Question 1

In nuclear reactor engineering, what is the primary function of a moderator within the core? Choose the best description that reflects standard terminology (i.e., how the moderator affects neutron energies and fission probability), without focusing …

Accepted Answer

Introduction / Context: In a thermal nuclear reactor, the moderator is a core material that changes the energy spectrum of neutrons. Most fissions in fuels like uranium-235 happen much more readily with slow (thermal) neutrons than with fast ones. The moderator’s job is to reduce neutron kinetic energy efficiently while avoiding excessive neutron absorption, thereby sustaining a stable, controllable chain reaction. Given Data / Assumptions: The reactor is a thermal system (e.g., PWR, BWR, PHWR, graphite-moderated types). Fission cross section for U-235 rises sharply as neutron energy drops from fast to thermal range. Common moderators: light water, heavy water, graphite; each has low absorption and good scattering characteristics. Concept / Approach: Elastic scattering with low-atomic-mass nuclei removes energy from neutrons in many small steps. An effective moderator has a small microscopic absorption cross section and a favorable scattering cross section so that neutron losses are minimized while the spectrum softens. The control of neutron population (and thus power) is primarily performed by control rods and soluble poisons; the moderator’s role is spectral, not regulatory. Step-by-Step Solution: Identify what sustains fission in thermal reactors: a supply of thermal neutrons.Relate moderation to neutron energy: repeated scattering slows neutrons.Separate functions: moderator sets spectrum; control rods set reactivity by absorption.Choose the statement that highlights slowing down neutrons with minimal capture. Verification / Alternative check: Standard reactor physics texts depict the “slowing-down region” of neutron life cycle, where moderators bring neutrons from MeV to eV energies before thermalization, maximizing thermal fission probability in U-235 or Pu-239 fuel regions. Why Other Options Are Wrong: Absorb neutrons: that would be a poison or control material, not a moderator.Control the chain reaction directly: that is the job of control rods/soluble boron.None of these / Increase energy: contradicts the definition of moderation. Common Pitfalls: Confusing moderation (energy reduction) with reactivity control (neutron removal). Also, assuming all moderators are equally effective; absorption penalties differ widely (e.g., heavy water versus light water). Final Answer: Slow down fast neutrons to thermal energies without capturing too many of them

Question 2

Alpha decay bookkeeping: when the isotope 92U238 emits one alpha (α) particle, what is the resulting daughter nuclide (give the correct element and mass/atomic numbers)?

Accepted Answer

Introduction / Context: Alpha decay subtracts a helium nucleus (two protons and two neutrons) from a parent nuclide. Correctly writing alpha-decay products is a foundational skill in nuclear chemistry and reactor physics because it enforces conservation of nucleon number and charge while identifying the right element symbol from the periodic table. Given Data / Assumptions: Parent: 92U238 (uranium-238). One alpha particle emitted: 2 protons + 2 neutrons, symbolically 2He4. Mass number and atomic number must be conserved. Concept / Approach: Conservation relations for alpha decay are straightforward: A_daughter = A_parent − 4, Z_daughter = Z_parent − 2. Subtracting 2 from Z changes the chemical element to the one two places earlier in the periodic table. For uranium (Z = 92), the daughter has Z = 90, which corresponds to thorium (Th). The mass number decreases from 238 to 234. Step-by-Step Solution: Write A_parent = 238, Z_parent = 92.Apply alpha emission: A_daughter = 238 − 4 = 234; Z_daughter = 92 − 2 = 90.Map Z_daughter = 90 to element symbol: Th (thorium).State daughter nuclide: 90Th234. Verification / Alternative check: Check conservation explicitly: Left side nucleons 238, right side 234 + 4 = 238; charges 92, right side 90 + 2 = 92. Both balances hold, confirming the result. Why Other Options Are Wrong: 90U234: Wrong element; Z = 90 is thorium, not uranium.90Pa234: Protactinium is Z = 91, not 90; also alpha decay from U-238 goes to Th-234.92U236: Would require neutron emission, not alpha; alpha decay lowers Z by 2.88Ra234: Z = 88 would require emitting more than an alpha or a different decay chain. Common Pitfalls: Keeping the element symbol as U after changing Z, or mixing up Pa (Z = 91) and Th (Z = 90). Always translate atomic number to the correct periodic symbol after the arithmetic. Final Answer: 90Th234

Question 3

Orders of magnitude: the ratio of a typical atomic radius to a typical nuclear radius is approximately equal to which power of ten?

