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19/04/23 radiation safety - level 5 2
ExcercisesExcercises
Atomic and nuclear physics Sources and x-ray equipment Interaction and shielding Detection Quantities and units Radiobiology Risk of radiation Regulations Dose calculations Open sources Radioactive waste
19/04/23 radiation safety - level 5 3
Atomic and nuclear physicsAtomic and nuclear physics
1 Which particles are the building blocks of the atomic nucleus?
protons and neutrons
2 The nucleus of a copper atom contains 29 protons.How many electrons are there in the electron cloud of a neutral copper
atom?
29
3 What is meant by excitation?What is meant by ionization?
excitation = promotion of an electron to a higher energy level
ionization = removal of an electron from the electron cloud
19/04/23 radiation safety - level 5 4
Atomic and nuclear physicsAtomic and nuclear physics
4 What are isotopes ?
atoms with equal Z but different N
5 What are isomers?
atoms with equal Z and equal N
6 What do you know about the Z-value of hydrogen (1H), deuterium (2H) and tritium (3H)?
all equal Z (Z = 1)
19/04/23 radiation safety - level 5 5
Atomic and nuclear physicsAtomic and nuclear physics
7 What do you know about the N-value of hydrogen (1H), deuterium (2H) and tritium (3H)?
all different N (N = 0, 1 and 2)
8 What is the unit of activity?
becquerel (Bq)
9 How many disintegrations per second (dps) is 1 Bq?
1 dps
19/04/23 radiation safety - level 5 6
Atomic and nuclear physicsAtomic and nuclear physics
10 Would you call 1 kBq a strong or a weak source?
weak
11 Would you call 1 GBq a strong or a weak source?
strong
12 The initial activity is 100 MBq.The half-life is 24 hour.What is the activity after 1 day?
100 / 2 = 50 MBq (1 day = 24 hours)
19/04/23 radiation safety - level 5 7
Atomic and nuclear physicsAtomic and nuclear physics
13 And what is the activity after 5 days?How many percent of the initial activity is this?
100 / 32 = 3 MBq (25 = 32)
14 What is the half life?25 seconds
about 3%
19/04/23 radiation safety - level 5 8
Atomic and nuclear physicsAtomic and nuclear physics
15 How change Z, N and the mass number A during --decay?
Z = +1, N = -1, A = 0
16 How change Z, N and the mass number A during +-decay?
Z = -1, N = +1, A = 0
17 How change Z, N and the mass number A during electron capture?
Z = -1, N = +1, A = 0
19/04/23 radiation safety - level 5 9
Atomic and nuclear physicsAtomic and nuclear physics
18 How change Z, N and the mass number A during -decay?
Z = -2, N = -2, A = -4
19 How change Z, N and the mass number A during -decay?
Z = 0, N = 0, A = 0
20 How change Z, N and the mass number A during internal conversion?
Z = 0, N = 0, A = 0
19/04/23 radiation safety - level 5 10
Atomic and nuclear physicsAtomic and nuclear physics
21 Which secundary processes take place after electron capture?
emission of x-ray photons and Auger electrons
22 Which secundary processes take place after internal conversion?
emission of x-ray photons and Auger electrons
23 Which secundary process takes place after +-decay?
emission of annihilation radiation (E± = 511 keV)
