lecture 9 Flashcards

1
Q

E/M radiation for photon E

A

> 100 ev starts in UV

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2
Q

What is the absorbed dose

A

the measure of the amount of energy from ionizing radiation deposited in a mass of some material (delta E/delta M)

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3
Q

Does the biological effect depend only on dose

A

No, it is dependent on the nature of radiation

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4
Q

Old unit of Absorbed dose

A

RAD (radiation absorbed dose) = 100 ergs/g

1 erg=10^-7 J

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5
Q

SI unit for absorbed dose

A

Gy (Gray)=1J/kg=10^7 erg/1000g=10000erg/g=100rad

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6
Q

For what type of radiation Gy is used

A

all types of radiation and does not describe the biological effects (health effects depend on how radiation interacts with material on micro-level)

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7
Q

Absorbed dose: is it a macroscopic concept

A

yes, it is not related to microdosimetry

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8
Q

Is energy delivered by radiation is continuous and uniform?

A

No, it is delivered not uniformly through the entire mass

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9
Q

Why do we care about secondary electrons?

A

They produce additional ionization and excitation until the energies fall below the threshold for further interaction

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10
Q

What paradox illustrated irradiation of viruses

A

both sensitive and highly resistant, some of them were killed at low dose. On average they tolerated very large doses: actually receiving a dose is not equal to the dose delivered, bioeffects can be very different at the same dose. Random statistical hit.

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11
Q

How many J in ev

A

1.6*10^(-19)

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12
Q

Absorbed energy depends on

A

number of particles traversing the mass and energy that they deposit in tissue

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13
Q

Main problems with the absorbed dose concept

A

neglects the density of energy absorbed per unit mass in a point in the medium,
on a small scale (micrometer) the energy distribution is non-uniform,
energy is localized near tracks,
E transfer takes place in discrete amounts,
statistical quantity gives a global value (large enough that statistical fluctuations are not significant)

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14
Q

The biological effect is related to the dose

A

deposition at micro-level (cell, DNA), depends on nature nad E of particles

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15
Q

Can we use exposure for neutrons?

A

No, only for gamma and x-rays.

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16
Q

What affects the absorbed dose?

A

type and E of Radiation, depth and elementary composition of the material.

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17
Q

How do we characterize dose from X-ray fields?

A

exposure

18
Q

What is exposure/ what unit is used?

A

amount of E transferred from the X-ray field to a unit mass of AIR. 1 [X] unit = 1C/kg air = 34 Gy/air (production of single ion pair = 34 ev)

19
Q

Charge of single ion?

A

1.6*10^(-19) C

20
Q

What unit is used for exposure (non SI)

A

R = quantity of gamma radiation that produces ions carrying one SC (3*10^9 C) per cm^3 at T=0C, and P = 760mm. [R] = 1 [sc/cm^3]

21
Q

convert 1 X unit to R

A

1 X = 3881 R

1R = 2.58*10^-4 X

22
Q

Dose to air from 1R

A

1R= 0.877 rad = 87.7 erg/g air = 8.7 *10^-4 Gy

23
Q

Formula and units for exposure rate

A

dX/dt = Fluence rate ([photones/(cm^28s) * E (Mev) 1.610^(-13) J/Mev* mu (air/cm)]/density of air34) [C/kgs]

24
Q

Formula and units for dose rate

A

dD/dt = Fluence rate ([photones/(cm^28s) * E (Mev) 1.610^(-13) J/Mev* mu (/cm)]/density of medium*1) [Gy/s]

25
Q

The formula for a point source of gamma rays Dose rate

A

dD/dt = E fluence rate* mass E abs coefficient (cm^2/g)= CE(mu.en/rho)/4Pir^2), where C is activity

26
Q

Dose rate from exposure rate can be found as

A

34Xrate mu/density if medium divided on mu/density of air

27
Q

Dose for a beam of photons

A

D = mu.en/rho * photon fluence (/cm^2) * E

28
Q

Two reactions of tissue with neutrons

A

capture (thermal) and scattering (higher E)

29
Q

Dose from thermal neutrons formula

A

D=fluence (/cm^2)*atom density (/cm^3) reaction cross sectionE /tissue density

30
Q

name major neutron capture reactions is tissue

A

14N(n, p)14c, 1H(n, gama)2H

31
Q

name 4 principal tissue components

A

H, O, C N

32
Q

Average E lost by fast neutron

A

4MmE/2(m+M)^2

33
Q

first collision dose

A

represent the abs dose when mean free path&raquo_space; target size;

D delivered by individual neutron;

34
Q

formula and units for first collision dose

A

D=atom densityscattering cross sectionAverage E lost by fast neutron/density;
[Gy*cm^2]

35
Q

What is KERMA

A

(for indirectly ionizing radiation - no charge) the measure of all the E transferred from the uncharged particle (gamma, neutron to primary ionizing particle (e, photo e, Compton e, scattered nuclei and etc) per unit mass

36
Q

Provide examples of radionuclides with specific metabolic pathways?

A

I- thyroid
Ra, Sr -bone,
3H - water in body,
Cs- throughout the whole body

37
Q

Range of alpha particle

A

short, E deposited locally

38
Q

Rate of E absorption per gram tissue for alpha particle

A

dD/dx = AE [Mev/g*s]

39
Q

Dose formula for alpha particle

A

D= fluence * mu.rho *E absorbed

40
Q

Formula for KERMA

A

D= fluence * mu.rho *E transferred

41
Q

10 MEV photon penetration in 100 g tissue

A

single interaction produces beta - and beta + with 4.5 MEV each, that dissipate all E through Brems giving us Kerma os 2*4.5Mev / 0.1kg