Accepted Answer

Introduction / Context: Physics relies heavily on orders of magnitude to compare very different length scales. Understanding how atomic sizes compare to nuclear sizes helps explain why matter is mostly empty space and why nuclear forces act over extremely short ranges compared with electromagnetic interactions in atoms. Given Data / Assumptions: Atomic radius scale: about 1 angstrom, which is 1 Å = 10^-10 m. Nuclear radius scale: about a few femtometres, e.g., 1 fm = 10^-15 m. We need the ratio r_atom / r_nucleus. Concept / Approach: Compute the ratio using canonical scales. If r_atom ≈ 10^-10 m and r_nucleus ≈ 10^-15 m, then r_atom / r_nucleus ≈ 10^-10 / 10^-15 = 10^5. While precise values vary by element and isotope (nuclear radius roughly scales as r0 * A^(1/3)), the 10^5 figure is the widely accepted order-of-magnitude comparison. Step-by-Step Solution: Set r_atom ≈ 10^-10 m (angstrom scale).Set r_nucleus ≈ 10^-15 m (femtometre scale).Form ratio: r_atom / r_nucleus = 10^-10 / 10^-15.Simplify powers: 10^(-10 − (−15)) = 10^5. Verification / Alternative check: Realistic ranges (e.g., 0.5–2.5 Å for atoms and 4–7 fm for many nuclei) still deliver a ratio near 10^5 within a factor of a few, confirming the order-of-magnitude choice. Why Other Options Are Wrong: 10^8 or 10^12 or 10^15: Overstate the gap by several to many orders of magnitude.10^3: Understates the gap; nuclei are much smaller than atoms. Common Pitfalls: Confusing atom diameter with radius or using nanometres instead of angstroms without adjusting exponents, both of which can skew the ratio if not handled consistently. Final Answer: 10^5

Question 4

Half-life definition refresher: the time required for half of the __________ of a radioactive sample to undergo decay is called the half-life of that nuclide. Fill in the most precise word.

Accepted Answer

Introduction / Context: Radioactive decay is a stochastic process at the level of individual nuclei but produces a characteristic exponential law for large ensembles. The half-life is a core parameter in nuclear science, radiological protection, geochronology, and medical imaging, defining the time at which half the original radioactive nuclei have decayed. Given Data / Assumptions: We are discussing a specific radioactive nuclide. Terminology must be precise: decay refers to transformations of nuclei. Electrons, protons, and neutrons inside other contexts are not what “half-life” counts. Concept / Approach: The exponential decay law is N(t) = N0 * exp(−λt), where N(t) is the number of undecayed nuclei at time t and λ is the decay constant. The half-life t_1/2 satisfies N(t_1/2) = N0/2, which leads to t_1/2 = ln 2 / λ. The definition centers on the number of undecayed nuclei in the sample—neither electrons nor free protons are being “consumed” in the definition. Step-by-Step Solution: State the decay law for nuclei: N(t) = N0 * exp(−λt).Define half-life via N(t_1/2) = N0/2.Solve for t_1/2: t_1/2 = ln 2 / λ.Identify the quantity halved: the count of undecayed nuclei. Verification / Alternative check: Any standard text defines half-life with respect to a population of identical radioactive nuclei in a sample. Derived quantities like activity A(t) = λN(t) inherit the same time dependence. Why Other Options Are Wrong: Electrons/protons/neutrons: Not the counted entities in half-life definition; decay transforms nuclei.Atoms in the entire universe: Irrelevant and nonspecific. Common Pitfalls: Confusing “half-life of activity” with “half-life of mass”; while proportional for a single nuclide, activity is a rate variable derived from N(t), which counts nuclei. Final Answer: nuclei

Question 5

Fission fragment accounting: when a slow neutron is absorbed by 92U235 to form a compound nucleus that fissions into 54Xe139 and 38Sr94, how many neutrons are emitted along with the fission fragments?

Accepted Answer

Introduction / Context: Balancing nuclear reactions is a core competency in reactor physics and nuclear chemistry. It ensures conservation of nucleon number and charge, and it helps estimate neutron economy—vital for sustaining a chain reaction and for calculating reactivity and breeding ratios. Given Data / Assumptions: Incident: a slow neutron captured by 92U235. Fission products: 54Xe139 and 38Sr94. We must find the number of emitted neutrons, n_emitted. Concept / Approach: Use conservation of mass number (A) and atomic number (Z). On capture, 92U235 + 0n1 → 92U236* (compound). After fission, the sum of product mass numbers plus emitted neutrons must equal 236. Similarly, the sum of product atomic numbers must equal 92, which is satisfied by Z = 54 + 38 = 92 for xenon and strontium. Step-by-Step Solution: Compute compound mass number: 235 + 1 = 236.Sum fragment mass numbers: 139 + 94 = 233.Conservation of A: 236 = 233 + n_emitted ⇒ n_emitted = 3.Verify Z: 54 + 38 = 92; atomic number is conserved. Verification / Alternative check: This result matches common averages for U-235 thermal fission, where approximately 2–3 neutrons per fission are emitted, depending on fragment split and excitation energy; the exact integer here follows from the specified split. Why Other Options Are Wrong: 1 or 2: Would undercount mass number relative to 236.4 or 5: Would overcount relative to the specified fragment masses. Common Pitfalls: Forgetting to include the incident neutron in the compound nucleus mass number, or misadding the fragment masses and then forcing charge balance incorrectly. Final Answer: 3

Question 6

Origin of beta (β) particles: in radioactive beta decay, from which part of the atom are the emitted β particles produced?

