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Radiology Biology & Protection > Chapter 4: Radiation Quantities and Units > Flashcards

Chapter 4: Radiation Quantities and Units Flashcards

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AP® Biology flashcards Biology 101 flashcards
1
Q

who discovered xrays

A

wilhelm conrad roentgen

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2
Q

when was xrays discovered

A

November 8, 1895

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3
Q

with what was xrays discovered

A

with crookes tube

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3
Q

First xray image

A

roentgens wifes hand

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4
Q

who was the first fatality

A

Clarence Dally thomas edison assistant

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5
Q

what was the crookes tube then updated to

A

Coolidge tube

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6
Q

devised a FLUOROSCOPE using a fluorescing screen

-dynamic

A

Thomas edison

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7
Q

when did clarence dally die

A

October in 1904

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8
Q

What place did Conrad discovered x-rays

A

the university of wurzburg Germany bavaria

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9
Q

what was the paper coated with for the tube to be energized

A

barium platinocyanide

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10
Q
  • Awareness of potential harmful effects of ionizing radiation
    Desire of the medical community to reduce radiation exposure throughout the world by developing standards for measuring and limiting this exposure
    Reasons diagnostic imaging personnel should be familiar with
A

radiation quantities and units

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11
Q

greek term “soma” means

A

of the body

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12
Q

Among physicians, cancer deaths attributed to x-ray exposure were reported as early as

A

1910

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13
Q

Result of excessive occupational radiation exposure for early pioneers and excessive exposure of patients

A

Radiodermatitis
Cancer
Blood disorders

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14
Q

somatic

A

to yourself

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15
Q

genetic

A

future generations

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16
Q

many radiologists and dentists using the new penetrating rays developed a reddening of the skin called

A

radiodermatitis.

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16
Q

when were committees being started

A

1910
first death was 1904

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17
Q

best overall dose

A

effective dose

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18
Q

Unit used from 1900 to 1930 to measure radiation exposure Problems encountered in using the skin erythema dose as a way to measure radiation exposure
Need to find a more reliable unit
New unit selected to be based on some exactly measurable effect produced by radiation, such as ionization of atoms or energy absorbed in the irradiated object
- Because the amount of radiation required to produce an erythema reaction varied from one person to another

A

Skin Erythema Dose

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19
Q

early tissue reactions appear within

A

minutes, hours, days, or weeks of the time of radiation exposure, were believed to be preventable if doses to radiation workers were limited.

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20
Q

Early tissue reactions

A
  • Nausea
  • Fatigue
  • Diffuse redness of the skin
  • Loss of hair
  • Intestinal disorders
  • Fever
  • Blood disorders
  • Shedding of the outer layer of skin
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21
Q

Late tissue reactions

A
  • Cataract formation
  • Fibrosis
  • Organ atrophy
  • Loss of parenchymal cells
  • Reduced fertility
  • Sterility
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22
Q

Stochastic effects

A
  • Cancer
  • Genetic (hereditary) effects
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22
Q

stochastic

A

random

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22
Q

meaning nothing is safe

A

nonthreshold

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23
Q

is a radiation dose to which occupationally exposed persons could be subjected without any apparent harmful acute effects, such as erythema of the skin

A

tolerance dose (threshold dose)

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24
Q

meaning up to a certain point, your fine after that you start seeing reactions

A

Threshold

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25
Q

Concept of tolerance dose

A

Threshold dose

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26
Q

a dose of radiation lower than which an individual has a negligible chance of sustaining specific biologic damage

A

threshold dose

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27
Q

is recommended as a tolerance daily dose limit in 1934

A

0.2 R (roentgens)

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28
Q

is recommended as a tolerance daily dose limit in 1936

A

0.1 R

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29
Q

late reactions time period

A

couple months and years

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30
Q

becomes internationally accepted as the unit of measurement for exposure to x-radiation and gamma radiation in 1937.

A

Roetgen

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31
Q

radiation exposure received in the course of exercising professional responsibilities, many radiologists and dentists using the new penetrating rays developed a reddening of the skin called radiodermatitis.

