研習資料
These supplemental problems were developed by the authors for their MIT courses and are included here with the designation "N" (for new) in their numbering. For example, 2-6N is a new problem in Chapter 2 and is the sixth problem related to Chapter 2 material in the textbook. Those with the designation "S" were developed based on materials from Introduction to Structural Mechanics, which is on the required readings page.
| 課程單元 | QUESTIONS |
|---|---|
| Worldwide Utilization of Power Reactor Technology | 1-1N (PDF) |
| Analysis of Reactor Types | 2-6N (PDF) |
| Decay Power Calculations of a 3-Batch PWR Core | 3-8N (PDF) |
| Thermodynamics of Binary Cycle Involving Sodium and Steam Water | 6-8N (PDF) |
| Proofs Involving the Brayton Cycle | 6-9N (PDF) |
| Replacement of a Steam Generator in a PWR with a Flash Tank | 6-10N (PDF) |
| Irreversibility Problems Involving the Rankine Cycle | 6-11N (PDF) |
| Optimizing the Pressure Ratio of the Brayton Cycle in a Brayton-Rankine Combined Cycle | 6-13N (PDF) |
| BWR Operation at Supercritical Conditions | 6-14N (PDF) |
| Tokamak Power Generation Problem | 6-16N (PDF) |
| Power Cycle for a Simplified BWR | 6-17N (PDF) |
| Containment Problem Involving a LOCA | 7-10N (PDF) |
| Pressurizer Transient Problem | 7-11N (PDF) |
| Pressurizer Insurge Problem | 7-12N (PDF) |
| Pressurizer Sizing Analysis | 7-13N (PDF) |
| Containment Pressurization Reactor Thermodynamics | 7-14N (PDF) |
| Drain Tank Pressurization Problem | 7-15N (PDF) |
| Containment Pressurization Following Zircaloy-Hydrogen Reaction | 7-16N (PDF) |
| Containment Sizing for a Gas-Cooled Reactor with Passive Emergency Cooling | 7-17N (PDF) |
| Conductivity Integral | 8-8N (PDF) |
| Thermal Conduction Problem Involving Design of a BWR Core | 8-9N (PDF) |
| Important Features of Fuel Element Temperature Calculation | 8-10N (PDF) |
| Transient Fuel Pin Analysis | 8-12N (PDF) |
| Radially Averaged Fuel Temperature and Stored Energy in Solid and Annular Pellet | 8-14N (PDF) |
| Two-Zone Sintering of an Annular Fuel Pellet | 8-15N (PDF) |
| Reynolds Analogy and Equivalent Diameter Problem | 10-7N (PDF) |
| Turbulent Heat Transfer Coefficient Calculations | 10-8N (PDF) |
| Equivalent Diameter and Reynolds Analogy Problem Involving a Fuel Element | 10-9N (PDF) |
| Fully Developed Laminar Heat Transfer in a Circular Duct | 10-10N (PDF) |
| Thermal Analysis of a Lead-Cooled Reactor Fuel Assembly | 10-11N (PDF) |
| Wall Friction Components for Liquid and Vapor Only | 11-9N (PDF) |
| Calculating Void Fraction in Adiabatic Steam-Water Flow | 11-11N (PDF) |
| Critical Flow During a Small-Break LOCA in a BWR | 11-12N (PDF) |
| Computation of the Axial Distribution of Thermal and Hydraulic Characteristics of a Horizontal Steam Generator | 12-7N (PDF) |
| Shell and Tube Horizontal Evaporator | 12-8N (PDF) |
| Calculation of MCHFR and MCPR for a BWR Channel | 12-10N (PDF) |
| Nucleate Boiling on a Tube Wall | 12-12N (PDF) |
| Nucleate Boiling Initiation and Termination on a Heat Exchanger Tube | 12-13N (PDF) |
| Nucleation in Pool and Flow Boiling | 12-14N (PDF) |
| Two-Phase Flow Pressure Drop Calculation in BWR | 13-7N (PDF) |
| Thermal Hydraulic Analysis of a Pressure Tube Reactor | 13-8N (PDF) |
| Heat Transfer Problems for a BWR Channel | 13-9N (PDF) |
| Two-Phase Problem Involving a Nuclear Power Plant | 13-10N (PDF) |
| Location of Maximum Clad and Fuel Temperature for a Uniform Axial q''' | 13-11N (PDF) |
| Thermal Behavior of a Plate Fuel Element Following a Loss of Coolant | 13-12N (PDF) |
| Maximum Clad Temperature for LMFBR Reactor | 13-13N (PDF) |
| Stress Field Determination using Mohr's Circle | S1-2 (PDF) |
| Interior Pressure to Fail Cylindrical and Spherical Vessel by Several Failure Theories | S4-2 (PDF) |
| Determining Allowable Pressure by ASME Criteria | S5-1 (PDF) |
