 days (A) - For female the half time of compartment B is
significantly less than for males. - In some countries there is also evidence of mean
biological half time for adult males shorter than
110 d. - Urinary to faecal excretion ratio of 41 is
recommended.
53Caesium
54Caesium
55Partitioning between urine and faeces
56Skeleton
- Bone formation is made by bone-forming cells
(osteoblasts). They synthesise the organic matrix
and perform mineralisation. This results in a
hard, durable structure (not permanent). - Throughout life there is a continual modification
(remodelling) of bone by bone-resorbing cells
(osteoclasts). - Two types of bone structures
- CORTICAL BONE (Compact)
- TRABECULAR BONE (Spongy, Cancellous)
57Skeleton
- Cortical Bone
- Hard, dense bone
- Forms the outer walls of bones
- The bulk of compact bone is found in shafts of
long bones (e.g. femur) - Trabecular Bone
- Soft, spongy bone
- Forms the interior parts of flat bones and of end
long bones - It has much higher porosity than compact bone and
soft tissue content (bone marrow).
58Skeleton
- Figure related to the head of human femur (ICRP
70)
59Skeleton
- Figure of bones in humans (ICRP 70)
- Skull is about 14-15 (around 1/7) of the mass of
all bones.
60Skeleton
- Percentages of cortical and trabecular tissues in
bones (ICRP 70)
61Model for Sr, Ra and U
62Model for Sr, Ra and U/2
- Skeletal activity first deposits on bone surfaces
- Return to plasma or migrates to exchangeable bone
volume within a few days - Some activity leaves exchangeable bone volume is
assumed to return to bone surfaces - Remainder is assigned to non-exchangeable bone
volume - Gradually moves to plasma by bone resorption
63Model for Sr, Ra and U/3
- Soft tissue is represented by 3 compartments,
ST0, ST1, and ST2 - For radium and uranium, the liver is kinetically
distinct from other soft tissues - Excretion of U through the kidney and exchange of
activity between plasma and kidney tissues is
also considered
64Model for Th, Np, Pu, Am and Cm
65Model for Th, Np, Pu, Am and Cm/2
- Th and Pu retention and
- excretion data are most
- easily reproduced using
- a 2 compartment model
- Liver 2 represents
- retention with t½ gt 1 year
- Liver 1 loses a portion of its activity to the GI
tract over a relatively short period (1 year) - Liver 2 shows greater retention of Pu
66Model for Th, Np, Pu, Am and Cm/3
- Am and Cm ? Liver can
- be treated as a uniformly
- mixed pool, losing activity
- to blood and the GI tract
- with a Tb of 1 year
- Radioactive material enters Liver 1
- Part of the material is removed to the GI tract
via biliary secretion - The rest goes to blood.
Liver 1
Blood
GI tract contents
Faeces
67Model for Th, Np, Pu, Am and Cm/4
- Kidneys are assigned two compartments,
- One loses activity to urine
- Another that returns activity to blood
- Urinary bladder contents is treated as a
separate pool that receives all material destined
for urinary excretion
68Radioactive progeny
- A number of radionuclides decay to nuclides that
are themselves radioactive - It has been assumed that the decay products would
follow the biokinetics of their parents - A few exceptions made for decay products which
are isotopes of noble gases or iodine - The revised biokinetic models apply separate
systemic biokinetics to the parent and its decay
products for intakes of radioisotopes of lead,
radium, thorium and uranium.
69Excretion
70Excretion
- Urinary bladder and colon are given wT values
- Specific information is given on excretion
pathways in the urine and faeces in revised
biokinetic models for workers. - GI tract model is used to assess doses from
systemic activity lost into the faeces. - Secretion of radionuclides from the blood into
the upper large intestine is assumed (e.g. for
bone-seekers radionuclides) - A urinary bladder model has been adapted for
calculating doses to the bladder wall - l 12 d-1 6 voids / d
71References
- FOOD AND AGRICULTURE ORGANIZATION OF THE UNITED
NATIONS, INTERNATIONAL ATOMIC ENERGY AGENCY,
INTERNATIONAL LABOUR ORGANISATION, OECD NUCLEAR
ENERGY AGENCY, PAN AMERICAN HEALTH ORGANIZATION,
WORLD HEALTH ORGANIZATION, International Basic
Safety Standards for Protection against Ionizing
Radiation and for the Safety of Radiation
Sources, Safety Series No. 115, IAEA, Vienna
(1996). - INTERNATIONAL ATOMIC ENERGY AGENCY, Occupational
Radiation Protection, Safety Guide No. RS-G-1.1,
ISBN 92-0-102299-9 (1999). - INTERNATIONAL ATOMIC ENERGY AGENCY, Assessment of
Occupational Exposure Due to Intakes of
Radionuclides, Safety Guide No. RS-G-1.2, ISBN
92-0-101999-8 (1999). - INTERNATIONAL ATOMIC ENERGY AGENCY, Indirect
Methods for Assessing Intakes of Radionuclides
Causing Occupational Exposure, Safety Guide,
Safety Reports Series No. 18, ISBN 92-0-100600-4
(2002). - INTERNATIONAL ATOMIC ENERGY AGENCY,
Intercomparison and Biokinetic Model Validation
of Radionuclide Intake Assessment, Results of a
Co-ordinated Research Programme, 1996-1998,
TECDOC 1071, IAEA, Vienna (1999). - INTERNATIONAL COMMISSION ON RADIOLOGICAL
PROTECTION, Report of the Task Group on Reference
Man, ICRP Publication 23, Pergamon Press, Oxford
(1975).
