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The initial needs of the Brazilian Government following the discovery of the Goiania accident

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that had been done in Bikini in 1954. ... Bikini Atoll. Fishing vessel, from ... Dose estimate based on ICRP models. Low level. of internal. contamination ... – PowerPoint PPT presentation

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Title: The initial needs of the Brazilian Government following the discovery of the Goiania accident


1

ASSESSMENT OF OCCUPATIONAL EXPOSURE DUE TO
INTAKES OF RADIONUCLIDES
Assessment of Internal Exposure following
Accidents or Incidents
2
Assessment of Internal Exposure following
Accidents or Incidents Unit Outline
  • Introduction
  • Post Event Information Requirements
  • Post Event Monitoring
  • Follow-up Monitoring

3
Introduction
4
Accident
  • Any unintended event, including operating
    errors, equipment failures or other mishaps, the
    consequences or potential consequences of which
    are not negligible from the point of view of
    protection or safety.
  • BSS Glossary

5
IAEA Accident response experience
  • Under the 1986 Convention on Assistance in the
    Case of a Nuclear Accident or Radiological
    Emergency, the IAEA
  • makes available appropriate resources for
    emergency response,
  • promptly transmits requests for assistance to
    other States or international organizations which
    may possess necessary resources, and
  • may co-ordinate assistance at the international
    level

6
IAEA Accident response experience
  • Chernobyl was the most serious accident in Agency
    history.
  • IAEA has been involved in investigation of a
    number of other accidents involving.
  • loss of control or misuse of radioactive sources,
  • errors in medical treatment, or
  • accidental exposure in irradiation facilities.

7
  • Several situations contribute to accidents
  • Operational error or equipment failure when
    transferring large sources
  • Interlock failure on high dose rate equipment
  • Radiography sources left unshielded
  • Equipment failure or operational errors in
    nuclear facilities.
  • Medical misuse of sources and
  • Criticalities

8
Accidents with clinical consequences
  • Persons
  • Activity affected
  • Nuclear fuel cycle 245
  • Industrial uses of radiation 94
  • Medical uses of radiation 18
  • Tertiary education and accelerators 19
  • Other 344
  • Total 720
  • From 2000 UNSCEAR Report (1975 through 1994)

9
Post Event Information Requirements
10
Introduction
  • There will be situations involving the use of
    radioactive material in which the operational
    controls break down
  • Accidents or incidents may result in releases of
    radioactive materials into the working
    environment with the potential for high doses to
    the workforce

11
Accidents Medical treatment first
  • After an accident, the radiological consequences
    may be complicated by trauma or other health
    effects incurred by workers
  • Treatment of injuries, especially those that are
    potentially life threatening, generally takes
    priority over radiological operations
  • Post-accident exposure assessment should be
    conducted when the situation has been brought
    under control.

12
Post-accident Gather key information
  • When exposure assessment starts, get as much
    information as possible
  • Example - information is needed on
  • Time and nature of the incident
  • Radionuclides involved
  • Timing of bioassay samples and
  • Measurements of body activity

13
Post-accident Gather key information
  • Information is necessary for
  • Exposure assessment
  • Medical assessment, to guide medical treatment of
    the victim (which may include chelation therapy
    or wound excision)
  • Accident reconstruction
  • Long term medical follow-up of victims