A

occupational exposure

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32
Q

replaced the tolerance dose for radiation protection purpose in 1950s

A

maximum permissible dose (MPD)

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32
Q

The rem has since been replaced by the SI unit

A

sievert

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32
Q

Based on the energy deposited in biologic tissue by ionizing radiation, it takes into account both of the following: the effective dose

A

The type of radiation (e.g., x-radiation, gamma, neutron)
2. The variable sensitivity of the tissues exposed to the radiation

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33
Q

The International System of Units (SI) is developed. what year

A

1948

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34
Q

he ICRP replaces effective equivalent dose with the term effective dose (EfD). what year

A

1991

35
Q

The SI unit of absorbed dose

A

gray (Gy)

36
Q

who created the gray

A

Louis Harold Gray

36
Q

ionization produced in air.

A

exposure

37
Q

deposition of energy per unit mass in any material from exposure to ionizing radiation.

A

absorbed dose

37
Q

is a quantity that builds upon D but then takes into account the type of radiation striking an object

A

equivalent dose

38
Q

builds upon EqD by adding an attempt to take into account the different harmful degrees of radiation effects on the parts of the body that are being irradiated to arrive at an index of overall harm to a human

A

effective dose

38
Q

The quantity equivalent dose uses radiation weighting factors (WR)

A

to adjust the value of the absorbed dose to reflect the different capacity for producing biologic harm by various types and energies of ionizing radiation

39
Q

The quantity effective dose uses tissue weighting factors (WT)

A

to adjust the quantity equivalent dose to reflect the difference in harm to the person as a whole depending on the tissues and organs that have been irradiated. Therefore, effective dose takes into account both the type of radiation and the part of the body irradiated.

39
Q

Units for exposure

A

Coulombs per kilogram

40
Q

units for air kerma

A

gray

41
Q

Units for absorbed dose

A

gray

42
Q

Units for equivalent dose and effective dose

A

Sievert

42
Q

is the total electric charge of one sign, either all plus or all minus, per unit mass that x-ray and gamma ray photons with energies up to 3 million electron volts (MeV) generated in dry (i.e., nonhumid) air at standard temperature (22° C) and pressure (760 mm Hg or 1 atmosphere at sea level).

A

exposure

43
Q

It is a radiation quantity “that expresses the concentration of radiation delivered to a specific area, such as the surface of the human body.

A

exposure

43
Q

This type of direct measurement is normally accomplished in an accredited dosimetry calibration laboratory (ADCL) by using a standard, or free-air,

A

ionization chamber

43
Q

chambers collected electrical charge of 2.58 x 10-4 c/kg of irradiated air constitutes an exposure

A

of 1 roentgen R

44
Q

The basic unit of electric charge
It is equal to the “amount” of electrical charge moving past a point in a conductor in 1 second when an electric current amounting to 1 ampere is used

A

coulomb (c)

44
Q

The SI unit of electric current

A

Ampere

44
Q

SI unit of measure for the radiation quantity, exposure, is equal to an electric charge of 1 C produced in a kilogram of dry air by ionizing radiation.

A

Coulomb per kg

44
Q

Acronym for
Kinetic energy released in air
Kinetic energy released in material
Kinetic energy released per unit mass

A

Air Kerma

45
Q

Gradually replacing the traditional quantity, exposure
Denotes a calculation of radiation intensity in air
Quantity that can be used to express x-ray tube output and inputs to image receptors

A

Air Kerma

45
Q

SI quantity used to express how energy is transferred from a beam of radiation to a material such as the patient’s skin

A

Air Kerma

46
Q

Expressed in metric units of joule per kilogram (J/kg)
May be stated in Gy
When the Gy is used to indicate kinetic radiation energy deposited or absorbed in a mass of air, it is written as Gya.
When the Gy is used to indicate kinetic radiation energy deposited or absorbed in a mass of tissue, it is written as Gyt.

