HKIE Professional Assessment - Nuclear Discipline flashcards
HKIE Professional Assessment - Nuclear Discipline · Build recall with a focused review session.
34 cards. Read the term and the definition here. The deck at the top of this page is optional.
- Six-factor formula
- k_inf = epsilon * p * f * eta * PFNL * PTRL, combining fast fission, resonance escape, thermal utilisation, reproduction factor and fast/thermal non-leakage probabilities to give infinite multiplication factor.
- Reactivity in pcm
- Reactivity rho = (k_eff - 1)/k_eff, expressed in pcm where 1 pcm = 1e-5. One dollar equals beta_eff, about 650 pcm for thermal U-235 systems.
- Delayed neutron fraction
- Beta_eff is about 0.0065 for U-235 thermal fission and 0.0021 for Pu-239. Operation below rho = beta keeps the reactor controllable by delayed neutrons.
- Xenon-135 iodine pit
- After shutdown, Xe-135 builds from I-135 decay for 6-10 hours because burnout stops. Its huge absorption cross-section (2.6e6 barns) depresses reactivity and restricts restart.
- Doppler reactivity coefficient
- Fuel temperature rise broadens U-238 resonance absorption, reducing resonance escape probability. This gives a prompt negative feedback of about -1 to -3 pcm/K in oxide fuel.
- PWR operating conditions
- Primary coolant at about 155 bar with cold leg near 290 C and hot leg near 325 C, remaining subcooled. Secondary side produces saturated steam at 60-70 bar to the turbine.
- Departure from nucleate boiling
- DNB is the critical heat flux condition in subcooled or low-quality PWR flow where a vapour blanket causes rapid cladding temperature rise. Design limit is typically DNBR of at least 1.3.
- Decay heat fraction
- Residual heat from fission products is about 6.5% of full power at 1 s, 1.3% at 1 hour and 0.4% at 1 day after shutdown, driving residual heat removal design.
- LOCA acceptance criteria
- Under 10 CFR 50.46, peak cladding temperature must stay below 1204 C, local oxidation below 17% of zirconium thickness, and hydrogen generation below 1% of the full reaction value.
- Effective dose formula
- Effective dose E equals the sum over tissues of tissue weighting factor w_T times equivalent dose H_T. ICRP 103 weights sum to 1.0, with lung 0.12 and gonads 0.08.
- Occupational dose limits
- ICRP recommends 20 mSv per year averaged over five years, with no more than 50 mSv in any single year. Lens of eye limit is 20 mSv per year.
- Tenth-value layer
- The thickness of shielding material that reduces gamma dose rate by a factor of ten. It equals ln(10)/mu, about 3.32 divided by the linear attenuation coefficient.
- Neutron shielding principle
- Fast neutrons are first moderated by hydrogenous material, then absorbed by boron or cadmium. Capture gamma rays of 2.22 MeV from hydrogen require an outer high-Z shield layer.
- Defence in depth levels
- Five IAEA levels: prevention of abnormal operation, detection and control, control of design basis accidents, severe accident management, and off-site emergency response. Each level has independent provisions.
- IAEA safety standards hierarchy
- Safety Fundamentals set principles, General Safety Requirements cover all facilities, and Specific Safety Requirements address NPPs (SSR-1, SSR-2), research reactors, waste, disposal and transport.
- Periodic safety review
- A comprehensive reassessment of plant safety, typically every ten years of operation, covering ageing, operating experience, safety analysis and modifications against current standards.
- Very low level waste
- IAEA GSG-1 classifies waste by activity level and half-life. VLLW needs limited containment and can go to near-surface disposal with simplified engineered barriers.
- Geological disposal multi-barrier
- HLW disposal at 500-1000 m depth uses vitrified waste, metal canister, bentonite buffer and host rock. Each barrier independently retards radionuclide release over long timescales.
- Clearance of material
- Regulatory release of material from control when activity concentration and total activity fall below IAEA RS-G-1.7 levels, verified by measurement and documented in a final survey.
- Type B package tests
- Type B transport packages must survive a 9 m drop onto an unyielding target, 1 m puncture, 800 C fire for 30 minutes, and 200 m water immersion.
- Separative work unit
- SWU measures enrichment effort. Mass balance F = P + T and F*xf = P*xp + T*xt apply; producing 4.5% U-235 at 0.25% tails needs roughly 5-6 SWU per kg.
- PUREX reprocessing
- Plutonium uranium reduction extraction uses tributyl phosphate in kerosene to separate uranium and plutonium from fission products, enabling MOX fuel fabrication and HLW vitrification.
- Criticality safety margin
- Fissile material operations maintain k_eff at or below 0.95, applying the double contingency principle so at least two independent unlikely failures are needed for criticality.
- Reactor vessel embrittlement
- Neutron irradiation raises the nil-ductility transition temperature of low-alloy steel. Surveillance capsules with test specimens monitor the RTNDT shift against pressure-temperature curve limits.
- Reactor protection 2-out-of-4
- Four independent measurement channels feed trip logic requiring at least two channels to exceed setpoint. This tolerates one failed channel and one channel in test.
- Class 1E qualification
- Safety-related electrical equipment must meet IEEE 323 for environmental qualification, IEEE 344 for seismic qualification and IEEE 384 for separation and independence.
- Station blackout coping
- Loss of offsite power plus emergency diesel failure. Plants must cope typically 4-8 hours using batteries, turbine-driven pumps or passive systems before AC power restoration.
- Level 1 PSA output
- Level 1 probabilistic safety assessment quantifies core damage frequency from initiating events, system fault trees and human error, using minimal cut sets and importance measures.
- Fussell-Vesely importance
- The fraction of total risk contributed by cut sets containing a component. It ranks contributors for risk-informed maintenance and design improvements in PSA models.
- Risk-informed regulation criteria
- RG 1.174 accepts changes when CDF increase stays below 1e-5/y and LERF increase below 1e-6/y, with defence in depth and safety margin maintained.
- Urgent protective action zone
- The UPZ extends typically 5-30 km, where urgent actions such as sheltering, evacuation and iodine thyroid blocking are planned based on projected dose averted.
- Emergency action levels
- EALs classify events as notification, alert, site area emergency or general emergency, based on plant parameters, radiation monitors and security conditions, triggering notification and response.
- Engineer duty to report
- Professional codes require engineers to report safety concerns through internal channels and to the regulator if unresolved, protected by just culture from retaliation for good-faith reporting.
- Just culture
- A framework distinguishing human error from at-risk or reckless behaviour. Honest mistakes are handled with learning; wilful violations face disciplinary action, encouraging reporting.