Accepted Answer

Introduction / Context: Radioactive beta decay is a nuclear process, not an electronic or chemical one. In β− decay, a neutron in the nucleus converts into a proton, emitting an electron (the β− particle) and an antineutrino. In β+ decay, a proton converts into a neutron with emission of a positron (β+) and a neutrino, or electron capture occurs instead. Understanding the origin helps avoid conflating nuclear decay with atomic electron transitions. Given Data / Assumptions: We are considering radioactive β emission in nuclides. Atomic electron shells may respond (e.g., characteristic X-rays after EC), but they are not the source of β particles. β may mean β− (electron) or β+ (positron). Concept / Approach: β particles are created inside the nucleus during weak-interaction mediated transformations. They are not preexisting orbital electrons getting expelled. For β−, the process can be written qualitatively as n → p + e− + v̄; for β+, as p → n + e+ + v. These leptons are produced at the instant of decay and then exit the nucleus with a spectrum of kinetic energies characteristic of allowed/forbidden transitions. Step-by-Step Solution: Identify β emission as a nuclear decay mode.Recall β− and β+ fundamental transformations.Conclude that β particles are generated in the nucleus during these transformations.Select “Nucleus (via nuclear transformation).” Verification / Alternative check: Energy spectra of beta particles are continuous up to an endpoint, consistent with a three-body decay in the nucleus (lepton + neutrino), not with discrete electronic transitions. Why Other Options Are Wrong: Innermost/outermost shells: Atomic electrons may rearrange after decay but are not the source of β.None of these / chemical bonds: β emission is nuclear, not chemical. Common Pitfalls: Confusing β radiation with Auger electrons or characteristic X-rays that arise from atomic relaxation after electron capture, which are separate effects. Final Answer: Nucleus (via nuclear transformation)

Question 7

Concept check—pick the wrong statement about basic nuclear/particle facts (only one statement below is incorrect). Which one is it?

Accepted Answer

Introduction / Context: Many entry-level nuclear questions test whether you can separate accurate facts from plausible-sounding misconceptions. Electrons, positrons, protons, and alpha particles have well-established identities and masses that should be memorized for quick elimination logic in multiple-choice items. Given Data / Assumptions: Protium (ordinary hydrogen) has a nucleus consisting of a single proton. β− radiation consists of high-energy electrons emitted in nuclear decay. The electron-to-proton mass ratio is roughly 1/1836 (≈ 1/1800 by rough GK). Positron has the same mass as an electron but positive charge. Concept / Approach: Evaluate each statement against standard constants and identities. A positron (e+) is the electron’s antiparticle; its mass is identical to the electron’s, far lighter than a proton. Therefore, any statement claiming a positron is heavier than a proton is false. The other statements align with standard definitions: β− equals an electron; protium’s nucleus is a proton; and the widely used rounded mass ratio is acceptable. An alpha particle is indeed a helium-4 nucleus (2p + 2n). Step-by-Step Solution: Check Statement A: true for 1H1 (protium).Check Statement B: β− is an electron → true.Check Statement C: 1/1800 is a rounded figure close to 1/1836 → acceptable.Check Statement D: positron mass = electron mass ≪ proton mass → false.Check Statement E: alpha = 2p + 2n → true. Verification / Alternative check: Reference mass values: m_e ≈ 9.11e−31 kg, m_p ≈ 1.67e−27 kg (≈ 1836 m_e). Positron mass equals m_e; therefore it cannot be heavier than a proton. Why Other Options Are Wrong: A/B/C/E are consistent with textbook definitions and accepted constants.D contradicts the equality m_e = m_positron and the much larger proton mass. Common Pitfalls: Mixing up “antiparticle” with “heavier partner”; antiparticles mirror charge and certain quantum numbers, not mass magnitude relative to the corresponding particle. Final Answer: A positron is heavier than a proton.

Question 8

Safety comparison of common power reactor types: which reactor configuration is generally considered most prone to radiological hazards due to the working fluid path and in-core boiling characteristics?