19/04/23 radiation safety - level 5 11
Atomic and nuclear physicsAtomic and nuclear physics
24 The desintegration energy is 1000 keV.Can +-decay occur?
no
25 Name the decay processes.
--decay
electron capture +-decay -decay -decay
19/04/23 radiation safety - level 5 12
Atomic and nuclear physicsAtomic and nuclear physics
26 Can a nucleus show --decay as well as +-decay?
yes
27 What is annihilation?
e+ + e- 2 photons, each with an energy of 511 keV
19/04/23 radiation safety - level 5 13
Sources and x-ray equipmentSources and x-ray equipment
1 Sealed sources do or do not form a risk of internal contamination?
they do
2 Sealed sources do or do not form a risk of external irradiation?
they do
3 A Nuclear Energy Act permit is or is not required for possession of a sealed source?
it is
19/04/23 radiation safety - level 5 14
Sources and x-ray equipmentSources and x-ray equipment
4 The application of a sealed source is or is not restricted to a radionuclide laboratory?
it is not
5 A smear test on a sealed source does or does not make sense?
it does: the source might leak
6 An x-ray tube produces bremsstrahlung, or annihilation radiation, or both, or neither of them?
bremsstrahlung
19/04/23 radiation safety - level 5 15
Sources and x-ray equipmentSources and x-ray equipment
7 An x-ray tube produces bremsstrahlung, or characteristic radiation, or both, or neither of them?
both
8 The maximum bremsstrahlung energy does or does not depend on the anode voltage?
it does
9 The maximum bremsstrahlung energy does or does not depend on the anode current?
it does not
19/04/23 radiation safety - level 5 16
Sources and x-ray equipmentSources and x-ray equipment
10 The maximum bremsstrahlung energy does or does not depend on the cathode material?
it does not
11 The maximum bremsstrahlung energy does or does not depend on the anode material?
it does not
12 The maximum bremsstrahlung energy does or does not depend on the filtering?
it does not
19/04/23 radiation safety - level 5 17
Sources and x-ray equipmentSources and x-ray equipment
13 The energy of characteristic radiation does or does not depend on the anode voltage?
it does not
14 The energy of characteristic radiation does or does not depend on the anode current?
it does not
15 The energy of characteristic radiation does or does not depend on the cathode material?
it does not
19/04/23 radiation safety - level 5 18
Sources and x-ray equipmentSources and x-ray equipment
16 The energy of characteristic radiation does or does not depend on the anode material?
it does
17 The energy of characteristic radiation does or does not depend on the filtering?
it does not
18 The bremsstrahlung intensity does or does not depend on the anode voltage?
it does
19/04/23 radiation safety - level 5 19
Sources and x-ray equipmentSources and x-ray equipment
19 The bremsstrahlung intensity does or does not depend on the anode current?
it does
20 The bremsstrahlung intensity does or does not depend on the cathode material?
it does not
21 The bremsstrahlung intensity does or does not depend on the anode material?
it does
19/04/23 radiation safety - level 5 20
Sources and x-ray equipmentSources and x-ray equipment
22 The bremsstrahlung intensity does or does not depend on the filtering?
it does
23 The intensity of characteristic radiation does or does not depend on the anode voltage?
it does
24 The intensity of characteristic radiation does or does not depend on the anode current?
it does
19/04/23 radiation safety - level 5 21
Sources and x-ray equipmentSources and x-ray equipment
25 The intensity of characteristic radiation does or does not depend on the cathode material?
it does not
26 The intensity of characteristic radiation does or does not depend on the anode material?
it does
27 The intensity of characteristic radiation does or does not depend on the filtering?
it does
19/04/23 radiation safety - level 5 22
Sources and x-ray equipmentSources and x-ray equipment
28 Neutrons are effectively shielded by water, or paraffin, or concrete, or any of these materials?
any
29 Neutrons are effectively shielded by paraffin, or lead, or both, or none of these materials?
paraffin
19/04/23 radiation safety - level 5 23
Interaction and shieldingInteraction and shielding
1 The range of 5 MeV -particles in air is about• 0.3 mm• 3 mm• 3 cm• 3 m
3 cm
2 The range of 1 MeV -particles in air is about• 0.4 mm• 4 mm• 4 cm• 4 m
4 m
19/04/23 radiation safety - level 5 24
Interaction and shieldingInteraction and shielding
3 The range of 5 MeV -particles in tissue is about• 3 m• 30 m• 0.3 mm• 3 mm
3 cm / 1000 = 30 µmbecause the density of tissue is 1000 times larger than the density of air
4 The range of 1 MeV -particles in tissue is about• 0.4 mm• 4 mm• 4 cm• 4 m
4 m / 1000 = 4 mmbecause the density of tissue is 1000 times larger than the density of air
