The US-APWR is a 4451 MWt pressurized water reactor designed by Mitsubishi Heavy Industries, Ltd. It is an evolutionary design with active safety features. The US-APWR is based on established APWR technology. Mitsubishi Heavy Industries, Ltd submitted an application for standard design certification on December 31, 2007. The NRC staff is performing a detailed review of the application.
| Date |
Description |
| 04/25/08 |
Dynamic Analysis of the Coupled RCL-R/B-PCCV-CIS Lumped Mass Stick |
| 02/29/08 |
US-APWR Fuel System Design |
| 02/29/08 |
Subcompartment Analyses for US-APWR Design Confirmation |
| 02/29/08 |
Enhanced Information for PS/B Design |
| 02/27/08 |
US-APWR Sump Strainer Performance |
| 02/27/08 |
Criticality Analysis for US-APWR New and Spent Fuel Storage Racks |
| 12/31/07 |
Comprehensive Vibration Assessment Program for US-APWR Reactor Internals |
| 12/31/07 |
Defense-in-Depth and Diversity Coping Analysis |
| 12/31/07 |
FMEA of Control Rod Drive Mechanism Control System |
| 12/31/07 |
US-APWR Incore Power Distribution Evaluation Methodology |
| 12/31/07 |
Justification for Deviations between NUREG-1431 Rev. 3.1 and US-APWR Technical Specifications |
| 12/31/07 |
Validation of the MHI Criticality Safety Methodology |
| 12/31/07 |
Probability of Missile Generation from Low Pressure Turbines |
| 12/31/07 |
Qualification of Nuclear Design Methodology using PARAGON/ANC |
| 12/31/07 |
Structural Analysis for US-APWR Reactor Coolant Pump Motor Flywheel |
| 12/31/07 |
Mitsubishi Reload Evaluation Methodology |
| 12/31/07 |
APWR Reactor Internals 1/5 Scale Model Flow Test Report |
| 12/31/07 |
US-APWR Technical Report Software Program Manual |
| 12/31/07 |
Probabilistic Evaluation of Turbine Valve Test Frequency |
| 12/31/07 |
Small Break LOCA Sensitivity Analyses for US-APWR |
| 12/31/07 |
US-APWR Fuel System Design Parameters |
| 12/05/07 |
Qualification and Test Plan of Class 1E Gas Turbine Generator System |
| 11/01/07 |
Common Cause Failure Potential for Safety System Digital Platform |