ROphex Old Q1000+ Flashcards

1
Q

Q1000. A radioactive sample is counted for a ten minute interval many times, yielding a mean count rate of 100 cpm. The most probable distribution is:

A. 68% of the measurements fall between 990 and 1010 cpm

B. 68% of the measurements fall between 936 and 1064 cpm

C. 68% of the measurements fall between 900 and 1100 cpm

D. 95% of the measurements fall between 936 and 1064 cpm

E. 95% of the measurements fall between 800 and 1064 cpm

A

A. 68% of the measurements fall between 990 and 1010 cpm

–If a large number of measurements(N) are made, approximately 67% will fall between +σ, and 96% between +2σ of the mean. The standard deviation σ=sqrt(N).

In this case, 1000 cpm x 10 min = N = 10000 counts. σ=sqrt(N) so it is 100. 100 averaged over 10 minutes is 10 cpm.

Therefore 1000+/-(10)= 990-1010

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2
Q

Q1002. A series of measurements has a mean of 100 counts. A range of +σ is ___ .

A. 95-105

B. 90-110

C. 68-137

D. 50-150

E. 33-167

A

B. 90-110

–The standard deviation s is the square root of the mean, in this case sqrt(100) = 10.

–68% fall within σ of the mean.

–95% fall within 2 σ of the mean.

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3
Q

Q1004. To achieve a standard deviation of 2%, ___ counts must be collected.

A. 400

B. 1,414

C. 2,500

D. 10,000

E. 40,000

A

C. 2,500

%σ = σ/N x 100 = N^.5/N x 100 = 100/N^.5 = 2

50 = N^.5

N = 2500

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4
Q

Q1006. A radioactive sample is counted for 1 minute and produces 900 counts. The background is counted for 10 minutes and produces 100 counts. The net count rate and net standard deviation are about ___,___ counts.

A. 800, 28

B. 800, 30

C. 890, 28

D. 890, 30

E. 899, 30

A

D. 890, 30

900/1 min - 100/10 min = 890/1 min

590^.5 = 30 = 1 standard deviation

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5
Q

Q1012. In a chi-square test, looking for a statistically significant difference between two experimental results, claims of such a difference with a p value of 0.01:

A. Means there is unquestionably a difference between the two results.

B. Allows the experimenter a wider latitude of error than would a p value of 0.05.

C. Means there is a 99% chance that the claim is true.

D. Means there is a 99% chance that the claim is incorrect.

A

C. Means there is a 99% chance that the claim is true.

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6
Q

Q1018. Concerning the poisson distribution (answer A for true and B for false):

  1. It is another name for the normal distribution
  2. It is due to random variations
  3. Photon distribution on an x-ray film is a poisson distribution
  4. Radioactive decay as a function of time is a poisson distribution
  5. The standard deviation increases as the number of measurements increases
  6. The percent standard deciation increases as the number of measurements increases
A
  1. It is another name for the normal distribution - B, FALSE; Poisson is binomal distribution whether it either occurs or not. Normal is much larger.
  2. It is due to random variations - A, TRUE
  3. Photon distribution on an x-ray film is a poisson distribution - A, TRUE
  4. Radioactive decay as a function of time is a poisson distribution - A, TRUE
  5. The standard deviation increases as the number of measurements increases - A, TRUE; σ=(N)^1/2, so yes
  6. The percent standard deciation increases as the number of measurements increases - B, FALSE
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7
Q

Q1020. Information will be destroyed in/on a ___ when the computer power is turned off.

A. Floppy disk

B. Hard disk

C. Magnetic tape

D. RAM

E. ROM

A

D. RAM - random access memory

ROM is read only memory

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8
Q

Q1022. Concerning digital computers, all of the following are true, except:

A. ROM stands for Random Order Memory.

B. A Word is a set of consecutive bits treated as an entity, and occupying one storage location in memory.

C. A byte contains 8 bits.

D. A modem is a device that converts a digital signal into a frequency-coded signal for transmission over a telephone line.

A

A. ROM stands for Random Order Memory.

  • stands for read only memory
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9
Q

Q1024. The number of binary bits that are required to represent all CT numbers from -1024 to 3096 is bits.

A. 8

B. 9

C. 10

D. 11

E. 12

A

E. 12

3096+1024 = 4120

2^12 = 4096

k-bit is the number of bits per pixel, the grey scale of an image is equal to 2k-bit

k-bit of 2 = 4 shades of grey

k-bit of 8 = 256 shades of grey

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10
Q

Q1026. The computational speed of a computer is measured in units of

A. MB

B. MIPS

C. RVU

D. BAUD

E. BPI

A

B. MIPS

–MIPS is Millions of Instructions Per Second.

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11
Q

Q1028. ROM is memory that can be

A. Used and changed freely

B. Freely read, but not written to

C. Repeatedly used to store output from an input device

D. Randomly accessed

A

B. Freely read, but not written to

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12
Q

Q1030. Parallel processing refers to:

A. Running multiple tasks simultaneously.

B. Using multiple processors to increase speed.

C. Computer networking.

D. Sharing peripheral devices between computers.

A

B. Using multiple processors to increase speed

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13
Q

Q1032. There are approximately __ bits in a megabyte.

A. 1024

B. 2048

C. 8000

D. 2,000,000

E. 8,400,000

A

E. 8,400,000

1 byte = 8 bits

1 kilobyte = 1024 bytes (computers based on binary (base 2)

1 megabyte = 1024 x 1024 bytes = 1048576 bytes

so 1048576 bytes x 8 bits/ 1 byte = 8388608

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14
Q

Q1034. A CT image consists of 200 slices each 512 x 512 pixels each pixel having a 16 bit pixel depth. The size of the file is ____

A. 500 kB

B. 5 MB

C. 10 MB

D. 50 MB

E. 100 MB

A

E. 100 MB

200 slices x 512 x 512 pixels x 16 bits/ pixel x 1 byte/ 8 bits x 1 megabyte/ (1024 x 1024 bytes) = 100 MB

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15
Q

Q1036. The mainframe of a digital computer contains:

  1. core memory
  2. central processing unit (CPU)
  3. only random access memory
  4. software
  5. connectors for peripheral devices

A. 1, 2, 5

B. 1, 2

C. 2, 4

D. 1, 4

E. 1, 2, 3, 4, 5

A

A. 1, 2, 5

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16
Q

Q1043. A 16 bit word computer can directly address a maximum of how many different locations?

A. 16

B. 32581

C. 58325

D. 65536

E. 130036

A

D. 65536

2^16

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17
Q

Q1048. All of the following contribute about equally to the average annual dose equivalent received by a member of the US population, except:

A. Internal

B. Terrestrial, other than radon

C. Medical x-rays

D. Nuclear medicine

E. Cosmic

A

D. Nuclear medicine

–Out of a total of about 2.6 mSv, nuclear medicine contributs about 0.14 mSv, and the other all contribute 0.3 to 0.4 mSv each.

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18
Q

Q1050. The highest dose received by the population from natural background radiation is from:

A Cosmic radiation.