19/04/23 radiation safety - level 5 25
Interaction and shieldingInteraction and shielding
5 What is the photo-electric effect?
ionization due to absorption of a photon
6 What is the Compton-effect?
scattering of a photon by an electrons
7 What is pair formation?
e+ + e-
19/04/23 radiation safety - level 5 26
Interaction and shieldingInteraction and shielding
8 Which secundary processes take place after photo-electric effect?
emission of x-ray photons and Auger electrons
9 Which secundary processes take place after pair formation?
emission of annihilation photons (511 keV)
10 Which material would you choose to shield -radiation?
no shielding needed (range is too small)
19/04/23 radiation safety - level 5 27
Interaction and shieldingInteraction and shielding
11 Which material would you choose to shield --radiation?
plastic (small Z-value to avoid bremsstrahlung)
12 Which material would you choose to shield +-radiation?
plastic + additional lead (to shield 511 keV annihilation photons)
13 Which material would you choose to shield -radiation?
lead (or concrete)
19/04/23 radiation safety - level 5 28
Interaction and shieldingInteraction and shielding
14 Which material would you choose to shield Auger electrons?
no shielding needed (range is too small)
15 The maximum range in water of the -particles emitted by 32P is 0.8 cm. What is the maximum range in air?
about 1000 0.8 cm = 800 cm = 8 m
19/04/23 radiation safety - level 5 29
Interaction and shieldingInteraction and shielding
16 What is the half-value thickness of lead for the -radiation emitted by• 131I• 137Cs• 60Co• 123Sb• 24Na
0.2 cm0.6 cm1.3 cm1.3 cm1.7 cm
17 Why is the transmission curve for 198Au not a straight line?
because -photons with different energies are emitted(284 keV, 364 keV and 637 keV)
19/04/23 radiation safety - level 5 30
Interaction and shieldingInteraction and shielding
18 The half-value thickness for shielding -radiation is 1 cm.How much shielding material is needed to reduce the radiation level to 3% of
the initial value?
5 × 1 = 5 cm (3% = 1 / 25 = 1 / 32)
19 The linear attenuation coefficient for shielding -straling is 1 cm-1.How much shielding material is needed to reduce the radiation level to
3% of the initial value?
5 × (0.7 / 1) = 3.5 cm (d½ = 0.7 / µ)
19/04/23 radiation safety - level 5 31
Interaction and shieldingInteraction and shielding
20 When shielding -radiation, the build-up factor of concrete is larger or smaller than the build-up factor of lead?
larger
19/04/23 radiation safety - level 5 32
DetectionDetection
1 The voltage over an ionization chamber is relatively low or relatively high?
relatively low
2 The voltage over a proportional counter is relatively low or relatively high?
neither low nor high, but in the intermediate region
3 The voltage over a Geiger-Müller counter is relatively low or relatively high?
relatively high
19/04/23 radiation safety - level 5 33
DetectionDetection
4 A gas-filled ionization chamber can or can not measure radiation energies?
it can not (signals too small)
5 A proportional counter can or can not measure radiation energies?
it can
6 A Geiger-Müller counter can or can not measure radiation energies?
it can not (all signals are equal)
19/04/23 radiation safety - level 5 34
DetectionDetection
7 Which material is more suited to detect γ-radiation: Si (Z=14) or Ge (Z=32)?
Ge (because of larger photo-electric effect)
8 Which material is more suited to detect β-radiation: Si (Z=14) or Ge (Z=32)?
Si (small photo-electric effect, therefore less sensitive to background -radiation)
9 A Ge-detector is a scintillation detector or an ionization chamber?
ionization chamber
19/04/23 radiation safety - level 5 35
DetectionDetection
10 TLD is a scintillation detector or an ionization chamber?
scintillation detector
11 Why must scintillation material be transparant?
scintillation light must be able to escape from the detector material and reach the photocathode of the photomultiplier tube
12 A scintillation detector can or can not measure radiation energies?
it can
19/04/23 radiation safety - level 5 36
DetectionDetection
13 A source with an activity of 400 kBq gives rise to a count rate of 100 counts per second (cps). What is the counting efficiency?
