HKIE Professional Assessment - Nuclear Discipline study plan
HKIE Professional Assessment - Nuclear Discipline · Give each week a clear focus.
8 weeks · About 6 hours per week
Nuclear physics and reactor theory fundamentals & Nuclear reactor systems, thermal-hydraulics and safety analysis
Derive and explain the four-factor formula and six-factor formula, stating the physical meaning of each term and how each is affected by fuel enrichment, moderator-to-fuel ratio, and geometry.
Solve point-kinetics problems for a step reactivity insertion, computing prompt jump magnitude and stable period for both prompt-supercritical and delayed-supercritical cases.
Explain the physical basis of the Doppler, moderator temperature, and void reactivity coefficients in a light-water reactor, and state the sign and relative magnitude expected in each core state.
Sketch a PWR primary loop and a BWR recirculation loop from memory, labelling each major component and stating its thermal-hydraulic function.
Compute subchannel-level quality, void fraction, and critical heat flux margin for a simplified steady-state channel using a supplied correlation, and interpret the margin against the design limit.
Your checkpoint
A one-page formula sheet plus five fully worked numerical problems (kinetics, reactivity coefficients, CHF margin) solved without notes, self-marked against a written solution key.
Nuclear reactor systems, thermal-hydraulics and safety analysis
Build a nodal or lumped-parameter model of a single heated channel and calculate steady-state coolant temperature and pressure drop at three power levels.
Analyse a large-break loss-of-coolant accident sequence phase by phase, identifying the dominant heat-transfer regime and the safety function challenged in each phase.
Evaluate the role of the emergency core cooling system and the containment isolation and heat removal systems in mitigating a design-basis accident, referencing acceptance criteria rather than plant-specific numbers.
Distinguish design-basis accident analysis from severe accident phenomenology (core degradation, hydrogen generation, molten corium behaviour) and state which phenomena each analysis must capture.
Explain how a safety analysis report structures deterministic safety cases and where single-failure criteria and conservative assumptions enter.
Your checkpoint
A 1,500-word written safety-analysis narrative of a design-basis LOCA with a phase table mapping sequence step to heat-transfer regime, challenged safety function, and acceptance criterion.
Radiation protection, shielding and dosimetry
Convert between activity, exposure, absorbed dose, equivalent dose, and effective dose, and state the SI unit and the conditions under which each conversion is valid.
Compute unshielded and shielded dose rates from a point gamma source using inverse-square attenuation and buildup factors, and state the limits of validity of the point-source approximation.
Apply the ALARA principle to a planned maintenance task: define dose constraints, estimate collective dose, and propose at least three engineered or administrative dose-reduction measures.
Explain internal dose pathways and the biokinetic basis of committed effective dose, distinguishing inhalation, ingestion, and wound intake.
Describe the design principles of shielding for photons, neutrons, and beta particles, and explain why the material choice differs for each.
Your checkpoint
A worked dose-assessment package for one maintenance scenario: source term, calculated dose rate at the work position, collective dose estimate, and a documented ALARA justification.
Nuclear safety, licensing and regulatory framework
Map the licensing process for a nuclear facility from site selection through construction, commissioning, operation, and periodic safety review, naming the applicant and regulator deliverables at each stage.
Explain the graded approach to safety classification of structures, systems, and components and apply it to five example components.
Summarise the key obligations of a nuclear safety regulator and of the licensee, and distinguish prescriptive from goal-setting regulatory regimes.
Explain how a safety culture is assessed and what observable indicators distinguish a healthy from a deteriorating safety culture.
Describe the interface between nuclear safety regulation and other regulatory regimes (environmental, occupational safety, security) and where conflicts must be resolved.
Your checkpoint
A licensing roadmap diagram with an accompanying 800-word note mapping each stage to its governing document type, regulator decision, and licensee obligation.
Radioactive waste management and decommissioning & Nuclear fuel cycle and materials
Classify radioactive waste by activity level and radionuclide content and select an appropriate conditioning and disposal route for each class, justifying the choice.
