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Pennsylvania Nuclear Engineer Exam – Practice Questions & Correct Answers (Verified Answers) with Detailed Rationales | PE Nuclear CBT Exam Prep

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This comprehensive practice exam is designed for engineers and professionals preparing for the Pennsylvania Nuclear Engineer Licensing Examination, which is administered as the NCEES Principles and Practice of Engineering (PE) Nuclear Exam. The content is updated for the 2025/2026 testing cycle and features expertly designed, exam-style multiple-choice questions that closely mirror the format and rigor of the actual PE Nuclear CBT exam. The PE Nuclear exam is a 9.5-hour computer-based test containing 85 questions covering five major specification areas: Radiological Analysis and Consequences, Nuclear Fuel Cycle, Nuclear Systems and Components, Reactor Physics and Criticality Safety, and Safety Analysis. Candidates must pass this exam to earn professional engineering licensure in Pennsylvania, which recognizes nuclear engineering as a major branch of engineering practice. Key topics covered include: Reactor Physics and Neutronics – Neutron life cycle, effective multiplication factor (keff), neutron flux, cross sections, diffusion theory, delayed neutrons, fission product poisoning (xenon-135, samarium), control rod worth, reactivity coefficients (temperature, void, Doppler), and reactor kinetics. Nuclear Fuel Cycle – Uranium enrichment (U-235), fuel design and performance, cladding materials (zirconium alloys), burnup, transmutation, spent fuel composition, plutonium-239 production, and fuel cycle processes. Thermodynamics and Heat Transfer – Rankine cycle, pressurized water reactor (PWR) primary/secondary loops, boiling water reactors (BWR), steam generators, heat exchangers, natural circulation, and critical heat flux. Materials and Structural Engineering – Zirconium alloys (low neutron absorption, corrosion resistance), graphite as a moderator, stainless steel components, cladding integrity, embrittlement from neutron irradiation, swelling from fission gas accumulation, and displacement per atom (dpa) for radiation damage. Reactor Safety and Regulations – Containment building purpose, Emergency Core Cooling Systems (ECCS), Nuclear Regulatory Commission (NRC) oversight, SCRAM (rapid shutdown), design-basis accident analysis, probabilistic risk assessment (PRA), and ALARA principles. Radiation Protection and Health Physics – Dose limits, dosimetry, half-value layer, shielding materials (hydrogenous materials for neutrons), contamination control, and radiation detection. Sample Questions (from the exam): The neutron life cycle in a reactor includes all the following EXCEPT: a) Fission neutron production b) Fast neutron slowing down c) Thermal neutron absorption d) Moderation Answer: a – Fission neutron production is part of the cycle, not a separate life stage; the life cycle refers to neutron behavior after production. The effective multiplication factor keff=1 indicates: a) Subcritical reactor b) Critical reactor c) Supercritical reactor d) Reactor shutdown Answer: b – keff=1 means each fission leads to exactly one subsequent fission on average

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PENNSYLVANIA NUCLEAR ENGINEER EXAM
QUESTIONS AND CORRECT ANSWERS (VERIFIED
ANSWERS) PLUS RATIONALES 2025|2026 Q&A |
INSTANT DOWNLOAD PDF
1. The neutron life cycle in a reactor includes all the following EXCEPT:
• a) Fission neutron production
• b) Fast neutron slowing down
• c) Thermal neutron absorption
• d) Moderation
Rationale: Fission neutron production is part of the cycle, not a separate life stage;
the life cycle refers to neutron behavior after production.
2. The effective multiplication factor keff=1keff=1 indicates:
• a) Subcritical reactor
• b) Critical reactor
• c) Supercritical reactor
• d) Reactor shutdown
Rationale: keff=1keff=1 means each fission leads to exactly one subsequent fission
on average.
3. Which material is commonly used as a moderator in light water reactors?
• a) Water
• b) Graphite
• c) Heavy water
• d) Boron carbide

,4. The delayed neutron fraction is important for:
• a) Fuel enrichment
• b) Reactor control and stability
• c) Waste disposal
• d) Heat transfer
5. The primary fissile isotope used in most commercial reactors is:
• a) U-235
• b) Pu-239
• c) Th-232
• d) U-238
6. Fast reactors primarily rely on:
• a) Moderation by light water
• b) Fast neutrons without moderation
• c) Graphite moderation
• d) Heavy water moderation
7. Neutron flux is defined as:
• a) Energy released per fission
• b) Rate of fission reactions
• c) Number of neutrons per unit area per unit time
• d) Total neutron population
8. Control rods in a nuclear reactor primarily:
• a) Increase thermal conductivity
• b) Increase fuel enrichment
• c) Absorb neutrons

, • d) Slow down neutrons
9. A reactor is considered supercritical if keffkeff is:
• a) <1
• b) >1
• c) =1
• d) ≤0
10. In a PWR, the primary coolant loop:
• a) Directly drives turbines
• b) Transfers heat to the secondary loop
• c) Is open to the atmosphere
• d) Contains boron only in trace amounts


11–20: Thermodynamics & Heat Transfer
11. The Rankine cycle is used in nuclear power plants for:
• a) Converting thermal energy to electrical energy
• b) Enriching fuel
• c) Reactor cooling
• d) Controlling neutron flux
12. The boiling point of water increases in a pressurized reactor due to:
• a) Neutron flux
• b) Elevated pressure
• c) Moderator presence
• d) Control rods
13. The heat transfer in a fuel rod is primarily by:

Información del documento

Subido en
21 de julio de 2026
Número de páginas
22
Escrito en
2025/2026
Tipo
Examen
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