100 / 400103 = 0.025%
14 Which detector would you use to identify low-energy (20 keV) -radiation?
proportional counter or NaI(Tl) with a thin window
15 Which detector would you use to identify high-energy (2 MeV) -radiation?
NaI(Tl) or Ge-detector
19/04/23 radiation safety - level 5 37
DetectionDetection
16 Which detector would you use to identify low-energy (20 keV) -radiation?
liquid scintillator, proportional counter or plastic scintillator
17 Which detector would you use to identify high-energy (2 MeV) -radiation?
liquid scintillator, plastic scintillator or Si-detector
18 Which detector is commonly used as dose rate monitor?
Geiger-Müller counter
19/04/23 radiation safety - level 5 38
DetectionDetection
19 Which detector is extremely well suited to measure a contamination with a soft (20 keV) ‑emitter?
large-area proportional counter or NaI(Tl) with a thin window
20 Which detector is extremely well suited to measure a contamination with a hard (2 MeV) ‑emitter?
NaI(Tl) or Ge-detector combined with smear test
21 Which detector is extremely well suited to measure a contamination with a soft (100 keV) -emitter?
Geiger-Müller counter with a thin window (not for tritium) or liquid scintillator combined with smear test
19/04/23 radiation safety - level 5 39
DetectionDetection
22 Which detector is extremely well suited to measure a contamination with a hard (1 MeV) ‑emitter?
Geiger-Müller counter or proportional counter with a thin window or liquid scintillator combined with smear test
23 Which quantity is usually measured with a TLD-detector?
equivalent dose
19/04/23 radiation safety - level 5 40
Quantities and unitsQuantities and units
1 What is the unit for activity?What is the symbol of this unit?
bequerel
2 What is the unit for exposure?What is the symbol of this unit?
Bq
röntgen
R
19/04/23 radiation safety - level 5 41
Quantities and unitsQuantities and units
3 What is the unit for absorbed dose?What is the symbol of this unit?
gray
4 What is the unit for equivalent dose?What is the symbol of this unit?
Gy
sievert
Sv
19/04/23 radiation safety - level 5 42
Quantities and unitsQuantities and units
5 What is the unit for effective dose?What is the symbol of this unit?
sievert
6 What is the unit for commited dose?What is the symbol of this unit?
Sv
sievert
Sv
19/04/23 radiation safety - level 5 43
Quantities and unitsQuantities and units
7 Which quantity is expressed in becquerel (Bq)?What is the symbol of this quantity?
activity
8 Which quantity is expressed in röntgen (R)?What is the symbol of this quantity?
A
exposure
X
19/04/23 radiation safety - level 5 44
Quantities and unitsQuantities and units
9 Which quantity is expressed in gray (Gy)?What is the symbol of this quantity?
absorbed dose
10 Which quantity is expressed in sievert (Sv)?What is the symbol of this quantity?
D
equivalent dose, effective dose and committed dose
HT, E en E(50)
19/04/23 radiation safety - level 5 45
Quantities and unitsQuantities and units
11 The radiation weighting factor wR for -radiation is• 1• 5• 20• 100
20
12 The radiation weighting factor wR for -radiation is• 1• 5• 20• 100
1
19/04/23 radiation safety - level 5 46
Quantities and unitsQuantities and units
13 The radiation weighting factor wR for - radiation is• 1• 5• 20• 100
1
14 What is the equivalent dose, if the absorbed dose is 1 mGy and the radiation weighting factor is wR = 20?
20 1 = 20 mSv
19/04/23 radiation safety - level 5 47
Quantities and unitsQuantities and units
15 The tissue weighting factor for the thyroid is wT = 0.05.The equivalent dose in the thyroid is 2 Sv.What is the effective dose?
