Organization / Localization: NRU Reactor Country: Chalk River, Ontario, Canada Test Identification: FLHT-1 SA-Related Topics / Phenomena:effects of coolant and boilaway and core damage progression Measured Parameters: 12 fuel rods, water/steam, max T. =2300 K
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
Organization / Localization: NRU Reactor Country: Chalk River, Ontario, Canada Test Identification: FLHT-2 SA-Related Topics / Phenomena:effects of coolant and boilaway and core damage progression Measured Parameters: 12 fuel rods, water/steam, max T. =2500 K
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
Organization / Localization: NRU Reactor Country: Chalk River, Ontario, Canada Test Identification: FLHT-3 SA-Related Topics / Phenomena:effects of coolant and boilaway and core damage progression Measured Parameters: 12 rods (10F/1 IR/ 1 gamma), water/steam, max T. =2600 K
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
Organization / Localization: NRU Reactor Country: Chalk River, Ontario, Canada Test Identification: FLHT-4 SA-Related Topics / Phenomena:effects of coolant and boilaway and core damage progression Measured Parameters: 12 rods (10F/1 IR/ 1 gamma), water/steam, max T. =2600 K
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
Implemented as part of the Seaknot EU funded project (HORIZON-EURATOM-2021-NRT-01 under Grant Agreement No. 101060327) - WP2.6 UNIPI (2024-2026)