Accepted Answer

Introduction / Context: Different reactor types manage the primary coolant and steam cycle differently, which affects how radioactive species might reach the power conversion equipment and the environment under fault conditions. A high-level GK comparison often asks which design is intrinsically more prone to radiological transport if barriers are breached. Given Data / Assumptions: We compare typical textbook features at a general level. In BWRs, boiling occurs in the core; the same water that becomes radioactive in the core goes to the turbine. In PWRs, a separate secondary loop generates steam, isolating primary radioactivity from the turbine. Concept / Approach: Because BWR steam is produced directly in the reactor core, the steam delivered to the turbine is part of the radioactive primary circuit. This can elevate the potential for radioactivity in turbine systems and, during abnormal events, increase pathways for release compared with systems in which the primary coolant is fully separated from the steam cycle. Gas-cooled and sodium-cooled reactors have different hazards (e.g., chemical reactivity of sodium), but the question focuses on radiological hazard potential linked to working fluid paths. Step-by-Step Solution: Identify which design sends primary working fluid to the turbine: BWR.Recognize that PWRs isolate primary radioactivity via steam generators.Note gas-cooled and sodium-cooled systems generally do not boil the primary in-core to drive the turbine directly.Select BWR as comparatively more prone to radiological hazards in GK framing. Verification / Alternative check: Plant system diagrams show the BWR’s single-loop direct cycle. Maintenance procedures in BWR turbine halls often include radiological controls not required in PWR secondary systems. Why Other Options Are Wrong: PWR/PHWR: Have primary–secondary separation, limiting turbine-side radioactivity.Gas-cooled reactors: Different considerations; not direct-cycle radioactivity to turbine.Sodium-cooled fast reactors: Chemical hazards are notable but radiological transport to turbines is not via direct boiling steam from core. Common Pitfalls: Conflating “hazard” broadly (chemical, thermal, neutronic) with the specific radiological transport pathway that the question targets. Final Answer: Boiling water reactor (BWR)

Question 9

Fast breeder reactor (FBR) essentials: which statement correctly reflects the coolant and moderation features of a typical FBR used for breeding fissile material?

Accepted Answer

Introduction / Context: Fast breeder reactors are designed to maintain a fast-neutron spectrum and convert fertile isotopes (like U-238) into fissile ones (like Pu-239) while generating power. Their thermal–hydraulic and neutronic choices differ from thermal reactors and are optimized for breeding ratios and core physics. Given Data / Assumptions: Fast spectrum is desired; moderators would thermalize neutrons and defeat this. Coolant selection must remove heat efficiently while preserving fast spectrum. Common FBR coolants: liquid sodium (sometimes sodium–potassium), occasionally lead or lead–bismuth in other fast designs. Concept / Approach: Liquid sodium has excellent thermal conductivity, a high boiling point, and low neutron moderation/absorption, making it a classic FBR coolant. The absence of a moderator is intrinsic to preserving fast neutrons needed for breeding and for fission in plutonium-rich fuels. Fuel types vary (MOX, metallic fuels with Pu/U mixtures), so insisting on U-235-only fuel is incorrect for typical FBRs. Step-by-Step Solution: Eliminate options involving moderators (graphite, helium as moderator) since FBRs are unmoderated.Eliminate light-water coolant: it moderates and is uncommon in fast-spectrum cores.Reject “U-235 only” fuel: FBRs commonly use Pu-bearing fuels (e.g., MOX).Select “molten sodium coolant and no moderator.” Verification / Alternative check: Summaries of prototype and experimental FBRs (e.g., FBTR, Phénix, BN-series) consistently use sodium coolant and exclude moderators in the fast core. Why Other Options Are Wrong: Graphite/light water/helium moderators: contradict “fast” spectrum.U-235-only fuel: not characteristic of breeder cores; Pu-rich fuels are standard. Common Pitfalls: Assuming any reactor that breeds must be moderated. “Breeder” refers to fissile production, not to neutron energy regime; a fast spectrum is typical for high breeding gain. Final Answer: Uses molten (liquid) sodium as the primary coolant and operates without a moderator

Question 10

Uranium ore knowledge check: among the common uranium-bearing minerals listed, which one typically contains the highest percentage of uranium by composition?