A

air kerma

47
Q

Is the sum total of air kerma over the exposed area of the patient’s surface, or a measure of the amount of radiant energy that has been thrust into a portion of the patients body surfaceIs usually specified in units of mGy-cm2

A

Dose area product (DAP)

48
Q

This quantity is the amount of energy per unit mass absorbed by an irradiated object

A

Absorbed Dose

49
Q

It is responsible for any biologic damage resulting from exposure of the tissues to radiation.
Some structures in the body can absorb more radiant energy than others

A

Absorbed Dose

50
Q

The amount of energy absorbed by a structure depends on the

A

Atomic number (Z) of the tissue comprising the structure
Mass density of the tissue
Energy of the incident photon

51
Q

The Si unit of absorbed dose is :

A

milligray

52
Q

Units for the following :
- in the air
- hit tissue
- scatter

A
53
Q

-field of view
- how much tissue are you radiating

A

Dose area product

54
Q

is the amount of energy transferred on average by incident radiation to an object per unit length of track, or passage, through the object and is expressed in units of kiloelectron volts per micrometer (keV/µm)

A

linear energy transfer (LET)

55
Q

Quality Factor of xray

A

1

56
Q

quality factor of beta

A

1

56
Q

quality factor of gamma

A

1

57
Q

quality factor of alpha

A

20

58
Q

quality factor of x-ray, beta, and gamma

A

1

59
Q

quality factor for fast neurons

A

20

60
Q

Is the product of the average absorbed dose in a tissue or organ in the human body and its associated WR chosen for the type and energy of the radiation in question

A

EqD

60
Q

Used for radiation protection purposes when a person received exposure from various types of ionizing radiation
For measuring biologic effects may be determined and expressed in Sv or in a subunit of the Sv

A

EqD

61
Q

tissue is only used with which dose

A

effective

61
Q

D x WR and Sv = Gy x WR

A

EqD

62
Q

Must be used when determining EqD
Is a dimensionless factor (a multiplier) used for radiation protection purposes to account for differences in biologic impact among various types of ionizing radiation
Places risks associated with biologic effects on a common scale

A

Radiation Weighting Factor (WR)

63
Q

Provides a measure of the overall risk of exposure to humans from ionizing radiation

A

EfD

64
Q

how much was absorbed in the body + type of radiation

A

equivalent dose

64
Q

Takes into account the relative detriment to each specific organ and tissue
Used in the calculation of EfD
A value that denotes the percentage of the summed stochastic (cancer plus genetic) risk stemming from irradiation of tissue (T) to the all-inclusive risk, when the entire body is irradiated in a uniform fashion
Accounts for the risk to the entire organism brought on by irradiation of individual tissues and organs

A

Tissue Weighting Factor (WT)

65
Q

“The sum of the weighted equivalent doses for all irradiated tissues or organs” (NCRP Report No. 116)
Incorporates both the effect of the type of radiation used and the variability in radiosensitivity of the organ or body part irradiated through the use of appropriate weighting factors
These factors quantify the overall potential harm to those biologic components and the risk of developing a radiation-induced cancer or, for the reproductive organs, the risk of genetic damage.

A

EfD

65
Q

D × WR × WT

A

EfD

65
Q

Quantity used to describe radiation exposure of a population or group from low doses of different sources of ionizing radiation

A

Collective EfD

66
Q

Person-sievert is the radiation unit for this quantity

A

Collective EfD

66
Q

Used in radiation protection to describe internal and external dose measurements

A

Collective EfD

66
Q

is another SI quantity that is used to express how energy is transferred from a beam of radiation to air. It is mostly replacing the traditional quantity, exposure.

A

Air Kerma

66
Q

A radiation dosimetry quantity that was defined by the NRC to monitor and control human exposure to ionizing radiation

A

Total Effective Dose Equivalent (TEDE)

67
Q

is defined as the amount of energy per unit mass absorbed by an irradiated object

A

Absorbed Dose

67
Q

Described by NRC regulations as “the sum of effective dose equivalent from external radiation exposure and a quantity called committed effective dose equivalent (CEDE) from internal radiation exposures.

A
67
Q

Traditionally, the whole-body TEDE regulatory limit is

A

0.05 Sv for occupationally exposed personne

67
Q

how much Tede for the general public

A

0.001 Sv for the general public

67
Q

Determined as the product of the average EfD for an individual belonging to the exposed population or group and the number of persons exposed

A

Collective EfD

68
Q

If 200 people receive an average effective dose of 0.25 Sv, the collective effective dose is

A

(200)(0.25)= 50 person - sieverts

Radiology Biology & Protection (9 decks)

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