Open AccessNumerical results of PT-IP-338A and supplement A: DR reactor heat decay test at high outlet water temperatures
Author(s) -
S.S. Jones,
José Manuel
Publication year - 1962
Language(s) - English
Resource type - Reports
DOI - 10.2172/29395
Subject(s) - scram , coolant , nuclear engineering , decay heat , environmental science , pressurized water reactor , materials science , waste management , engineering , mechanical engineering
This report summarizes the results obtained in the experimental measurement of the reactor heat extracted by the coolant during two different scrams of the DR Reactor. These tests were conducted with the reactor flow carefully controlled to establish different reactor coolant temperatures following the scram. During normal reactor scrams, which have been used in the past to measure the reactor heat output, a high coolant flow was maintained. Consequently, the coolant outlet temperature dropped very quickly from an operating value of 90 to 95 C down to 20 to 30 C following the scram. Under emergency conditions, however, with only the last ditch emergency flow available, the coolant outlet temperature could remain as high as 80 to 90 C. This condition could prevail because of the small amount of last ditch flow available, and could last for 5 to as long as 70 minutes after the reactor scram