Accepted Answer

Introduction / Context: Identifying uranium-rich minerals is important in mining, fuel-cycle planning, and general science GK. Different ores vary widely in uranium concentration and in the presence of other actinides or rare-earth elements. Given Data / Assumptions: We compare representative uranium-bearing minerals. We seek the ore with the highest typical uranium percentage. Names may refer to mineral groups (e.g., uraninite/pitchblende) rather than strict chemical formulas. Concept / Approach: Pitchblende (also known as uraninite) is essentially uranium dioxide-rich mineral and is historically the most uranium-dense ore, often the primary source in high-grade deposits. Carnotite is a potassium–uranium–vanadium mineral with lower U content. Monazite sands are largely rare-earth phosphates with thorium and only modest uranium traces. Thorite is primarily a thorium mineral. “Rescolite” is not a standard uranium ore name in typical mining catalogs and may represent a distractor or misnomer. Step-by-Step Solution: Recall mineral compositions: uraninite (UO2±x) is highly uranium-rich.Compare with carnotite and monazite: uranium present but at lower percentages.Exclude thorium-dominant minerals (thorite) and nonstandard names.Select pitchblende/uraninite as the richest uranium ore. Verification / Alternative check: Historical mining records and geochemical references consistently cite high-grade uraninite/pitchblende veins as the most uranium-concentrated mineralized material used in extraction. Why Other Options Are Wrong: Carnotite: Uranium present but diluted by K and V components.Thorite: Predominantly thorium; not a high-U mineral.Rescolite: Not a recognized primary uranium ore.Monazite: Rare-earth phosphate with thorium; uranium is minor. Common Pitfalls: Assuming any actinide-bearing sand (monazite) is uranium-rich; many are thorium-dominant. Always match mineral identity with its primary actinide content. Final Answer: Pitchblende (uraninite)

Question 11

In nuclear power-plant cycles, which reactor type does not require a separate heat exchanger (steam generator) to supply steam to the power turbine, because steam is generated directly in the reactor vessel and sent to the turbine?

Accepted Answer

Introduction / Context: A key difference among commercial nuclear power reactor types is how they produce and deliver steam to the turbine. Some designs generate steam in a secondary loop via a steam generator (a type of heat exchanger), whereas others make steam directly inside the reactor vessel. Understanding this distinction is essential for comparing system complexity, contamination control, and component count. Given Data / Assumptions: We are comparing common thermal reactor types used for electricity generation. “Does not require a heat exchanger to supply steam” means turbine steam is produced in the reactor vessel itself and not in a separate steam generator. Options include molten-sodium-cooled, helium-cooled, boiling water, and pressurised water concepts. Concept / Approach: In a Boiling Water Reactor (BWR), feedwater enters the reactor vessel, where it is heated to saturation and allowed to boil within the core region. The resulting two-phase mixture is sent to internal steam separators and dryers; the dry steam is routed directly to the turbine. No separate steam generator is used. By contrast, Pressurised Water Reactors (PWRs) keep the primary water under high pressure to avoid boiling; heat is transferred to a secondary loop via a steam generator. Helium- and sodium-cooled reactors also transfer heat to a separate water/steam system to produce turbine steam. Step-by-Step Solution: Identify which design generates turbine steam inside the reactor vessel: the BWR.Note that PWRs necessarily use steam generators; sodium- and helium-cooled systems also need an intermediate steam-producing heat exchanger.Therefore, the reactor that does not require a separate steam generator is the Boiling Water Reactor. Verification / Alternative check: System schematics of BWRs show moisture separators/dryers inside the vessel and steam lines emerging directly to the turbine stop valves. PWR diagrams always include steam generators between the reactor coolant and the turbine cycle. Why Other Options Are Wrong: Molten sodium cooled: uses intermediate/steam generators for safety and chemistry reasons.Helium cooled: transfers heat to a separate steam or Brayton cycle unit.Pressurised water: requires steam generators by design. Common Pitfalls: Assuming “boiling” always implies a secondary loop; forgetting that “pressurised water” specifically avoids boiling in the primary loop and thus needs a steam generator. Final Answer: Boiling water

Question 12

In thermal nuclear reactors that use enriched uranium fuel, the typical maximum concentration of fissile U-235 is approximately what percentage (order-of-magnitude used in many textbook examples)?

Accepted Answer

Introduction / Context: Thermal power reactors moderated by light water generally require fuel enriched in the fissile isotope U-235 to maintain criticality and achieve practical core sizes and cycle lengths. Educational problems often quote a rounded “few percent” enrichment for simple estimates. Knowing the common enrichment range helps distinguish between natural-uranium, low-enriched, and highly enriched fuels. Given Data / Assumptions: “Thermal nuclear reactors” refers to common light-water reactors (PWR/BWR) in introductory contexts. Question seeks a representative maximum value used in basic problem statements, not the entire industrial range. Answer choices are 1, 2, 3, and 7 percent. Concept / Approach: Natural uranium contains about 0.711% U-235. Light-water reactors typically operate with low-enriched uranium, historically around 2% to 3% in many textbook examples, though modern cores may use 3%–5% or slightly higher depending on design and regulations. Within the options provided, 3% is the standard “typical maximum” value taught in foundational problems. Step-by-Step Solution: Recognize that 1%–2% may be insufficient for standard LWRs in classic examples.Identify the commonly cited educational figure: about 3% enrichment.Select 3 as the best representative maximum from the given choices. Verification / Alternative check: Introductory reactor engineering texts frequently compare natural uranium (0.711%) with “a few percent” enrichment for LWRs; 3% is a canonical round number in problems and MCQs. Why Other Options Are Wrong: 1 or 2 percent: below typical LWR practice in textbook problems.7 percent: exceeds the classic low-enrichment figures emphasized in entry-level questions and approaches ranges outside many historical baselines. Common Pitfalls: Confusing current industry practice (often >3%) with the simplified values used in examinations; mixing thermal-reactor enrichment with research or naval-reactor enrichments. Final Answer: 3

Question 13

Radioactive decay reasoning: a nuclide has a half-life of one month. Using count-rate (e.g., alpha counts per second) as a proxy for activity, which statement best describes the amount remaining after two and four months?

