| 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) |