Debridement
14
Internal decontamination
Soon after ingestion
gastric irrigation
Nuclides which are hardly absorbed by
gastrointestinal tract
cathartic
Na?K?FWT
diuretic
FWT
volume water intake
Cs, Rb
Prussian blue?depress reabsoption by small
intestine
I
potassium iodide ? depress absoption by thyroid
Pb, Cu, Zn?Cd, Cr, Mn, Ni
EDTA ? chelator
Actinides
DTPA ? chelator (Ca-DTPA Zn-DTPA)
approx.10 times
15
Debridement
This treatment is seldom done for decontamination
recently
16
Dose reconstruction
X-ray tube
FOV
Distance from the tube
Pattern ?
Analysis of the behavior pattern
Pattern ?
Pattern ?
Measurement of the dose with the same condition
as the accident
Pattern ?
17
Detectors for dose reconstruction
For low energy and high dose rate
5KeV-1.3MeV (Al deposited PET window 3.6µm)
For general energy and low dose rate
25KeV-50MeV (POM window 1mm)
30KeV-50MeV (POM window 1mm)
30KeV-50MeV (PMMA window 1mm)
18
Measurement devices for dose reconstruction
Reference hygrometer, barometer and thermometer
Reference ampere meter
hygrometer, barometer and thermometer
19
24Na analysis by Ge detector
to estimate thermal neutron flux
23Na(100) 0.531barn 41K(6.73) 1.46barn
20
Long term medical follow-up
23 crews of No.5 Fukuryu-maru were exposed by
the nuclear test that had been done in Bikini in
1954 . The purpose of this investigation is to
examine these victims' health conditions for a
long term,and to research the delayed effect. The
exposure type was a mixture exposure and the
estimated dose was 1.7-6.0Gy. 11 survivors are
having their physical condition examined once a
year .
Fishing vessel, from which radioactivity was
detected Fishing vessel and the fish, from which
radioactivity was detected
Bikini Atoll
21
Long term medical follow-up
The contrast medium "Thorotrast" of which the
principal ingredient was the thorium dioxide was
used for the angiography in Japan from 1932 to
1945. The number is estimated to be 10,000-20,000
people. Thorotrast deposits mainly on the liver
and the spleen, then causes the internal
exposure for a long term. The purpose of this
investigation is to clarify the relation between
the deposition amount of Th- 232 and the clinical
conditions and also to clarify the influence to
human body by a long-term internal exposure. The
medical examination is done once a year.
Thorotrast
Abdomen image by radiography
22
Post-accident information gathering
  • Accidents or incidents can result in high
    committed effective doses (? dose limits)
  • Individual and material specific data are
    normally needed for exposure assessment
  • Necessary data include information on
  • Chemical and physical forms of the
    radionuclide(s)
  • Particle size
  • Airborne concentrations

23
Post-accident information gathering
  • Necessary data also includes information on
  • Surface contamination levels
  • Retention characteristics in the individual
    affected
  • Nose blows, face wipes and other skin
    contamination levels and
  • External dosimetry results

24
Post-accident information gathering
  • Data may seem inconsistent or contradictory,
    particularly if the intake period is uncertain
  • Adequate dose assessments can be made only after
  • Considering all of the data
  • Resolving the sources of inconsistency as far as
    is possible, and
  • Deciding most likely and worst scenarios for
    exposure and magnitude of intake

25
Post Event Monitoring
26
Recommended procedures for monitoring
NO
Later actions (see below)
27
External contamination interference
  • Radiological characteristics of the radionuclides
    determine whether direct, indirect, or both
    methods should be used
  • If there is external contamination with gamma
    emitters, direct measurements should normally be
    delayed until decontamination
  • This 1) prevents interference with the
    measurement and 2) avoids contamination of the
    direct measurement facility

28
External contamination interference
  • If urgency of assessment precludes complete
    decontamination, wrap the individual in a sheet
    to minimize contamination of the facility
  • Such initial direct measurement results are upper
    limits for the body content
  • More measurements would be needed after further
    decontamination
  • External a or ß contamination wont normally
    interfere with direct measurements, unless
    bremsstrahlung is produced by the betas

29
Other concerns
  • External contamination will not interfere with
    indirect methods
  • However, care must be taken to avoid transfer of
    contamination to excreta samples
  • Rarely, intakes may be so high that special
    techniques to avoid interference with equipment
    response, e.g. excessive electronic dead times

30
Mobile Direct Measurement Facilities
31
Mobile Direct Measurement Facilities
32
Analysis of excreta
  • Analyses of samples of urine and faeces should be
    considered to verify the intake
  • These results may be difficult to interpret,
    because of
  • Possible multiple routes of intake and
  • Imprecise about radionuclide transfer to the blood

33
Analysis of excreta
  • Early excreta results are generally not useful
    for intake assessment because of the delay
    between intake and excretion
  • Particularly true for faecal excretion
  • In addition, rapid early components of urinary
    excretion can be difficult to interpret - not
    fully defined in some models

34
Analysis of excreta
  • Nevertheless, all excreta should be collected
    following an accident or incident
  • Early detection of radioactivity in urine can be
    a useful indication of the material solubility
    and potential for effective treatment
  • Excreta analyses can be the only reliable method
    of assessing intakes if large amounts of external
    contamination interfere with direct measurements.

35
Blood sampling
  • Emphasize non-invasive procedures. Invasive
    procedures such as blood sampling are usually
    justified only in accident situations in which
    large intakes may have occurred
  • Blood sampling can provide data on the solubility
    and biokinetics
  • Has limited value for quantitative intake
    estimates because of rapid clearance of most
    radionuclides to other tissues

36
Workplace monitoring samples
  • Workplace monitoring samples, e.g.
  • Air filters
  • Surface contamination wipes,
  • Should be analysed to determine
  • Radionuclides involved
  • Isotopic ratios, and
  • Physicochemical characteristics

37
Follow-up Monitoring
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