0.05 2 = 0.10 Sv = 100 mSv
16 Is this peanuts or a lot?
a lot
17 Is 1 Sv a large or a small effective dose?
a very large dose (50 annual dose limit)
19/04/23 radiation safety - level 5 48
Quantities and unitsQuantities and units
18 Is 1 Sv/h a large or a small equivalent dose rate?
small equivalent dose rate(maximum effective dose = 2000 1 = 2000 μSv = 2 mSv per year)
19 A large value of e(50) means a large or a small radiotoxicity?
large radiotoxicity
20 The value of the effective dose coefficient does or does not depend on the radionuclide?
it does
19/04/23 radiation safety - level 5 49
Quantities and unitsQuantities and units
21 The value of the effective dose coefficient does or does not depend on the chemical composition of the radioactive substance?
it does
22 The value of the effective dose coefficient does or does not depend on the contamination route?
it does
19/04/23 radiation safety - level 5 50
RadiobiologyRadiobiology
1 Damage produced by ionizing radiation is mainly due to direct breaks of biomolecules or to ionization of water molecules?
ionization of water molecules
2 Which cells are most sensitive to radiation?
frequently dividing cells
3 Which cells are least sensitive to radiation?
cells that do not divide anymore
19/04/23 radiation safety - level 5 51
RadiobiologyRadiobiology
4 What happens if the unborn embryo is irradiated during the first week of the pregnancy?
either nothing or the embryo dies
5 Is it possible that malformed organs develop if the unborn embryo is irradiated during the first week of the pregnancy?
no
6 Is it possible that malformed organs develop if the unborn embryo is irradiated during the second month of the pregnancy?
yes, during this period the organs are formed
19/04/23 radiation safety - level 5 52
RadiobiologyRadiobiology
7 Is it possible that malformed organs develop if the unborn foetus is irradiated during the second half of the pregnancy?
no, organ formation is completed
8 What might happen if the unborn foetus is irradiated during the second half of the pregnancy?
growth retardation
9 Is there a threshhold dose for stochastic effects?
no
no
10 Is the severity of a stochastic effect dose dependend?
19/04/23 radiation safety - level 5 53
RadiobiologyRadiobiology
11 Is there a threshhold dose for harmful tissue reactions?
yes
12 Is the severity of harmful tissue reactions dose dependend?
yes
13 Leukemia is a stochastic effect or a harmful tissue reaction?
stochastic effect
harmful tissue reaction
14 Cataract is a stochastic effect or a harmful tissue reactions?
19/04/23 radiation safety - level 5 54
RadiobiologyRadiobiology
15 After a total-body irradiation dies half of the irradiated persons if the effective dose is about• 0.4 Sv• 4 Sv• 40 Sv
4 Sv
16 After a total-body irradiation to an effective dose of 4 Sv there is a 50% chance to die because of damage to the• bone marrow• gastro-intestinal tract• nervous system
the bone marrow
19/04/23 radiation safety - level 5 55
RadiobiologyRadiobiology
17 After a total-body irradiation to an effective dose of 10 Sv there is a 50% chance to die because of damage to the• bone marrow• gastro-intestinal tract• nervous system
the gastro-intestinal tract or, at survival, the bone marrow
18 After a total-body irradiation to an effective dose of 50 Sv there is a 50% chance to die because of damage to the• bone marrow• gastro-intestinal tract• nervous system