72References
- INTERNATIONAL COMMISSION ON RADIOLOGICAL
PROTECTION, Limits for Intakes of Radionuclides
by Workers, ICRP Publication 30, Part 1, Annals
of the ICRP 2(3/4), Pergamon Press, Oxford
(1979). - INTERNATIONAL COMMISSION ON RADIOLOGICAL
PROTECTION, Limits for Intakes of Radionuclides
by Workers, ICRP Publication 30, Part 2, Annals
of the ICRP 4(3/4), Pergamon Press, Oxford
(1980). - INTERNATIONAL COMMISSION ON RADIOLOGICAL
PROTECTION, Limits for Intakes of Radionuclides
by Workers, ICRP Publication 30, Part 3
(including addendum to Parts 1 and 2), Annals of
the ICRP 6(2/3), Pergamon Press, Oxford (1981). - INTERNATIONAL COMMISSION ON RADIOLOGICAL
PROTECTION, Individual Monitoring for Intakes of
Radionuclides by Workers Design and
Interpretation, ICRP Publication 54, Annals of
the ICRP 19(1-3), Pergamon Press, Oxford (1988). - INTERNATIONAL COMMISSION ON RADIOLOGICAL
PROTECTION, Age-dependent Doses to Members of the
Public from Intake of Radionuclides Part 1, ICRP
Publication 56, Annals of the ICRP, 20(2),
Pergamon Press, Oxford (1989). - INTERNATIONAL COMMISSION ON RADIOLOGICAL
PROTECTION, Human Respiratory Tract Model for
Radiological Protection, ICRP Publication 66,
Annals of the ICRP 24(1-3), Elsevier Science
Ltd., Oxford (1994).
73References
- INTERNATIONAL COMMISSION ON RADIOLOGICAL
PROTECTION, Age-dependent Doses to Members of the
Public from Intake of Radionuclides Part 2,
Ingestion Dose Coefficients, ICRP Publication 67,
Annals of the ICRP 23(3/4), Elsevier Science
Ltd., Oxford (1993). - INTERNATIONAL COMMISSION ON RADIOLOGICAL
PROTECTION, Dose Coefficients for Intakes of
Radionuclides by Workers, ICRP Publication 68.
Annals of the ICRP 24(4), Elsevier Science Ltd.,
Oxford (1994). - INTERNATIONAL COMMISSION ON RADIOLOGICAL
PROTECTION, Age-dependent Doses to Members of the
Public from Intake of Radionuclides Part 3,
Ingestion Dose Coefficients, ICRP Publication 69,
Annals of the ICRP 25(1), Elsevier Science Ltd.,
Oxford (1995). - INTERNATIONAL COMMISSION ON RADIOLOGICAL
PROTECTION, Age-dependent Doses to Members of the
Public from Intake of Radionuclides Part 4,
Inhalation Dose Coefficients, ICRP Publication
71, Annals of the ICRP 25(34), Elsevier Science
Ltd., Oxford (1995). - INTERNATIONAL COMMISSION ON RADIOLOGICAL
PROTECTION, Age-dependent Doses to Members of the
Public from Intake of Radionuclides Part 5,
Compilation of Ingestion and Inhalation Dose
Coefficients, ICRP Publication 72, Annals of the
ICRP 26 (1), Pergammon Press, Oxford (1996). - INTERNATIONAL COMMISSION ON RADIOLOGICAL
PROTECTION, Individual Monitoring for Internal
Exposure of Workers Replacement of ICRP
Publication 54, ICRP Publication 78, Annals of
the ICRP 27(3-4), Pergamon Press, Oxford (1997).
74References
- INTERNATIONAL COMMISSION ON RADIOLOGICAL
PROTECTION, Guide for the Practical Application
of the ICRP Human Respiratory Tract Model, ICRP
Supporting Guidance 3 (in press). - NATIONAL COUNCIL ON RADIATION PROTECTION AND
MEASUREMENTS, Deposition, Retention and Dosimetry
of Inhaled Radioactive Substances, NCRP Report
No.125, NCRP, Bethesda (1997). - NATIONAL COUNCIL ON RADIATION PROTECTION AND
MEASUREMENTS, Evaluating the Reliability of
Biokinetic and Dosimetric Models and Parameters
Used to Assess Individual Doses for Risk
Assessment Purposes, NCRP Commentary No.15, NCRP,
Bethesda (1998).