The BTF-104 Experiment: An In-Reactor Test of Fuel Behaviour, and Fission-Product Release and Transport Under LOCAILOECC Conditions

Abstract

The primary objective of the BTF-104 experiment was to determine the timing, amount andtransport characteristics of fission products released from a previously irradiated CANDU-sizedfuel element subjected to a high-temperature transient representative of a Loss-of-CoolantAccident (LOCA) with additional Loss-of-Emergency-Core-Cooling (LOECC). This papersummarizes the results of the BTF- 104 experiment.