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Pennsylvania Nuclear Engineer Exam | 100 Q&A PE Nuclear Verified Rationales | PDF

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Pass your PA nuclear engineer PE exam with 100 verified practice questions & rationales. Covers reactor physics, thermodynamics, NRC regulations, fuel cycle. PDF.nuclear engineer exam, PE nuclear exam prep, reactor physics study guide, NRC licensing test, nuclear power plant exam, nuclear engineering certification, reactor operator test, nuclear thermodynamics exam, nuclear fuel cycle study, radiation protection test, nuclear safety exam, PWR BWR reactor test, nuclear materials exam, criticality safety study, nuclear waste management test, nuclear professional exam, power reactor physics, nuclear engineering career, nuclear PE practice test, nuclear regulatory exam

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PENNSYLVANIA NUCLEAR ENGINEER EXAM b b b




QUESTIONS AND CORRECT ANSWERS (VERIFIED
b b b b b




ANSWERS) PLUS RATIONALES 2026|2027 Q&A |
b b b b b b




INSTANT DOWNLOAD PDF
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1. The neutron life cycle in a reactor includes all the following EXCEPT:
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 a) Fission neutron production
b b b




 b) Fast neutron slowing down
b b b b




 c) Thermal neutron absorption
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 d) Moderation
b




Rationale: Fission neutron production is part of the cycle, not a separate life
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stage; the life cycle refers to neutron behavior after production.
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2. The effective multiplication factor keff=1keff=1 indicates:
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 a) Subcritical reactor
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 b) Critical reactor
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 c) Supercritical reactor
b b




 d) Reactor shutdown
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Rationale: keff=1keff=1 means each fission leads to exactly one subsequent fission
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on average.
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3. Which material is commonly used as a moderator in light water reactors?
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 a) Water
b




 b) Graphite
b




 c) Heavy water
b b




 d) Boron carbide
b b

,4. The delayed neutron fraction is important for:
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 a) Fuel enrichment
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 b) Reactor control and stability
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 c) Waste disposal
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 d) Heat transfer
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5. The primary fissile isotope used in most commercial reactors is:
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 a) U-235
b




 b) Pu-239
b




 c) Th-232
b




 d) U-238
b




6. Fast reactors primarily rely on:
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 a) Moderation by light water
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 b) Fast neutrons without moderation
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 c) Graphite moderation
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 d) Heavy water moderation
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7. Neutron flux is defined as:
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 a) Energy released per fission
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 b) Rate of fission reactions
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 c) Number of neutrons per unit area per unit time
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 d) Total neutron population
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8. Control rods in a nuclear reactor primarily:
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 a) Increase thermal conductivity
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 b) Increase fuel enrichment
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 c) Absorb neutrons
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,  d) Slow down neutrons
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9. A reactor is considered supercritical if keffkeff is:
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 a) <1
b




 b) >1
b




 c) =1
b




 d) ≤0
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10. In a PWR, the primary coolant loop:
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 a) Directly drives turbines
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 b) Transfers heat to the secondary loop
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 c) Is open to the atmosphere
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 d) Contains boron only in trace amounts
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11–20: Thermodynamics & Heat Transfer
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11. The Rankine cycle is used in nuclear power plants for:
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 a) Converting thermal energy to electrical energy
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 b) Enriching fuel
b b




 c) Reactor cooling
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 d) Controlling neutron flux
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12. The boiling point of water increases in a pressurized reactor due to:
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 a) Neutron flux
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 b) Elevated pressure
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 c) Moderator presence
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 d) Control rods
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13. The heat transfer in a fuel rod is primarily by:
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