Design of Slab Core Test Facility (SCTF) In Large Scale Reflood Test Program, 1. Core-1

摘要

This report describes the design principle and the detailed features of the Slab Core Test Facility (SCTF) which is used to investigate the two-dimensional, thermohydraulic behavior in the reactor pressure vessel during the last part of blowdown, refill and reflood phases of a postulated loss-of-coolant accident for pressurized water reactor. The SCTF test program is one of the research activities based on the agreement on so called the 2D/3D test program among Japan Atomic Energy Research Institute, Bundesminister fur Forschung und Technologie and United Stated Nuclear Regulatory Commission. Not only for good understanding of the SCTF test results but also for further analytical work, information of instruments, identification of the measurements and the description of the test procedure are introduced as well as the description of hardware of the facility. (Atomindex citation 15:059460)