B. Radon.

C. Internal radiation.

D. Terrestrial, other than radon.

A

B. Radon

–Radon contributes 2 mSv to the average annual effective dose equivalent.

–Out of a total of about 2.6 mSv, nuclear medicine contributes about 0.14 mSv, and the other all contribute 0.3 to 0.4 mSv each (including medical x-rays, internal, cosmic, and terrestial radiation EXCLUDING radon)

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19
Q

Q1052. The average natural background is made up of cosmic radiation, terrestrial radiation and:

A. fallout

B. scattered medical radiation

C. nuclear plant releases

D. radioactive waste disposal contamination

E. internal radiation

A

E. internal radiation

–NATURAL IS KEY, as other products are artificial.

–About 40 mrem/yr is contributed by radionuclides within the body, most 40K.

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20
Q
  1. The most significant source of man made radiation dose to the population as a whole is from:

A. high altitude air travel

B. television recievers and other consumer products

C. fallout from nuclear weapons exploded in the atmosphere

D. diagnostic radiological examination

E. nuclear reactor effluents

A

D. diagnostic radiological examination

Nuclear med is 2nd after x-ray

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21
Q

Q1056. The annual average natural background radiation dose to members of the public in the United States, excluding radon, is approximately ___ mrem.

A. 10

B. 50

C. 100

D. 200

E. 400

A

C. 100

–Radon adds another 230 mrem/yr. Man-made radiation, mostly diagnostic x-rays, is about 54 mrem/yr.

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22
Q

Q1058. The largest contribution to the radiation exposure of the U.S. population as a whole is from:

A. Radon in the home.

B. Medical x-rays.

C. Nuclear medicine procedures.

D. The nuclear power industry.

A

A. Radon in the home.

–Radon, at 230 mrem/yr, is twice other natural background radiation, which in turn is about twice all man-made radiation put together.

Radon (~200 mrem) > other background natural (100 mrem) > man made AKA mostly x-rays (50 mrem)

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23
Q

Q1060. The principal hazard from indoor radon involves:

A. Whole body dose from gamma rays.

B. Skin dose from betas.

C. Lung dose from alpha emission.

D. Bone dose from deposited radionuclides.

A

C. Lung dose from alpha emission.

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24
Q

Q1065. About half the average effective dose equivalent received by the U.S. population is attributable to:

A. Radon

B. Medical procedures

C. Fallout

D. Cosmic radiation

E. Internal radionuclide

A

A. Radon

Radon (~200 mrem) > other background natural (100 mrem) > man made AKA mostly x-rays (50 mrem)

Remember radon is damaging via alpha to lung tissue

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25
Q

Q1066. Match the following annual radiation levels with the sources listed. Answers may be used more than once.

A. 50 mSv

B. 10 mSv

C. 2 mSv

D. 1 mSv

E. 0.5 mSv

  1. Average dose to a member of the population from radon
  2. Maximum recommended dose to a radiation worker
  3. Average dose to a member of the population from medical uses of radiation
  4. Maximum recommended dose to a member of the public (infrequent exposure)
A
  1. Average dose to a member of the population from radon (C. 2 mSv)
  2. Maximum recommended dose to a radiation worker (A. 50 mSv)
  3. Average dose to a member of the population from medical uses of radiation (E. 0.5 mSv)
  4. Maximum recommended dose to a member of the public (infrequent exposure) (D. 1 mSv)
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26
Q

Q1068. The average total annual dose to a member of the public from background and man-made radiation is ___ mSv.

A. 5.0

B. 3.5

C. 1.5

D. 0.4

E. 0.2

A

B. 3.5

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27
Q

Q1073. According to NCRP report #91, the quality factor for high LET radiations such as neutrons should generally be:

A. 1

B. 2

C. 5

D. 10

E. 20

A

E. 20

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28
Q

Q1076. Studies of the affects of the atomic bombs dropped on Japan during World War II indicate that the probability of inducing cancer in a large population that is irradiated with 1 rem is about ___ during that population’s lifetime.

A. 1 in 10

B. 1 in 1,000

C. 1 in 10,000

D. 1 in 100,000

E. 1 in 1,000,000

A

C. 1 in 10,000

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29
Q

Q1078. Current models of radiation dose v. effect assume that 100 mSv (10 rem) delivered over a year to 1 thousand people will cause ___ additional cancer deaths, compared to an unexposed group of the same size.

A 0.05

B. 0.5

C. 5

D. 50

E. 100

A

C. 5

–The current value is 5 x 10^-2 per Sv. (BEIR V)

1 rem = 1 in 10,000 additional cancer cases

10 rem = 1 in 1,000 additional cancer cases

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30
Q

Q1080. The latent period for radiation-induced carcinogenesis (solid tumors) is about ___ years.

A. 1

B. 5

C. 10

D. 20-30

E. 40-50

A

D. 20-30

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31
Q

Q1082. The currently accepted model of radiation dose versus effect used by regulatory agencies to determine dose standards is ___ .

A. Linear quadratic.

B. Exponential.

C. Cubic.

D. Linear, threshold.

E. Linear, no threshold.

A

E. Linear, no threshold.

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32
Q

Q1084. A whole body dose of 5 mSv/yr for 20 years would increase a radiation worker’s risk of cancer by approximately ___%.

A. 0.05

B. 0.5

C. 5

D. 10

A

B. 0.5

5 mSv/yr for 20 years = 100 mSv = 0.1 Sv

(5 x 10^-2)/ Sv is the increased risk; thus:

(5 x 10^-2)/ Sv x 0.1 Sv = 0.005 = 0.5%

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33
Q

Q1086. The latent period for radiation-induced solid tumors is about ___ years.

A. 1

B. 5

C. 10

D. 20

E. 50

A

D. 20

–According to BEIR V - Biological Effects of Ionizing Radiation

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34
Q

Q1088. For risk-benefit calculation purposes, NCRP Report 116 (1993) estimates a probability of developing fatal breast cancer from one 2-view mammographic exam to be about___%. (Assume a mean glandular dose of 4 mGy to each breast.)

A. 0.001

B. 0.1

C. 1

D. 10

A

A. 0.001

–0.05 per Sv x breast organ weighting factor (0.05) for a total of 0.0025 per Sv.

–For x-rays 1 Sv = 1 Gy

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35
Q

Q1090. The radiation protection quantity which has been used in attempts to estimate the cancer risk from x-ray irradiation of personnel is

A. Exposure (X)

B. Air Kerma (K)

C. Absorbed dose (D)

D. Dose equivalent (H)

E. Effective dose (E)

A

E. Effective dose (E)

–Attempts to weight the radiation dose to different organs by the relative cancer risk of each organ.