nervous system
19/04/23 radiation safety - level 5 56
RadiobiologyRadiobiology
19 What is the risk factor for stochastic effects after exposure to ionizing radiation?
5% per sievert
19/04/23 radiation safety - level 5 57
Risk of radiationRisk of radiation
1 What is meant by:the risk factor for stochastic effects is 0.05 per sievert?
if a million people are exposed to 1 Sv, about 0.05 1 000 000 = 50 000 of them will eventually die
2 The annual natural radiation background in The Nederlands is approximately• 2 µSv per year• 20 µSv per year• 2 mSv per year• 20 mSv per year
2 mSv per year
19/04/23 radiation safety - level 5 58
Risk of radiationRisk of radiation
3 The annual dose limit for exposed workers is• 2 µSv per year • 20 µSv per year• 2 mSv per year• 20 mSv per year
20 mSv per year
4 The annual dose limit for normal workers is• 0 mSv per year • 0.1 mSv per year• 1 mSv per year• 20 mSv per year
1 mSv per year
19/04/23 radiation safety - level 5 59
Risk of radiationRisk of radiation
5 Regular exposure to the dose limit of 20 mSv per year is a relatively small or a relatively high occupational hazard?
(very) high hazard
6 The risk factor for ionizing radiation is 0.05 per Sv.The average annual dose is about 2 mSv.Nearly 17 million people live in The Netherlands.How many persons will die each year due to ionizing radiation?
17 000 000 0.002 0.05 = 1700(each year about 44 000 people die of cancer!)
19/04/23 radiation safety - level 5 60
Risk of radiationRisk of radiation
7 What is wrong with this newspaper clipping, and why?
the boy is at least 4 years old and was already born at the moment of the Chernobyl accidentthe malformations must be due to something else
A Chernobyl victim one yearafter the nuclear disaster.
19/04/23 radiation safety - level 5 61
RegulationsRegulations
1 The ICRP is an• independent committee of experts • advisory board of the Dutch government • advisory board of the American government • advisory board of the European Community
an independent committee of experts
2 Radiological workers must comply with the• dose limits• ALARA principle• principle of justification• all these principles
with all principles
19/04/23 radiation safety - level 5 62
RegulationsRegulations
3 The ALARA principle means that the effective dose must be • as low as reasonably achievable • zero• less than 2 mSv per year• less than 20 mSv per year
as low as reasonably achievable
4 The annual effective dose limit for an exposed worker is• 2 Sv• 20 Sv• 2 mSv• 20 mSv
20 mSv
19/04/23 radiation safety - level 5 63
RegulationsRegulations
5 The annual dose limit for the lens of the eye of an exposed worker is• 2 mSv• 20 mSv• 150 mSv• 500 mSv
150 mSv
6 The annual dose limit for hands, feet and skin of an exposed worker is• 2 mSv• 20 mSv• 150 mSv• 500 mSv
500 mSv
19/04/23 radiation safety - level 5 64
RegulationsRegulations
7 The tissue weighting factor for the gonads is 0.20.The maximum permittable annual gonade dose is
• 4 mSv• 20 mSv• 100 mSv• 500 mSv
20 / 0.20 = 100 mSv
8 Radiological workers must comply with the• Nuclear Energy Act• Working Conditions Act• Environmental Management Act• all of them
all of them
19/04/23 radiation safety - level 5 65
RegulationsRegulations
9 The Decree Transport of Fissile Materials, Ores and Radioactive Substances is a• recommendation of the ICRP • Decree under the Nuclear Energy Act • Decree under the Working Conditions Act • none of these
Decree under the Nuclear Energy Act
10 The Decree Radiation Protection is a• recommendation of the ICRP • Decree under the Nuclear Energy Act • Decree under the Working Conditions Act • none of these
Decree under the Nuclear Energy Act
19/04/23 radiation safety - level 5 66
RegulationsRegulations
11 Is a Nuclear Energy Act permit needed if the activity concentration is lower, but the total activity is larger than the exemption level?
no
12 Is a Nuclear Energy Act permit needed if the activity concentration is larger, but the total activity is lower than the exemption level?
no
13 No Nuclear Energy Act permit is required if and only if both the activity concentration and the total activity are below the exemption level. This is true or not true?
not true: it is either-or
19/04/23 radiation safety - level 5 67
RegulationsRegulations
14 The annual effective dose limit for an exposed A worker is• 1 mSv• 2 mSv• 6 mSv• 20 mSv
20 mSv
15 The annual effective dose limit for an exposed B worker is• 1 mSv• 2 mSv• 6 mSv• 20 mSv
6 mSv
19/04/23 radiation safety - level 5 68
RegulationsRegulations
16 The annual effective dose limit for a normal worker is• 0 mSv• 0.1 mSv• 1 mSv• 2 mSv
1 mSv
17 An area in which the annual effective dose is larger than 1 mSv but smaller than 6 mSv, must be qualified as controlled area ("gecontroleerde zone") or supervised area ("bewaakte zone")?