Accepted Answer

Introduction / Context: Half-life is the characteristic time over which a radioactive sample’s number of undecayed nuclei falls by half. Activity (count rate in a Geiger–Müller counter) is proportional to the number of undecayed nuclei, so it decays at the same exponential rate. This question tests correct qualitative reasoning about successive half-lives. Given Data / Assumptions: Half-life t1/2 = 1 month. Time intervals of interest: 2 months and 4 months. We assume a single nuclide with no replenishment and that count rate is proportional to the number of atoms remaining. Concept / Approach: After n half-lives, the remaining fraction is (1/2)^n. Disintegrated fraction = 1 − remaining fraction. For two months, n = 2; for four months, n = 4. Complete disintegration never occurs in a finite time for pure exponential decay. Step-by-Step Solution: Two months: n = 2 → remaining = (1/2)^2 = 1/4; disintegrated = 1 − 1/4 = 3/4.Four months: n = 4 → remaining = (1/2)^4 = 1/16, not 1/8; still not zero.Thus, the only correct statement in the list is that 3/4 will have disintegrated in two months. Verification / Alternative check: Successive-halving check: 1 → 1/2 (1 month) → 1/4 (2 months) → 1/8 (3 months) → 1/16 (4 months). This confirms the fractions. Why Other Options Are Wrong: Completely disintegrate in two or four months: exponential decay never reaches zero in finite time.1/8 remaining at four months: incorrect; 1/8 corresponds to three months, not four. Common Pitfalls: Mistaking linear for exponential behavior; assuming “complete” decay at a multiple of the half-life; mixing up the numbers after three and four half-lives. Final Answer: 3/4th of it will disintegrate in two months.

Question 14

Uranium enrichment basics: enrichment is performed to increase the concentration of which isotope in natural uranium for use as nuclear fuel?

Accepted Answer

Introduction / Context: Natural uranium consists primarily of U-238 with a small fraction of U-235, the fissile isotope that readily undergoes fission with thermal neutrons. Many reactor designs require an increased proportion of U-235 to achieve criticality and practical performance, motivating enrichment technologies. Given Data / Assumptions: Natural uranium composition: ~99.3% U-238 and ~0.711% U-235 (trace U-234). Goal of enrichment: improve fissile content for reactor fuel. Choices include fertile isotopes and non-uranium options. Concept / Approach: Enrichment processes (gaseous diffusion, centrifuges, laser-based methods) separate isotopes based on small mass differences to increase the U-235 content. U-233 is bred from thorium, and Pu-239 is bred from U-238; neither is increased by “uranium enrichment” of natural uranium feedstock. Step-by-Step Solution: Identify the fissile isotope in natural uranium: U-235.Recognize enrichment increases U-235 fraction while decreasing U-238 fraction.Select U-235 as the target of enrichment. Verification / Alternative check: Fuel specifications for light-water reactors cite low-enriched uranium (LEU) with a few percent U-235, directly reflecting enrichment objectives. Why Other Options Are Wrong: U-238: the dominant fertile isotope; its fraction is reduced during enrichment.U-233: not present in natural uranium; obtained via thorium fuel cycle.Pu-239: produced by neutron capture in U-238 followed by beta decays, not by isotope enrichment of uranium. Common Pitfalls: Confusing enrichment (isotopic separation) with breeding (neutron-induced transmutation); assuming all fissile isotopes are increased by the same process. Final Answer: U-235

Question 15

Nuclear notation refresher: if an element has mass number A and atomic number Z, what is the number of neutrons present in one atom of that element?