Equivalent dose = Radiation weighing factor

Effective dose = Tissue weighing factor

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36
Q

Q1092. Deterministic or non-stochastic effects of radiation include all of the following except:

A. Bone marrow damage

B. Skin damage

C. Cataract induction

D. Leukemia

E. Infertility due to gonadal irradiation

A

D. Leukemia

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37
Q

Q1094. The following effects are:

A. Stochastic

B. Deterministic

C. Both

D. Neither

  1. Induction of cancer from exposure to radiation
  2. Skin burns from prolonged fluoroscopic exams
A
  1. Induction of cancer from exposure to radiation - (A. Stochastic)
  2. Skin burns from prolonged fluoroscopic exams - (B. Deterministic)

Hint:

Deterministic - you can “determine” the extent of your consequences and change the severity of them occuring by actions

Stochastic - Be “stoic” and accept whatever fate throws at you, can can’t change the outcome that is up to chance

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38
Q

Q1096. According the BEIR V, the additional risk of cancer death from a 0.1 Sv (10 rem) exposure to a population of 100,000 people would be about ___%.

A. 0.01

B. 0.1

C. 1.0

D. 10.0

A

C. 1.0

BEIR V (1990) states that the excess cancer deaths in a population of 100,000 persons exposed to 0.1 Sv would be about 770 males or 810 females.

Remember that based off of the A-bomb studies from World War II, probability of inducing cancer in a large population that is irradiated with 1 rem is about 1 in 10,000 during that population’s lifetime.

1 rem = 0.01 Sv, so 0.1 Sv would lead to 1 in 1,000

1,000/ 100,000 = 1/100 = 1%

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39
Q

Q1098. Perinatal death (at or around the time of birth) is most likely to occur as a result of irradiation in humans which occurs in the gestational period of:

A Implantation of the embryo.

B. Major organogenesis (21-40 days).

C. Second trimester.

D. Just before birth (30-36 weeks).

A

B. Major organogenesis (21-40 days), AKA 3-8 weeks (deterministic effect, threshold is 0.1 Gy)

  • Do NOT confuse this with PRE-natal death which is highest risk with radiation exposure in first 3 weeks of pregnancy; PERI-natal/NEO-natal only takes into effect at earlist after 3 weeks post implantation

–In early organogenesis, the organ buds consist of a few cells, and the lose of some of these can result in a major defect which may not be apparent during gestation, but after birth is too severe to permit independent life.

  • In week 8-25, greatest risk is mental retardation
  • In week 25+ it is risk of cancer
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40
Q

Q1101. In radiation protection the embryo/fetus is considered more vulnerable to radiation than an adult, for all of the following reasons except:

A. In a given volume, more embryonic cells are proliferating than adult cells.

B. In a given volume, more embryonic cells are differentiating than adult cells.

C. An embryo consists of fewer cells, making the loss of cells by radiation injury potentially more damaging.

D. The higher oxygen tension of the embryo/fetus results in a higher oxygen enhancement ratio (OER).

A

D. The higher oxygen tension of the embryo/fetus results in a higher oxygen enhancement ratio (OER).

–Just wrong.

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41
Q

Q1103. Regarding radiation effects in the embryo:

A. Prenatal death is equally likely at all stages of development.

B. Neonatal death is most likely for embryos irradiated in the last trimester.

C. Embryonic cells are resistant to radiation because of an efficient repair mechanism.

D. Most congenital abnormalities occur during the period of organogenesis.

A

D. Most congenital abnormalities occur during the period of organogenesis.

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42
Q

Q1105. The estimated increased risk of birth defect in a fetus receiving 1 rem (10 mSv) in the 12th week of gestation is about _%.

A 0.01

B. 0.1

C. 1.0

D. 10

A

C. 1.0

–The highest risk from 2 to 16 weeks post-conception is a maximum incidence of 1% per rem for small head size.

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43
Q

Q1107. According to NCRP there is a negligible increase in the risk of adverse effects to the fetus, compared with other risks of pregnancy, up to a total dose of___mGy.

A. 5

B. 20

C. 100

D. 500

E. 1000

A

C. 100

–Or 10 cGy.

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44
Q

Q1109. For radiation protection purposes, the dose equivalent of 100 mrem of neutrons is ___ mSv.

A 1

B. 2

C. 10

D. 20

E. 100

A

D. 20

–100 mrem = 1 mSv.

–Dose equivalent (H) = Dose (D) x Quality Factor (Q)

–Q for neutrons is 20.

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45
Q

Q1111. Which of the following is true about film badges?

A. Can measure total dose, but cannot distinguish between high- and low-energy x-rays.

B. Can measure exposures of 2 mR.

C. Are insensitive to heat.

D. Are used to determine exposure by measuring the optical density of the film.

E. None of the above is true.

A

D. Are used to determine exposure by measuring the optical density of the film.

Placing filters over parts of the film allows one to estimate the proportion of dose due to x-rays in different energy ranges

–Cannot measure below 20 mR.

–Are sensitive to heat and sunlight.

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46
Q

Q1118. The recommended weekly effective dose equivalent permitted for radiologists under current regulations is:

A. 10 μSv

B. 50 μSv

C. 100 μSv

D. 0.5 mSv

E. 1.0 mSv

A

E. 1.0 mSv

–50 mSv/yr divided by 52 wks is 1.0 mSv/week

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47
Q

Q1120. Regulations limit the dose equivalent to the embryo/fetus of a declared pregnant radiation worker to __ mSv/month.

A. 50

B. 10

C. 5

D. 0.5

E. 0.1

A

D. 0.5

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48
Q

Q1121. According to NCRP Report No. 116, the recommended maximum annual dose equivalent for radiation workers’ whole body is ___ mSv and for the hands is ___ mSv.

A 5 5

B. 5 50

C. 10 100

D. 50 50

E. 50 500

A

E. 50 500

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49
Q

Q1128. Filters are used in film badges to: (answer A for true and B for false)

  1. Convert x-ray or y-ray energy to visible light to expose the film
  2. Shield a portion of the film for a base density reading
  3. Discriminate between different types of radiation
  4. Discriminate between different radiation energies
  5. Reduce the exposure to the user
A
  1. Convert x-ray or y-ray energy to visible light to expose the film - (B, FALSE)
  2. Shield a portion of the film for a base density reading- (B, FALSE)
  3. Discriminate between different types of radiation - (A, TRUE)
  4. Discriminate between different radiation energies - (A, TRUE)
  5. Reduce the exposure to the user - (B, FALSE)
50
Q

Q1134. The NRC requires personnel to wear a radiation monitor if they are likely to receive ___% of the annual dose limit.

A. 90

B. 50

C. 25

D. 10

E. 1

A

D. 10

51
Q

Q1136. Regulations in the U.S. limit the total dose equivalent to the fetus of a declared pregnant radiation worker to___mSv.

A. 50

B. 25

C. 5

D. 2.5

E. 0.5

A

C. 5

52
Q

Q1138. The recommended annual effective dose limits for members of the public (NCRP 116) are ___ mSv for infrequent exposure, and___mSv for continuous exposure.

A. 5, 1

B. 1, 5

C. 10, 5

D. 5, 5

E. 10, 20

A

A. 5, 1

53
Q

•If the workload of a diagnostic x-ray room is increased by a factor of 4, (all other factors, e.g., energy, use factor, etc., remaining unchanged), the shielding at the console should be increased by:

A. 1 HVL

B. 2 HVLs

C. 4 HVLs

D. 2 TVLs

E. 4 TVLs

A

B. 2 HVLs

–2 HVLs will reduce the dose by a factor of 2^2 = 4.