Compare the front-end and back-end options of the fuel cycle (once-through, reprocessing, partitioning and transmutation) on resource use, waste volume, and proliferation resistance.
Explain the mechanisms of fuel cladding failure and the consequences for primary-circuit activity and subsequent waste arisings.
Outline a decommissioning strategy from characterization through dismantling, waste routing, and site release, and identify the dose and waste drivers at each stage.
Explain the safety case for an interim spent-fuel storage facility and the phenomena that must be managed over extended storage periods.
Your checkpoint
A waste-routing decision table covering at least six waste streams, each with classification, conditioning route, disposal route, and the governing safety argument.
Instrumentation, control and electrical systems in nuclear facilities & Probabilistic safety assessment and risk management
Explain the measurement chain for neutron flux detection from source range through intermediate and power range, and state the redundancy and diversity requirements for reactor trip signals.
Analyse a reactor protection system architecture for single-failure tolerance and identify common-cause failure vulnerabilities in a two-out-of-four voting arrangement.
Construct a small fault tree for a simplified safety function, compute the top-event probability from basic-event data, and identify the minimal cut sets.
Explain the difference between core damage frequency and large early release frequency and how each is used in risk-informed decision making.
Interpret importance measures (Fussell-Vesely, risk achievement worth, Birnbaum) and state what each tells a designer or operator.
Your checkpoint
A complete small fault tree with minimal cut sets, quantified top-event probability, and importance measures for each basic event, plus a 300-word interpretation of the dominant contributors.
Emergency preparedness and response & Professional practice, ethics and engineering management
Classify nuclear emergencies by emergency action level and state the protective action decision criteria for sheltering, evacuation, and iodine prophylaxis.
Explain the design basis of an off-site emergency plan, including plume projection, dose projection, and the interface between the operator and off-site responders.
Analyse an ethical dilemma in nuclear engineering practice using a recognised professional code, identifying the competing obligations and the correct escalation path.
Explain the engineer's duty to report safety concerns and the legal and professional protections and limits that apply.
Outline the elements of an engineering change control process in a nuclear facility and the safety justification required before implementation.
Your checkpoint
A tabletop exercise write-up: a simulated release scenario with a timeline of decisions, the dose criteria applied at each decision point, and a 500-word ethical and managerial reflection.
Nuclear physics and reactor theory fundamentals & Nuclear reactor systems, thermal-hydraulics and safety analysis & Radiation protection, shielding and dosimetry & Nuclear safety, licensing and regulatory framework & Radioactive waste management and decommissioning & Nuclear fuel cycle and materials & Instrumentation, control and electrical systems in nuclear facilities & Probabilistic safety assessment and risk management & Emergency preparedness and response & Professional practice, ethics and engineering management
Sit two full-length timed mock assessments under exam conditions and record the score by domain to identify residual weak areas.
Re-derive from memory the ten highest-yield relationships across the syllabus (kinetics, reactivity coefficients, dose conversion, fault-tree quantification) without reference material.
Review every incorrectly answered mock question and write a corrected explanation for each in your own words.
Practise structuring written answers to the professional-practice and ethics questions under time pressure, with explicit statement of obligation, reasoning, and recommended action.
Consolidate the formula sheet and decision tables from weeks 1 to 7 into a single revision pack indexed by domain.
Your checkpoint
Two marked mock papers with a domain-by-domain score profile, a corrected-answer log, and a final one-page revision pack.
Milestones
Week 2: Can derive the six-factor formula and solve a delayed-supercritical kinetics problem from a blank page, and can narrate a design-basis LOCA phase by phase without notes.
Week 4: Can draw the full licensing roadmap from memory and correctly classify ten mixed components under a graded safety approach.
Week 6: Can build and quantify a small fault tree and interpret its importance measures, and can explain reactor protection redundancy requirements in terms of single-failure tolerance.
Week 8: Mock assessment scores at or above 65 percent overall with no single domain below 50 percent, and every mock error logged with a corrected explanation.