Accepted Answer

Introduction / Context: Mass number (A) and atomic number (Z) are the two integers that uniquely characterize a nuclide. A equals the total number of nucleons (protons plus neutrons) in the nucleus; Z is the number of protons. Determining the neutron count is a straightforward but critical operation in nuclear chemistry and reactor physics. Given Data / Assumptions: A = total nucleons in the nucleus (protons + neutrons). Z = number of protons (defines the element). We seek the number of neutrons, N. Concept / Approach: By definition, A = Z + N. Rearranging gives N = A − Z. This relationship is used universally in isotope notation, reaction balancing, and neutron economy calculations in reactor design. Step-by-Step Solution: Write the identity: A = Z + N.Solve for N: N = A − Z.Select the choice that matches N = A − Z. Verification / Alternative check: Example: for 235U, A = 235, Z = 92 → N = 235 − 92 = 143, consistent with standard nuclear data tables. Why Other Options Are Wrong: A + Z double-counts protons and is physically meaningless as a neutron count.A alone ignores the proton contribution.Z alone counts protons, not neutrons. Common Pitfalls: Confusing mass number with atomic mass (a real-number mass in units); forgetting that electrons are not part of A or Z. Final Answer: A- Z

Question 16

Why uranium dioxide (UO2) is preferred over metallic uranium as reactor fuel: which combination of material properties correctly explains the choice for most power-reactor fuel?

Accepted Answer

Introduction / Context: Most commercial power reactors employ uranium dioxide (UO2) fuel pellets inside zirconium alloy cladding rather than metallic uranium. Material selection balances thermal, mechanical, chemical, and neutronic constraints to ensure reliable performance across long irradiation cycles. Given Data / Assumptions: We compare bulk material properties relevant to reactor operation. Focus is on melting point, irradiation stability, chemical behavior, and density. General power-reactor context (e.g., PWR/BWR fuel). Concept / Approach: UO2 is a refractory ceramic with a very high melting point (~2800°C) and strong chemical stability under appropriate coolant chemistry. It resists radiation-induced swelling and phase changes better than metallic uranium, which has multiple allotropic forms and a much lower melting point (~1132°C). Although metallic uranium has higher density and thermal conductivity, its metallurgical complexities and lower melting point make it less suitable for standard light-water reactors. Step-by-Step Solution: Check (a): UO2 higher melting point than U metal → true.Check (b): UO2 does not have higher density than uranium metal; U metal is denser (~19 g/cm^3) than UO2 (~10.5–11 g/cm^3) → false.Check (c): As a ceramic, UO2 exhibits good irradiation stability and chemical compatibility in fuel–cladding–coolant systems → true.Therefore, the correct combined choice is “Both (a) and (c).” Verification / Alternative check: Standard fuel handbooks list UO2 pellet properties, including high melting point and acceptable irradiation performance; metallic uranium fuels were used historically but presented dimensional instability and metallurgical challenges. Why Other Options Are Wrong: (b) Incorrect: density comparison is the opposite; uranium metal is denser than UO2.“All (a), (b), and (c)” is invalid because (b) is false. Common Pitfalls: Equating higher density with universally better fuel without considering thermal margins and stability; assuming ceramics are inferior due to lower thermal conductivity while ignoring their high melting point and stability advantages. Final Answer: Both (a) and (c).

Question 17

Fast breeder reactor physics: which moderator is used in a fast breeder reactor to slow down neutrons?

Accepted Answer

Introduction / Context: Neutron spectrum control is central to reactor design. Thermal reactors rely on moderators to slow neutrons, whereas fast reactors are designed to maintain a fast (high-energy) spectrum to improve breeding of fissile material from fertile isotopes and to exploit fast-fission characteristics. Given Data / Assumptions: We consider fast breeder reactors (FBRs), which aim for breeding ratios above 1. Options list common moderator materials and a “No” option. Question asks what moderator is used to slow down neutrons in an FBR. Concept / Approach: Fast reactors intentionally avoid moderators because moderating collisions would soften the spectrum, reducing breeding gains and altering cross sections unfavorably. Designs therefore employ coolants with low moderating power, such as liquid sodium, lead, or lead–bismuth, and minimize hydrogenous materials in the core region. Step-by-Step Solution: Recognize that the defining feature of an FBR is a fast neutron spectrum.Moderators like light water, heavy water, graphite, or beryllium would slow neutrons, contrary to FBR goals.Hence, the correct choice is that no moderator is used. Verification / Alternative check: Operational and prototype FBRs (e.g., sodium-cooled designs) exclude moderators and are configured to keep leakage and spectral softening minimal. Why Other Options Are Wrong: Graphite/heavy water/beryllium: all are moderator materials used in thermal reactors; using them would defeat the fast spectrum purpose. Common Pitfalls: Assuming every reactor needs a moderator; confusing reflector materials with moderators. Final Answer: No

Question 18

Nuclear Fuel Complex (NFC), Hyderabad: which activity best describes its primary role in India’s nuclear fuel cycle?