54
Q

Q1144. When calculating radiation barrier thickness requirements, the use factor “U” refers to:

A. The weekly dose delivered at 1 m from the radiation source.

B. The fraction of operating time during which the area on the other side of the barrier is occupied.

C. The fraction of operating time during which the radiation is directed towards the barrier.

D. The fraction of the work week during which a particular individual is in the area of interest.

A

C. The fraction of operating time during which the radiation is directed towards the barrier.

–The use factor can be difficult to calculate, so standard fractionations can be used for the walls and floors.

55
Q

Q1147. A “controlled area” is defined as:

A. Any area around a radiation facility where the exposure rate is above background.

B. An area that one cannot enter unless one is wearing a film badge.

C. An area where workers will not receive more than 5 mrem/week.

D. An area where the exposure of workers is under the supervision of the Radiation Safety Officer (RSO).

A

D. An area where the exposure of workers is under the supervision of the Radiation Safety Officer (RSO).

–Workers can receive up to 100 mrem/wk.

56
Q

A dose rate of 2 mrem/hr is measured in a non-radiation worker’s office, adjacent to a source storage room. How much shielding must be added to reduce this to an acceptable level?

A. No additional shielding is required.

B. 1 HVL

C. 2 HVLs

D. 1 TVL

E. 2 TVLs

A

E. 2 TVLs

–The acceptable level for continous or frequent exposure of members of the public is 100 mrem/yr = 2 mrem/wk = 0.05 mrem/hr, assuming a hr work week.

–To reduce 2 to 0.05, requires 2 TVL’s

–Tenth-Value-Layers (TVL)
TVL = Shield thickness needed to reduce exposure by 1/10th.

57
Q

If one lead apron attenuates 95% of an x-ray beam, two aprons will transmit approximately _%.

A. 10

B. 5

C. 2.5

D. 1.25

E. 0.25

A

E. 0.25

–One lead apron transmits 5%.

–Two will transmit 0.052=0.0025 or 0.25%

58
Q

Q1156. When designing shielding for an x-ray machine, regulations require that the barrier for a fully-occupied non-controlled area must be about ___ HVLs thicker than that for a controlled area.

A. 50

B. 10

C. 6

D. 2

E. 1

A

C. 6

–The current annual MPDs are 100 mrem for non-controlled areas and 5 rem (5000 mrem) for controlled areas. This factor of 50 requires about 6 HVLs more shielding (26=64).

59
Q

Q1160. The exposure rate at 1 m from a radioactive source is 100 mR/hr. A 0.06 mm lead shield is placed around the source. The exposure rate is now ___ mR/hr. (HVL in lead is 0.02 mm.)

A. 75

B. 50

C. 25

D. 12.5

E. 5

A

D. 12.5

0.06 mm/ 0.02 mm = 3 HVLs

So 100 x (1/2)^3 = 100/8 = 12.5

60
Q

Q1162. The exposure rate constant of a radionuclide is 12.9 R-cm^2/ mCi-hr. How many HVLs are required to reduce the exposure rate at 1 meter from a 10 mCi soure to 2 mR/ hr?

A. 1

B. 2

C. 3

D. 6

A

C. 3

12.9 R-cm^2/ mCi-hr x 10 mCi x (1 m/ 100 cm)^2

= 12.9 R x 10 x m^2 / (10^4) hr

= 129 x 10^-4 Rm^2/hr

= 12.9 mR x m^2/ hr

To get this down to 2 mR/hr would be (1/2)^3 or 3 HVLS

61
Q

Q1164. In the event of a 137Cs “dirty bomb” explosion, regarding the use of potassium iodide pills, which of the following is true?

A. Kl should be taken as soon as possible.

B. Kl should be taken if the thyroid has the potential of receiving a dose greater than 15 rem.

C. A dose of 130 mg per day is suggested for adults.

D. KI will offer no protection.

A

D. KI will offer no protection.

–KI only good for nuclear bomb, reactor explosion.

–Only good for Iodine.

–I-131 has short half-life, not good for dirty bomb.

62
Q

Q1166. All of the following are used in x-ray machine room shielding calculations in the United States except:

A. Occupancy factor and use factor

B. Weekly dose limit to workers or public

C. Workload

D. Beam energy

E. Instantaneous dose rate

A

E. Instantaneous dose rate

63
Q

Q1168. A shielding design for a diagnostic or therapy installation, when there is no restriction on the beam direction, must (answer A for true and B for false):

  1. Consider all wals as primary barriers

2, Assign all walls a use factor (U) of 1

  1. Assign any area which people may frequent an occupancy factor (T) of 1
  2. Shield all areas to a radiation level of 0.1 rem per week
  3. Shield such that unrestricted environments will not receive greater than 2 mR in any one hour
A
  1. Consider all wals as primary barriers - TRUE
  2. Assign all walls a use factor (U) of 1 - FALSE
    - In general walls are assigned use factors (U) of ¼ or 1/16. The walls could have all have a U of 1 at the same time.
  3. Assign any area which people may frequent an occupancy factor (T) of 1 - FALSE
    - For areas such as corridors or toilets recommended occupancy factors (T) are ¼ or 1/16. Occupancy factors are based on the time that an individual is exposed to radiation in the area. A busy, one person office could be assigned a T of 1.
  4. Shield all areas to a radiation level of 0.1 rem per week - FALSE
    - Controlled areas are allowed levels of 0.1 rem per week. Non-controlled areas are required to be shielded to levels of 0.002 rem per week. In practice most areas are shielded well below the maximum permissible level.
  5. Shield such that unrestricted environments will not receive greater than 2 mR in any one hour - TRUE
    - This is an additional restriction on non-controlled areas in order to insure that any combination of use and occupancy cannot raise the total dose to greater than the MPD.
64
Q

Q1170. The occupancy factor (T) is changed from 1/16 to 1/2 and the activity (A) is doubled for a radiation source whose HVL is 0.3 mm Pb. In order to maintain the same level of protection ___ mmPb must be added.

A. 0.3

B. 0.6

C. 0.9

D. 1.2

E. 1.5

A

D. 1.2

1/2^4 = 1/16 so you need 3 further HVLs due to changing occupancy factor

In addition, activity is doubled so you need another HVL to counteract that

4 HVLs = 4 x 0.3 mm Pb = 1.2 mm Pb

65
Q

Q1176. A 0.5 mm lead equivalent protective apron is an effective protection device when working with (answer A for true and B for false):

  1. A high energy beta source, such as P-32
  2. Diagnostic x-rays
  3. A Cs-137 implanted patient
  4. Milking a Mo-99 - Tc-99m generator
  5. High levels of I-125
  6. High levels of positron emitters
A
  1. A high energy beta source, such as P-32 (B, FALSE; 1.7 MeV)
  2. Diagnostic x-rays (A, TRUE)
  3. A Cs-137 implanted patient (B, FALSE; 662 keV requires 6.5 mm Pb)
  4. Milking a Mo-99 - Tc-99m generator (B, FALSE; would get the 140 kev of 99mTc, but not the 740 kev of 99Mo)
  5. High levels of I-125 (A, TRUE; 30 keV)
  6. High levels of positron emitters (B, FALSE; 511 keV)

Remember, Pb attenuates at 2 MeV/ mm

66
Q

Q1179. An ionization chamber is calibrated at 22°C and 760 mm Hg. If a measurement is made at 18°C and 750 mm Hg, what correction factor must be applied to the chamber reading?

