| Document Number |
Title |
Publish Date |
| RIL–159 |
Nuclear Plant Aging Research: Safety-Related Inverters |
11/09/1988 |
| RIL–158 |
Operational Safety Reliability Program |
10/31/1988 |
| RIL–157 |
Report on the Results of the Core I Test Series at the Japan Atomic Energy Research Institute Slab Core Test Facility |
09/12/1988 |
| RIL–156 |
An Investigation of Core Liquid Level Depression in Small Break Loss-of-Coolant Accidents |
09/01/1988 |
| RIL–155 |
FULL Scale Fluid Mixing Test Results in Support of Pressurized Thermal Shock Resolution |
08/24/1988 |
| RIL–154 |
Water-Steam Countercurrent Flow Limit in a Full Scale Hot Leg |
08/01/1988 |
| RIL–153 |
A Methodology to Assess Safety During the Preclosure Period of High-Level Waste Repository |
04/27/1988 |
| RIL–152 |
Results of Research on Dating Ground Water for High Level Waste Repository Site Characterization |
04/20/1988 |
| RIL–151 |
Results of Meers Fault Investigations |
03/04/1988 |