supervised erea
19/04/23 radiation safety - level 5 69
RegulationsRegulations
18 An area in which the annual effective dose is larger than 6 mSv must be qualified as controlled area ("gecontroleerde zone") or supervised area ("bewaakte zone")?
controlled erea
the next three questions are only for level 5A:
19 Is a permit needed for x-ray equipment with a maximum anode voltage of more than 100 kV?
yes
19/04/23 radiation safety - level 5 70
RegulationsRegulations
20 Is a permit needed for x-ray equipment that is used for medical radiotherapy?
yes
21 Is a permit needed for x-ray equipment that is used for teaching?
yes
19/04/23 radiation safety - level 5 71
Dose calculationsDose calculations
1 How many working hours are there in a standard working day?
8 hours
2 How many working hours are there in a standard working week?
5 8 = 40 hours
3 How many working hours are there in a standard working year?
50 40 = 2000 hours
19/04/23 radiation safety - level 5 72
Dose calculationsDose calculations
4 The received dose is reduced by working faster or slower? faster
5 The received dose is reduced by increasing or decreasing the working distance?
increasing
6 The received dose is reduced by applying more or less shielding?
more shielding
19/04/23 radiation safety - level 5 73
Dose calculationsDose calculations
7 The dose rate is reduced by working faster or slower?
makes no difference
8 The dose rate is reduced by increasing or decreasing the working distance?
increasing
9 The dose rate is reduced by applying more or less shielding?
more shielding
19/04/23 radiation safety - level 5 74
Dose calculationsDose calculations
10 The dose rate is 2 mGy/h.The received dose in a standard working week is
• 16 mGy• 16 mSv• 80 mGy• 80 mSv
40 2 = 80 mGy
11 The dose rate at 1 m is 1 mGy/h.The dose rate at 10 cm is
• 0.01 mGy/h• 0.1 mGy/h• 10 mGy/h• 100 mGy/h
(100 / 10)2 1 = 100 mGy
19/04/23 radiation safety - level 5 75
Dose calculationsDose calculations
12 The received dose can be reduced by working twice as fast or by doubling the working distance. What is the best option?
Why?
doubling the working distance
13 The received dose can be reduced by working four times as fast or
by doubling the working distance. What is the best option?Why?
inverse square law
doubling the working distance
never rush
19/04/23 radiation safety - level 5 76
Dose calculationsDose calculations
14 The source constant for 60Co is Γ = 3.610-13 Gy m2 Bq-1 h-1.What is the dose received in 1 hour at 1 m from a source of 40 MBq?
3.610-13 40106 1 / 12 = 1410‑6 Sv = 14 µGy
15 What is the dose received in 1 standard working year?
2000 14 = 28103 µSv = 28 mGy
16 According to the granted Nuclear Energy Act permit, an accelerator must automatically shut down if the quivalent dose rate in the hal is 1 Sv/h. What is the maximum annual effective dose that workers in the hal may receive?
2000 1 = 2000 Sv = 2 mSv
19/04/23 radiation safety - level 5 77
Dose calculationsDose calculations
17 A -source gives rise to a much larger or a much smaller skin dose than a γ-source with the same activity at the same distance and within the same period of time?
much larger
the next four questions are only for level 5B:
18 Is the biggest risk of internal contamination due to the occasional uptake of a large amount of activity or to the regular uptake of small amounts of activity?
the regular uptake of small amounts of activity
19/04/23 radiation safety - level 5 78
Dose calculationsDose calculations
19 A drum filled with mud containing an amount of activity that is 10 time the exemption level is or is not a direct risk of internal contamination?