A. 0.81

B. 0.98

C. 1.00

D. 1.02

E. 1.19

A

C. 1.00

–The Temp-Pressure-Factor Correction factor is

–[(273 + T)/295] x [760/P]

So measurement is colder and less pressure compared to standard.

Cold temperature artificially increases your readings by concentrating your particles, less pressure artifically decreases your readings due to decreasing concentration of particles for interaction.

To correct for this:

(760/750) x (18+273)/(22+273)

67
Q

Q1183. Geiger counters:

A. Operate on the principle of scintillation.

B. Are less sensitive than ionization chambers.

C. Can be used in high-intensity radiation fields.

D. Can detect individual photons or particles.

A

D. Can detect individual photons or particles.

–The advantage of a geiger counter is its sensitivity. The ionizination of a single event is magnified due to gas multiplication, into a measurable signal.

–Its disadvantage is that it can read zero in a high-intensity field.

68
Q

Q1185. In general, which of the following detectors has the greatest energy dependence for x- and gamma rays?

A. Thin window geiger tube.

B. Air equivalent wall ionization chamber.

C. LiF thermoluminescent dosimeter.

D. NaI scintillation detector.

A

D. NaI scintillation detector.

–High Z of iodine makes it highly sensitive to low-energy radiation. This is because of the Z dependence of photoelectric interactions.

69
Q

Q1187. Which of the following detectors would be the best one to locate a dropped iodine-125 seed?

A. Large volume ionization type survey meter.

B. Thermoluminescent dosimeter.

C. Air-equivalent wall “thimble’ ionization chamber.

D. Film badge.

E. NaI scintillation probe.

A

E. NaI scintillation probe.

–Need a portable detector with an instantaneous readout.

–The scintillation probe will give a much higher reading (as would a geiger counter) than an ionization chamber, due to its greater sensitivity.

70
Q

Q1189. Match the most appropriate instrument to the procedure in each question.

A. Liquid scintillation counter

B. NaI well counter

C. Geiger-Mueller (GM) counter

D. Thermoluminescent dosimeter (TLD)

E. Ionization chamber survey meter

  1. Gamma ray sealed source wipe test
  2. Contamination survey for 99mTc.
  3. Radiation survey of a diagnostic x-ray installation
  4. Personnel monitoring
A
  1. Gamma ray sealed source wipe test - B. NaI well counter
    - NaI detects the low level gamma rays
  2. Contamination survey for 99mTc - C. Geiger-Mueller (GM) counter
    - GM has a fast response, and get the low level gamma
  3. Radiation survey of a diagnostic x-ray installation - E. Ionization chamber survey meter
    - minimal energy dependence
  4. Personnel monitoring - D. Thermoluminescent dosimeter (TLD)
  5. Contamination survey for tritium H-3 - A. Liquid scintillation counter
    - gets the low level beta rays form tritium.
71
Q

Q1195. Personnel monitors must have all of the following features except:

A. No energy dependence over the range of radiation encountered

B.. Neglible loss of stored signal over 1 month of wear and time taken to process detector

C. Must be unaffected by normal fluctuations in the environment (temperature, pressure, humidity)

D. Ability to differentiate between different energies and types of radiation

A

A. No energy dependence over the range of radiation encountered

72
Q

Q1197. Quenching gasses are usually used in:

A. ionization chambers

B. propotional counters

C. Geiger Mueller counters

D. Scintillation detectors

E. A and C

A

C. Geiger Mueller counters

Quench the avalanche of charge released by the passage of the initial charge particles.

This decreases dead time and prevents the total paralyzation of the counter.

73
Q

Q1199. The attached graph shows the response curve for a gas filled detector. Given the appropriate region for each of the following descriptions:

  1. The region where current is passed in the absence of radiation
  2. The pulse heights are proportional to the incident particle energy
  3. An ionization chamber is operated in this region
  4. A Geiger survey meter is operated in this region
  5. The saturation region where all charges are collected without multiplication
A
  1. The region where current is passed in the absence of radiation - E; too high voltage will cause conduction of gases
  2. The pulse heights are proportional to the incident particle energy - C; proportional counters operate in this region
  3. An ionization chamber is operated in this region - B
  4. A Geiger survey meter is operated in this region - D; event will trigger the avalanche
  5. The saturation region where all charges are collected without multiplication - B
74
Q

Q1201. The quanitity that an ionization chamber actually measures is:

A. Roentgen

B. Gray

C. Charge

D. Kerma

E. Voltage

A

C. Charge

Radiation produces ionization in the chamber gas which is measured as an electric current.

75
Q

Q1203. Electron equilibrium is said to exist in a small mass when:

A. the number of x-rays entering the mass is equal to the number of x-rays leaving it

B. the build up of dose begins to slow down

C. absorption of the radiation becomes exponential

D. the number of electrons entering the mass is equal to the number of electrons leaving it

A

D. the number of electrons entering the mass is equal to the number of electrons leaving it

76
Q

Q1204. An instrument used for absolute measurements of exposure is:

A. Baldwin-Farmer ionization chamber

B. Thermoluminescent dosimeter

C. Free-air chamber

D. Survey meter

A

C. Free-air chamber

  • the standard
77
Q

Q1205. Calorimetry is a technique used for:

A. routine exposure measurements

B. routine dose measurements

C. absolute exposure measurements

D. absolute dose measurements

A

D. absolute dose measurements

78
Q

Q1206. ion-recombination can be a problem when using a:

A, calorimeter

B. Geiger counter

C. ionization chamber

D. TLD

A

C. ionization chamber

79
Q

Q1215. A patient who had an iodine 125 seed prostate implant 3 years ago is admitted for a transurethral resection of the prostate (TURP). The activity implanted was 25 mCi. The half life of iodine-125 is 60 days. Which of the following is true?

A. radiographs should not be attempted as radiation from the seeds would fog the film

B. the physician performing the TURP should wear a Pb apron and gloves

C. the TURP should not be attempted because of the radiation hazard to OR staff

A

D. none of the above are true

Remember that:

1.44 x 1/2 life = average life

Total dose for LDR = average life x initial activity

80
Q

Q1219. After installation of a chest x-ray unit, which agency regulates its operation?

A. NRC

B. OSHA

C. HICFA

D. State

A

D. State

–Once installed, x-ray units are regulated by the state.

–Mammography units are also regulated by the FDA, under MGQSA standards.

–The FDA regulates the manufactrue and installation of x-ray devices.

–The NRC regulates the use of “man-made” radioactive materials such as Co-60 units and brachytherapy sources.

