Nuclear Safety Officer CCRPNSO Exam
**Question 1.** Which type of ionizing radiation has the highest linear energy transfer (LET) in
biological tissue?
A) Gamma rays
B) Beta particles
C) Alpha particles
D) Neutrons
Answer: C
Explanation: Alpha particles are heavy, doubly‑charged particles that deposit energy densely
along their short paths, giving them the highest LET among common radiations.
**Question 2.** The photoelectric effect predominates in which photon energy range for
interactions with high‑Z materials?
A) < 30 keV
B) 100 keV – 1 MeV
C) > 5 MeV
D) 10 MeV – 20 MeV
Answer: A
Explanation: The photoelectric effect dominates at low photon energies, especially below
~30 keV, and its probability increases with atomic number (Z³).
**Question 3.** In the International System of Units, what is the relationship between the Gray
(Gy) and the Rad?
A) 1 Gy = 0.01 rad
B) 1 Gy = 100 rad
C) 1 Gy = 10 rad
D) 1 Gy = 0.1 rad
Answer: B
, AIEHS Certified Chief Radiation Protection
Nuclear Safety Officer CCRPNSO Exam
Explanation: 1 Gray equals 100 rad; the Gray measures absorbed dose (J kg⁻¹) while the rad is
the older unit (0.01 Gy).
**Question 4.** Which of the following best describes a deterministic radiation effect?
A) Probability increases linearly with dose without a threshold.
B) Effects appear only after a certain dose threshold is exceeded.
C) Genetic mutations inherited by offspring.
D) Stochastic cancer induction that cannot be predicted for an individual.
Answer: B
Explanation: Deterministic effects, such as skin erythema or cataract formation, have dose
thresholds; severity rises with dose above that level.
**Question 5.** The Linear No‑Threshold (LNT) model is primarily used to estimate risk for
which type of radiation effect?
A) Deterministic skin burns
B) Stochastic cancer induction
C) Acute radiation syndrome
D) Radiation‑induced infertility
Answer: B
Explanation: LNT assumes that any incremental dose, no matter how small, carries a
proportional increase in stochastic cancer risk.
**Question 6.** Which occupational dose limit for whole‑body exposure is recommended by
the ICRP for radiation workers?
A) 5 mSv yr⁻¹
B) 20 mSv yr⁻¹
C) 50 mSv yr⁻¹
, AIEHS Certified Chief Radiation Protection
Nuclear Safety Officer CCRPNSO Exam
D) 100 mSv yr⁻¹
Answer: B
Explanation: The International Commission on Radiological Protection (ICRP) recommends an
occupational limit of 20 mSv per year averaged over 5 years, with no more than 50 mSv in any
single year.
**Question 7.** A thermoluminescent dosimeter (TLD) measures dose by:
A) Counting ion pairs in a gas.
B) Detecting scintillation photons.
C) Recording trapped electrons released as light when heated.
D) Measuring current produced in a semiconductor.
Answer: C
Explanation: TLDs store energy from radiation in crystal lattice defects; heating releases the
trapped electrons as visible light proportional to the absorbed dose.
**Question 8.** Which detector type is most suitable for rapid identification of gamma‑ray
energies in the field?
A) Geiger‑Müller tube
B) Proportional counter
C) Scintillation detector (NaI(Tl))
D) Silicon diode detector
Answer: C
Explanation: NaI(Tl) scintillation detectors have good efficiency and energy resolution for
gamma spectroscopy, allowing quick identification of photon energies.
**Question 9.** The International Atomic Energy Agency (IAEA) publishes which series of safety
standards that are globally recognized?
, AIEHS Certified Chief Radiation Protection
Nuclear Safety Officer CCRPNSO Exam
A) ISO 9000 series
B) IAEA Safety Standards Series (SSS)
C) ASTM International standards
D) EN (European Norm) series
Answer: B
Explanation: The IAEA Safety Standards Series provides guidance on radiation protection, waste
management, and nuclear safety used worldwide.
**Question 10.** In a nuclear licensing application, the “Safety Analysis Report” (SAR) primarily
demonstrates:
A) Financial viability of the project.
B) Compliance with environmental impact regulations.
C) That the facility will operate within acceptable safety limits under normal and accident
conditions.
D) The marketing plan for the plant’s electricity.
Answer: C
Explanation: The SAR details design, analysis, and safety measures proving the plant can be
operated safely under both routine and abnormal scenarios.
**Question 11.** Which of the following best defines “ALARA”?
A) A legal limit for annual radiation dose.
B) A principle to keep exposures “As Low As Reasonably Achievable”.
C) A type of personal protective equipment.
D) A method for calculating shielding thickness.
Answer: B
Explanation: ALARA is a radiation protection principle that encourages minimizing exposures
through practical means, balancing cost, benefit, and feasibility.