is not (it is impossible to ingest or inhale that much mud)
20 Ingestion of activity is or is not more risky than inhalation?
can't say: it all depends on the radionuclide and the chemical composition
21 It is or is not true that activy can penetrate skin and gloves?
true
19/04/23 radiation safety - level 5 79
Open sourcesOpen sources
the next seven questions only for level 5B:
1 The design requirements for a B-type laboratory are more strict or less strict than for a C-type laboratory?
more strict
2 The maximum allowed activity in a B-type laboratory is larger or smaller than that in a C-type laboratory?
larger
19/04/23 radiation safety - level 5 80
Open sourcesOpen sources
3 The maximum allowed activity in a D-type laboratory is larger or smaller than that in a C-type laboratory?
smaller
4 Specific requirements in the Nuclear Energy Act permit do or do not prevail over general requirements in the Guideline for Radionuclide Laboratories ("Richtlijn Radionucliden laboratoria")?
the most restrictive requirement prevails
19/04/23 radiation safety - level 5 81
Open sourcesOpen sources
5 Is pipetting of 50 MBq allowed outside the fume hood, in a C-type laboratory?
yes (p = -1, q = 2, r = 0)
6 Is boiling of 50 MBq until dryness allowed inside a fume hood that complies with NEN-EN 14175, in a B-type laboratory?
allowed (p = -4, q = 3, r = 2)
7 Is breaking of a quartz tube containing 500 MBq powder and subsequent transfer of the powder into a glass beaker allowed inside a glove box, in a B‑type laboratory?
allowed (p = -4, q = 3, r = 3)
effective dosiscoefficient is e(50)inh = 2,9×10-9 Sv/Bqsee also p,q,r-table
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Open sourcesOpen sources
p phase of material / type of work
-4 simple work with gasesmixing or grinding powdersliquid close to boiling pointhighly splashing activities
-3 labelling with volatile nuclide (3H, iodine)storage of gas in a dispensersimple work with enclosed powdersboiling of enclosed liquidscentrifugation, mixing on a vortex
-2 simple chemical manipulations (RIA)labelling with non-volatile nuclide
-1 elution of a Tc-generatorlabelling or other work in a closed systemlabelling of non-dispersible compoundspulling up a syringe
q laboratory class
0 outside the radionuclide-laboratory
1 D-laboratory
2 C-laboratory
3 B-laboratory
r local ventilation
0 outside fume hood
1 fume hood (not NEN-EN 14175)
2 fume hood (NEN-EN 14175)laminar flow cabinet (safety class 2)
3 air-flow isolator (safety class 3)glove box
back
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Radioactive wasteRadioactive waste
the next eleven questions only for level 5B:
1 A surface area is considered to be contaminated if the activity is• 1 Bq/cm2 • 4 Bq/cm2
• 4 Bq/m2
• 100 Bq/m2
4 Bq/cm2 (according to the "Richtlijn Radionucliden laboratoria")
2 Must waste be treated as radioactive waste if the activity concentration is below the exemption level?
no
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Radioactive wasteRadioactive waste
3 Must waste be treated as radioactive waste if the total activity is below the exemption level?
no
4 In order to dispose of waste as normal industrial waste, both the activity concentration and the total activity must be below the exemption level. Is this true or not true?
not true: it is either-or
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Radioactive wasteRadioactive waste
5 Radioactive waste must be• disposed of as industrial waste• disposed of dangerous industrial waste • disposed of chemical waste • handed over to COVRA
handed over to COVRA
6 Labels with the text "radioactive material" must be put in the• regular waste bin• blue box for environmental waste• bin for industrial waste• bin for radioactive waste
bin for radioactive waste
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7 May objects with a surface contamination of less than 4 Bq/cm2 be disposed of as industrial waste?
yes
8 May the contents of a counting vial always be discharged in the sink?
no (never throw chemical waste into the sink)
9 May the contents of a counting vial always be disposed of as chemical waste?
no (if activity concentration and total activity are both above the exemption level, the waste must be handed over to COVRA)