81
Q

Q1225. A “controlled area” is defined as:

A. any area around a radiation facility where the exposure rate is above background

B. an area which one cannot enter unless wearing a film badge

C. an area where the workers will not recieve more than 10 mrem/ week

D. an area where the exposure of workers is under the supervision of a radiation safety officer

A

D. an area where the exposure of workers is under the supervision of a radiation safety officer

82
Q

Q1226. A “High Radiation Area” sign must be posted at the entrance of all areas where the exposure rate can be:

A. >100 mR/hr

B. >100 mR/hr but <1000 mR/hr

C. >10 mR/hr

D. >100 mR/week

E. None of the above

A

A. >100 mR/hr

83
Q

Q1227. All of the following are true regarding Percentage Depth Dose (PDD) except:

A. Increases with increasing energy.

B. Depends on field size.

C. Is the dose at depth expressed as a % of the dose at dmax.

D. Decreases with increasing SSD.

E. Decreases as depth increases.

A

D. Decreases with increasing SSD.

–PDD increases with increasing SSD because it has two components, attenuation and inverse square.

  • The inverse square component decreases as distance increases.
  • PDD= 100 (Dose at depth along central axis) dose at depth of maximum dose along central axis
  • Dependent upon:

–Beam Quality

•As beam quality (energy) increases, so does PDD

–Depth in Material

•At depth increases, the PDD decreases (except if in buildup region)

–Size of Treatment Field

•As field size increases, PDD increases (more scatter)

–SSD

•As SSD increases, PDD increases secondary to inverse square.

84
Q

Q1230. Match the formula with the quantity:

A. (dose rate at dmax)/ (dose rate at depth) at SSD

B. (dose rate at depth)/ (dose rate at dmax) at SSD

C. (dose rate at dmax)/ (dose rate at depth) at SAD

D. (dose rate at depth)/ (dose rate at dmax) at SAD

E. (dose rate at dmax)/ (dose rate in air) at SAD

  1. TMR
  2. BSF
  3. PDD/100
A
  1. TMR - (D; (dose rate at depth)/ (dose rate at dmax) at SAD)
  2. BSF - (E; (dose rate at dmax)/ (dose rate in air) at SAD)
  3. PDD/100 - (B; (dose rate at depth)/ (dose rate at dmax) at SSD)
85
Q

Q1232. A single posterior spine field is treated at 130 cm SSD. Compared with treatment at 80 cm SSD the exit dose will be:

A. greater

B. smaller

C. the same

A

A. greater

As SSD increases PDD, and thus exit dose, increase (pet Mayneord’s f factor).

86
Q

Q1234. Choose the statement that is true:

A. TAR increases as SSD increases

B. BSF increases as beam energy increases above 1MV

C. PDD increases with increasing SSD

D. TMR cannot be measured for cobalt-60

A

C. PDD increases with increasing SSD

–TAR is independent of SSD or SAD

–BSF increases with increasing energy up to about 1.0 mm Cu HVL, then decreases as energy increases.

–Although historically TARs were measured for cobalt-60 and TMR were introduced for higher energy beams, TMRs can be measured and used for calculating timer settings at any megavoltage energy.

87
Q

Q1236. For a 10 MV photon beam at 10 cm depth, the TMR will be ___ the PDD at 100 cm for the same collimator setting.

A. Greater than

B. Less than

C. Approx. equal to

A

A. Greater than

–TMRs are a measure of attenuation only, whereas PDDs comprise attenuation and inverse square components.

88
Q

Q1238. Tissue-Maximum Ratio (TMR) depends on:

A. Energy, SAD, depth, and field size.

B. Energy, SAD, and field size.

C. SAD, depth, and field size.

D. Energy, depth, and field size.

E. SSD only.

A

D. Energy, depth, and field size.

–TMR is independent of SAD; it simply only needs to be a SAD setup

–It is the radio of the dose rate at depth (d) to dose rate at depth dmax, both measured at the same distance.

89
Q

Q1242. Back scatter factor:

A. is the TAR at dmax

B. increases as energy increases over 1 MV

C. is the PDD at dmax

D. is the ratio of dose in air to dose in tissue

E. all of the above

A

A. is the TAR at dmax

TAR is the dose rate at depth divided by the dose rate in air AKA Tissue Air Ratio

The TAR at dmax is called the back scatter factor (BSF).

BSF decreases as the energy increases above 1 MV.

90
Q

Q1245. TMR:

A. Stands for tumor maximum ratio

B. Is the ratio of dose at dmax to dose at depth

C. increases as SSD increases

D. Cannot be measured on a cobalt-60 unit

E. None of the above

A

E. None of the above

TMR = tissue maximum ratio. It is the ratio of two dose rates measured in phantom, at the same distance from the source; one with a chosen thickness of overlaying phantom, the other with only the thickness required to attain dmax.

It is independent of SSD and can be measured on any megavoltage x-ray or gamma ray unit.

91
Q

Q1246. Which of the following statements is false about TMR?

A. It is equal to TAR/BSF

B. It is approximately related to the percent depth dose by an inverse square factor

C. It is the ratio of the dose at depth divided by the dose at dmax, both measured at the isocenter

D. It is dependent on SSD

E, It increases with increasing field size

A

D. It is dependent on SSD

TMR is independent of SSD since the dose at depth and the dose at dmax are measured at the same distance from the source.

92
Q

Q1249. TAR is:

A. equal to the backscatter factor (BSF) at dmax

B. independent of SAD

C. used in calculations of timer settings for rotational therapy

D. all of the above

E. none of the above

A

D. all of the above

The timer or MU setting for rotation uses the average TAR, averaged over all depths for the area of rotation.

93
Q

Q1253. All of the following are independent of SSD except:

A. TMR

B. TAR

C. PDD

D. BSF

A

C. PDD

PDD increases with increasing SSD, since it contains an inverse square component as well as attenuation. TMR, TAR, and BSF (TAR at dmax) measure attenuation only and are independent of SSD.

94
Q

Q1254. Match the parameter with its definition, according to the diagrams below:

A. D5/D4

B. D5/D1

C. D3/D4

D. D3/D2

E. D1/D4

  1. BSF
  2. PDD/100
  3. TAR
  4. TMR
A
  1. BSF - (E. D1/D4)
  2. PDD/100 - (D. D3/D2)
  3. TAR - (A. D5/D4)
  4. TMR - (B. D5/D1)
95
Q

Q1256. A patient is treated with cobalt-60 radiation in the manner shown below. Point A is 1 cm from the exit surface. The dose at point A is calculated using PDD tables. Relative to the actual value, the calculated dose at point A is:

A. more than 15% high

B. slightly high

C. correct

D. slightly low

E. more than 15% low

A

B. slightly high

The dose to point A will be about 4% lower than that found from tables, due to the lack of total backscatter. The fact is generally ignored in treatment planning dose computer alogrithms.

96
Q

Q1258. Match the backscatter factor for a 10x10 cm field with the energy of the radiation:

A. 1.00

B. 1.02

C. 1.035

D. 1.15

E. 1.26

  1. Superficial, 2.5 mm Al HVL
  2. Co-60
  3. 10 MV x-rays
A
  1. Superficial, 2.5 mm Al HVL - (E. 1.26)
  2. Co-60 - (C. 1.035)
  3. 10 MV x-rays - (B. 1.02)

The BSF is a function of beam quality and field size. It increase to a value of about 1.5 for large fields at about 1 mm Cu HVL, then falls to a negligible value above about 10 MV. It cannot have a value of 1.0 because this would imply that there is no difference between the dose rate in air that that in dmax in tissue.

