SADD - Severe accident database directory

DataBase In-Vessel - Focus area 1: Mechanical degradation of the reactor core (4)

Facility Name	Test Identification	Measured Parameters	Country
NRU-FLHT	FLHT-1	12 fuel rods, water/steam, max T. =2300 K	Chalk River, Ontario, Canada
References: Rausch W N et al., "Full-Length High-Temperature Severe Fuel Damage Test 1", PNL-5691, August 1993; Lombardo N J et al., "Full-Length High-Temperature Severe Fuel Damage Test 2", PNL-6551, early 1994; Lanning D D et al., "Data Report: Full-Length High-Temperature Experiment 4", PNL-6368 (Draft), January 1988; Lanning D D et al., "Full-Length High-Temperature Severe Fuel Damage Test 5", PNL-6540, September 1993; Lombardo N J et al., "Full-Length Fuel Rod Behavior Under Severe Accident Conditions", NUREG/CR-5876, PNL-8023, December 1992 IP/Copyright Situation: To be Checked
NRU-FLHT	FLHT-2	12 fuel rods, water/steam, max T. =2500 K	Chalk River, Ontario, Canada
References: Rausch W N et al., "Full-Length High-Temperature Severe Fuel Damage Test 1", PNL-5691, August 1993; Lombardo N J et al., "Full-Length High-Temperature Severe Fuel Damage Test 2", PNL-6551, early 1994; Lanning D D et al., "Data Report: Full-Length High-Temperature Experiment 4", PNL-6368 (Draft), January 1988; Lanning D D et al., "Full-Length High-Temperature Severe Fuel Damage Test 5", PNL-6540, September 1993; Lombardo N J et al., "Full-Length Fuel Rod Behavior Under Severe Accident Conditions", NUREG/CR-5876, PNL-8023, December 1993 IP/Copyright Situation: To be Checked
NRU-FLHT	FLHT-3	12 rods (10F/1 IR/ 1 gamma), water/steam, max T. =2600 K	Chalk River, Ontario, Canada
References: Rausch W N et al., "Full-Length High-Temperature Severe Fuel Damage Test 1", PNL-5691, August 1993; Lombardo N J et al., "Full-Length High-Temperature Severe Fuel Damage Test 2", PNL-6551, early 1994; Lanning D D et al., "Data Report: Full-Length High-Temperature Experiment 4", PNL-6368 (Draft), January 1988; Lanning D D et al., "Full-Length High-Temperature Severe Fuel Damage Test 5", PNL-6540, September 1993; Lombardo N J et al., "Full-Length Fuel Rod Behavior Under Severe Accident Conditions", NUREG/CR-5876, PNL-8023, December 1994 IP/Copyright Situation: To be Checked
NRU-FLHT	FLHT-4	12 rods (10F/1 IR/ 1 gamma), water/steam, max T. =2600 K	Chalk River, Ontario, Canada
References: Rausch W N et al., "Full-Length High-Temperature Severe Fuel Damage Test 1", PNL-5691, August 1993; Lombardo N J et al., "Full-Length High-Temperature Severe Fuel Damage Test 2", PNL-6551, early 1994; Lanning D D et al., "Data Report: Full-Length High-Temperature Experiment 4", PNL-6368 (Draft), January 1988; Lanning D D et al., "Full-Length High-Temperature Severe Fuel Damage Test 5", PNL-6540, September 1993; Lombardo N J et al., "Full-Length Fuel Rod Behavior Under Severe Accident Conditions", NUREG/CR-5876, PNL-8023, December 1995 IP/Copyright Situation: To be Checked

effects of coolant and boilaway and core damage progression