Accepted Answer

Introduction / Context: India’s nuclear sector distributes functions across specialized facilities. The Nuclear Fuel Complex (NFC) in Hyderabad is a cornerstone industrial unit supporting power-reactor fuel supply, while other entities handle mining, milling, and reprocessing. Given Data / Assumptions: NFC is part of the national nuclear program’s front-end fuel cycle infrastructure. Options include ore processing, fuel fabrication, and spent-fuel treatment. We seek the best description of NFC’s primary function. Concept / Approach: NFC’s role focuses on conversion of intermediate materials into finished fuel assemblies and related components for reactors (e.g., zirconium alloy claddings, end-fittings, and complete fuel bundles for PHWRs/CANDUs and assemblies for LWRs). Ore mining and milling are typically the domain of dedicated mining corporations, while spent-fuel reprocessing is carried out at specialized reprocessing plants. Step-by-Step Solution: Identify NFC’s core competency: fabrication of fuel elements and assemblies.Differentiate from upstream ore processing and downstream reprocessing activities.Select the option describing manufacture of fuel elements/assemblies. Verification / Alternative check: Descriptions of NFC’s output include PHWR fuel bundles, BWR/PWR fuel assemblies, and zirconium alloy components, aligning with fuel fabrication rather than ore processing or reprocessing. Why Other Options Are Wrong: Processing of uranium ore: typically done by mining and milling entities, not NFC.Treatment of spent fuel: performed at reprocessing plants, not NFC’s primary remit.None of these: contradicts the well-known fabrication role. Common Pitfalls: Conflating the entire fuel cycle with a single facility; assuming ore processing and fabrication occur at the same site. Final Answer: Manufacture of nuclear fuel elements/assemblies

Question 19

Definition check: what is a “fertile” nuclear material?

Accepted Answer

Introduction / Context: Reactor physics distinguishes between fissile and fertile isotopes. Fissile isotopes sustain a chain reaction upon absorbing a thermal neutron, while fertile isotopes are not immediately fissile but can be transmuted into fissile nuclides via neutron capture and subsequent decay. Properly identifying fertile materials is foundational to understanding breeding and fuel cycles. Given Data / Assumptions: Typical fertile isotopes: U-238 and Th-232. Typical fissile isotopes: U-235, U-233, Pu-239, Pu-241. Definition-based question, not application-specific. Concept / Approach: When a fertile material absorbs a neutron, it becomes a heavier isotope that beta decays into a fissile nuclide. Examples: U-238 → (n,γ) → U-239 → β → Np-239 → β → Pu-239; Th-232 → (n,γ) → Th-233 → β → Pa-233 → β → U-233. These transmutation chains underpin breeder reactor concepts and closed fuel cycles. Step-by-Step Solution: Recall the definition of fertile: convertible to fissile after neutron absorption.Recognize that direct fission by thermal neutrons is a property of fissile, not fertile, materials.Select the option matching the conversion definition. Verification / Alternative check: Charts of the nuclides and standard reactor textbooks classify U-238 and Th-232 as fertile, with the above breeding paths to Pu-239 and U-233 respectively. Why Other Options Are Wrong: “Fissioned by slow neutrons” describes fissile behavior.“Fissioned by fast neutrons” may occur for some isotopes but does not define “fertile.”“Fissioned by either slow or fast neutrons” likewise describes fissile or fissionable behavior, not fertility. Common Pitfalls: Confusing “fissionable” (capable of fission under some conditions) with “fissile” (efficiently fissions with thermal neutrons); forgetting that fertile materials require transmutation to become fissile. Final Answer: Converted into fissile material on absorption of a neutron.

Question 20

Terminology of nuclides: what do we call nuclides that have the same mass number but different nuclear charges (different atomic numbers)?

Accepted Answer

Introduction / Context: Nuclear nomenclature helps classify nuclides by how they relate in terms of proton and neutron numbers. Three commonly tested terms are isotopes, isobars, and isotones. Distinguishing them quickly is essential for reaction bookkeeping and interpreting nuclear charts. Given Data / Assumptions: We compare nuclides by mass number A, atomic number Z, and neutron number N. The specific case is “same mass number but different Z.” Concept / Approach: Isotopes share the same Z (protons) but have different N → same element, different mass numbers. Isobars share the same A (total nucleons) but have different Z and N → different elements with equal mass number. Isotones share the same N (neutrons) but different Z and A. The term matching “same A, different Z” is therefore “isobars.” Step-by-Step Solution: Identify the defining equality: A is the same.Recognize that Z is different; hence N must differ to keep A constant.Select “Isobars” as the correct classification. Verification / Alternative check: Examples include 40Ar (Z=18, N=22) and 40Ca (Z=20, N=20): same A=40, different Z; these nuclides are isobars. Why Other Options Are Wrong: Isotopes: same Z, not same A.Isotones: same N, not same A.None of these: incorrect because “isobars” is the standard term. Common Pitfalls: Memorizing terms without associating them with A, Z, and N; mixing up “iso-” prefixes. Final Answer: Isobars

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