97
Q

Q1263. For megavoltage photons, TMR has replaced TAR because:

A. TMR is independent of field size

B. TAR is difficult to measure at high energies

C. TMR is preferable to TAR for rotation calculations

D. TMR is independent of depth of maximum dose

A

B. TAR is difficult to measure at high energies

As the beam energy increases, the depth of dmax increases and the size of the chamber build-up cap for the in-air measurement will also increase.

A large size build-up cap will start to act as a “mini” phantom.

98
Q

Q1265. Given a square and rectangle of the same area, which would you expect to have the greater percent depth dose for Co-60?

A. the square

B. the rectangle

C. they have the same depth dose

A

A. the square

Scatter from the corners of the rectangle has farther to travel than from the periphery of the square and will contribute less to the depth dose.

99
Q

Q1267. The TAR for a 10x10 cm SAD for 4 MV photons is 0.8 at a depth of 7 cm. What change would you expect in the TAR by extending the SSD from 93 cm to 193 cm (200 cm from the source), for the same field size at SAD?

A. 5% incease in TAR

B. 10% increase

C. 15% increase

D. no change in TAR

A

D. no change in TAR

TAR is independent of SSD

100
Q

Q1273. Which of the following is correct?

A. TAR = TMR x BSF

B. TAR = TMR/ BSF

C. TMR = BSF/ TAR

D. TMR = TAR x BSF

E. BSF = TAR x TMR

A

A. TAR = TMR x BSF

101
Q

Q1275. Percentage depth dose in photon beams:

  1. Increases with increasing SSD
  2. Increases with increasing field size
  3. Increases with increasing beam energy
  4. Decreases exponentially (not including inverse square effect and scattering beyond dmax

A. 1 only

B. 1, 2, 3

C. 2, 4

D. 4 only

E. all are correct

A

E. all are correct

102
Q

Q1277. Match the following quantities with the units in which they are measured.

A. Sievert

B. Coulombs/kg

C. Gray

D. Bequerel

E. cGy/hr

  1. Activity
  2. Absorbed dose
  3. Exposure
  4. Dose equivalent
A
  1. Activity - (D. Bequerel)
  2. Absorbed dose - (C. Gray)
  3. Exposure - (B. Coulombs/kg)
  4. Dose equivalent - (A. Sievert)
103
Q

Q1280. The depth of maximum dose for a photon beam is approximately equal to:

A. The depth at which dose and kerma are equal.

B. The maximum range of the secondary electrons.

C. The depth at which electronic equilibrium occurs.

D. All of the above.

E. None of the above.

A

D. All of the above.

104
Q

Q1281. The TMR for a 10 x 10 cm2 4 MV photon field at 100 cm SAD is 0.73 at 10 cm depth. If the SSD were changed from 90 cm to 95 cm, the expected change in the TMR would be:

A. Increase of 5%.

B. Increase of 7.5%.

C. Decrease of 5%.

D. Decrease of 7.5%.

E. Zero.

A

E. Zero.

–TMR is independent of SSD, since it represents attenuation of a given thickness of tissue.

–PDD has an inverse component and does depend on SSD.

105
Q

Q1283. Sievert (Sv) is

A. 100 ergs per gram

B. The SI unit of dose equivalent

C. Absorbed dose/RBE

D. The SI unit of exposure

A

B. The SI unit of dose equivalent

–Formerly rem

–Takes into account RBE of different types of radiation. i.e. the neutron effect

106
Q

Q1285. All of the following are true regarding Percent Depth Dose (PDD) except:

A. The value can be adjusted for extended SSD using Mayneord’s F factor.

B. It comprises an attenuation component and an inverse square component.

C. At a given depth it increases as field size increases.

D. For a given field size and depth it increases as energy increases.

E. It is defined as: (dose rate at dmax/dose rate at depth) x 100%.

A

E. It is defined as: (dose rate at dmax/dose rate at depth) x 100%.

–Equation is inverted

107
Q

Q1288. Collecting all the negative ions produced by a beam of photons in a small volume of air, under conditions of electronic equilibrium, is a direct measure of:

A. Dose equivalent

B. LET

C. Absorbed dose

D. Exposure

E. Specific ionization

A

D. Exposure

108
Q

Q1289. The greatest backscatter factor in soft tissue is associated with:

A. 30 kVp x-rays

B. 4 MV linear accelerator x-rays

C. cobalt-60 teletherapy y-rays

D. 2 mm Al HVL x-rays

E. 1 mm Cu HVL x-rays

A

E. 1mm Cu HVL x-rays

–Scatter is associated with compton interaction. At 2 mm Al HVL there is a considerable amount of photoelectric interactions. Above about 1 mm Cu HVl, photoelectic interaction are neglible and compton predominates.

–As the photon energy increases, more energy is transferred to the electron, and less to the scattered photon.

–The maximum backscatter is at about 0.7 mm Cu HVL.

109
Q

Q1291. Please see attached chart.

The MU setting to deliver 180 cGy at a depth of 5 cm, at 100 cm SSD, for a field of equivalent square 8x8 cm is ____ MU

A. 106

B. 153

C. 198

D. 204

E. 212

A

E. 212

SSD setup so need to use PDD; which accounts for both inverse square and depth

1 MU = 1 cGy at standardized conditions, so:

180 cGy / [(PDD 8x8 @5cm) x (Output 8x8 @ 100 cm SSD)]

= 180/ (0.862 x 0.985)

= 212

110
Q

Q1295. Please see attached chart.

The MU setting to deliver 180 cGy at a depth of 5 cm, at 100 cm SSD, for a field of equivalent square 8x8 cm is 212 MU. The dose at 10 cm depth is ___ cGy.

A. 115

B. 139

C. 143

D. 170

E. 185

A

B. 139

Since you know the dose at d1, you can solve for dmax. The PDD @ 10 cm is given as 66.4%, so that’s 66.4% of dmax. (Dose at d1/ PDD1 = dmax)

Dose at d2 = (PDD2/PDD1) x Dose at d1

= (0.664/0.862) x 180

= 0.77 x 180

= 139

DO NOT do a simple inverse square (105/110)^2 ratio in this setting. PDD accounts for both inverse square AND attenuation so you would be artifically high using inverse square alone.

111
Q

Q1298. Please see attached chart.

The MU setting per beam to deliver 250 cGy total to the isocenter via parallel opposed, 23x18 cm whole brain fields, for a patient separation of 15 cm is ___ MU.

