Design, Construction and Testing of an In-Pile Loop for PWR (Pressurized Water Reactor) Simulation.
Abstract
Corrosion product activation and transport in Light Water Reactors is a well recognized, but poorly understood phenomenon, despite studies conducted world-wide for the past 20 years. In an effort to determine the mechanistic parameters which produce, release the transport activated corrosion products throughout a typical Pressurized Water Reactor (PWR), MIT has undertaken the construction of a model pressurized water loop to simulate the thermal hydraulic characteristics of a representative full scale PWR. This report presents the final detailed design of the PCCL. As-built, the Loop duplicates the core and Steam Generator fluid surface film differential temperatures, bulk fluid temperatures, and wall fluid shear stress of an actual PWR. Included are proposed plans for sea trial testing of the initial Loop prior to research operation. The final design has been reviewed and authorized for construction by the PCCL Project Staff and the MIT Reactor Safeguards Committee.
Document Details
- Document Type
- Technical Report
- Publication Date
- Jun 01, 1987
- Accession Number
- ADA190258
Entities
People
- James H. Wicks Jr
Organizations
- Massachusetts Institute of Technology