A. 130

B. 156

C. 182

D. 208

E. 265

A

A. 130

First off calculate your equivalent square using Sterling’s formula, where the length of one side of your equivalent square = 4 x area/ perimeter

4 x (23x18)/ (2 x (23+18)) = 20; so you have a 20 x 20 equivalent square

Distance to deposit dose is in the middle of the patient, so depth is 15 cm/ 2 or 7.5 cm

Picking SAD: (250 cGy/2)/ (TMR 20x20 @ 7.5 cm) x (OF 20x20 @ 100 SAD)

= 125/(0.88*1.089) = 130

112
Q

Q1300. Please refer to the attached chart

A 6 MV anterior R supraclavicular field is set up at 100 cm SSD to the center. The prescribed dose is 200 cGy to the supraclavicular point (102 cm SSD), at depth 3 cm. Ignoring off-axis factors the MU setting is ___:

A. 213

B. 209

C. 205

D. 201

E. 194

A

A. 213

SSD setup, so use PDD and take into account inverse square. Dmax is given to you at the PDD of 100 at 1.6 cm.

Account for the difference in the SSD setup originally for dmax (which is 101.6 cm) and the new distance to SSD on the actual treatment at 102 cm, which is 2 cm further than the original setup (so now your dmax is actually at 101.6 + 2 additional cm).

200/ [(PDD@3) x (inv sq) x (OF@ 100 cm SSD)]

= 200/ [0.956 x ((101.6)/(101.6+2))^2 x 1.019)

= 213

113
Q

Q1303. Refer to attached chart. The Monitor Unit (MU) setting to deliver 180 cGy at 5 cm depth to a 6 x 28 cm2 field at 100 cm SSD is ___

A. 180

B. 191

C. 199

D. 207

E. 215

A

D. 207

SSD, so will use PDD chart

6 x 28 cm field equivalent square is 4x(6x28)/(2x(6+28)) = 2x6x28/(6+28) = 9.88

Use 10 x 10 cm field size at 5 cm depth; thus referring to the chart the PDD is 87.1

SSD output at depth 1.6, SSD 100 cm is 1.0 for 10x10

MU = 180/(0.871 x 1.0) = 207

114
Q

Q1306. A patient is to be irradiated to a depth of 7 cm using a field size of 10 x 10 cm at 80 cm SSD. The PDD at this point is 65% and the dose rate at dmax is 100 cGy/min. The time to deliver 150 cGy is ___ min.

A. 0.65

B. 1.25

C 1.5

D 2.3

E. 2.7

A

D 2.3

MU rate = Dose at depth/(Output at dmax x PDD at depth)

MU rate = 150 cGy / (100 cGy/min x 0.65)

MU rate = 2.31 min

115
Q

Q1307. A patient is simulated with a 10x10 cm field at 80 cm SAD to deliver 200 cGy at 8 cm depth on a Co-60 unit. If technique is now changed to 80 cm SSD, what values are required to calculate the timer setting?

  1. PDD for a 10x10 cm field, 8 cm depth, 80 cm SSD
  2. Dose rate in air at 80 cm for a 10x10 cm field
  3. Dose rate in air at 80.5 cm for a 10x10 cm field
  4. Dose rate at 80.5 cm in air for a 9x9 cm field
  5. TAR for a 10x10 cm field at 8 cm depth
  6. Backscatter factor for a 10x10 cm field
  7. Backscatter factor for a 9x9 cm field
  8. PDD for a 9x9 cm field, 8 cm depth, 80 cm SSD

A. 4,7,8

B. 3, 6, 1

C. 2, 6, 5

D. 4, 5

E. 2, 8

A

D. 4, 5

A field size of 10 cm at the tumor (8 cm depth) requires a field size of 10 x (80)/(88) = 9 cm on the surface at 80 cm SSD.

At treatment SSD, Dose Rate = DR air at 80.5 cm x SBF for field size at the skin. PDD =PDD for field size at the surface and depth to prescription point.

Time = D/(DR x PDD)

116
Q

Q1310. A single direct field is set up at 80 cm SSD. The prescribed dose is 3000 cGy in 10 fractions at 5 cm depth. The dose rate at dmax is 100 cGy/min. The PDD at D5cm = 78%. The timer setting and dose at dmax are:

A. 3.00 min and 385 cGy

B. 3.00 min and 300 cGy

C. 3.85 min and 300 cGy

D. 3.85 min and 385 cGy

A

D. 3.85 min and 385 cGy

Timer setting = dose at depth/(dose rate at Dmax x PDD)

=300/(100 x 0.78)

= 3.85 min

Given dose at 5 cm depth = 78% of dose at dmax

Dose at depth/PDD = 300/0.78 = 385 cGy

117
Q

Q1311. Which of the following would be a correct formula to calculate the timer setting for the following? A single posterior spine field is treated on 80 SSD on a Co-60 unit, dose per fraction is 300 cGy at 3 cm dpeth; field size on skin 6x12 cm (assume equivalent square = 8 cm).

A. t=30/((Dose rate in air at 30 cm) x TAR (8x8, d3cm))

B. t=300/(Dose rate at dmax, 80 cm SSD)

C. t=300/((Dose rate in air at 80 cm) x PDD (8x8, d3cm))

D. t=300/((Dose rate at dmax at 80 cm SSD) x PDD (8x8, d3cm))

E. t=300/((Dose rate at dmax at 80 cm SAD) x BSF (8x8))

A

D. t=300/((Dose rate at dmax at 80 cm SSD) x PDD (8x8, d3cm))

118
Q

Q1316. The dose rate in air for a 10x10 cm Co-60 field is 100 cGy/min at 80 SAD. The BSF = 1.035. The dose rate in tissue at depth=dmax, 80 cm SSD is:

A. 103.5 cGy/min

B. 102.2 cGy/min

C. 100 cGy/min

D. 115 cGy/min

E. 125 cGy/min

A

B. 102.2 cGy/min

100cGy/min x 1.035 x (80/80.5)2

= 102.2 cGy/min

119
Q

Q1324. Use the attached chart. For parallel opposed 80 cm SAD fields, separation 18 cm, field size at midplane 12x12 cm, 200 cGy total dose per fraction, the timer setting per beam is:

A. 1.07 min

B. 1.11 min

C. 1.15 min

D. 1.39 min

E. 1.41 min

A

B. 1.11 min

Parallel opposed, 18 cm separation means 100 cGy per beam delivered to 9 cm depth each

SAD setup, use TAR for timer setting

100/(TAR@d9cm for 12x12)x(DR air @80 cm for 10x10)x(OF air 12x12))

= 100/(0.775 x 115 x 1.013)

= 1.11 min

120
Q

Q1326. If 4000 cGy is delivered to a patient’s mediastinum via AP/PA fields, the lowest total dose at dmax is obtained using:

A. Co-60, 80 cm SSD.

B. 6 MV photons, isocentric fields.

C. 6 MV photons, 100 cm SSD.

D. 18 MV photons, 100 cm SSD.

E. 18 MV photons, isocentric fields.

A

D. 18 MV photons, 100 cm SSD.

–Dose at dmax, expressed as a percent of dose at midplane for parallel opposed fields decreases with increasing energy and increasing SSD.

121
Q

Q1328. The equivalent square of a 6x30 cm photon beam is a square CxC cm, where C is:

A. Closer to 30 than 6.

B. Equal to the square root of (6x30).

C. The side of the square field which has the same PDD as the rectangular field.

D. Is approximately equal to the (area / perimeter) for the rectangle.

A

C. The side of the square field which has the same PDD as the rectangular field.

122
Q

Q1330.

A