Facility Details: ACRR-DF

Organization / Localization: SNL
Country: Albuquerque, NM, USA
Test Identification: DF1
SA-Related Topics / Phenomena: initial fuel damage processes beginning with intact fuel rods undergoing heatup and progressing through oxidation in steam, hydrogen generation, melting and relocation of the fuel cladding, the formation of blockages, and the degradation of the fuel rod geometry
Measured Parameters: 9 UO2 rods, Steam, max T. > 2700 K
References: Gasser R D, Fryer C P, Gauntt R O, Marshall A C, Reil K O, and Stalker K T, "Damaged Fuel Experiment DF-l: Results and Analysis", NUREG/CR-4668, SAND86-1030, Sandia National Laboratories, Albuquerque, NM, January 1990; Gasser R D, Fryer C P, Gauntt R O, Marshall A C, Reil K O, and Stalker K T, "Damaged Fuel Relocation Experiment DF-2: Results and Analysis", NUREG/CR-4669, SAND86-1441, Sandia National Laboratories, Albuquerque, NM, September 1992; Fryer C P, Gauntt R O and Cronenberg A W, "Damaged Fuel Experiment DF-3: Test Results", NUREG/CR-6006, SAND87-1212, Sandia National Laboratories, Albuquerque, NM, December 1992; Gauntt R O, Gasser R D and Ott L J, "The DF-4 Fuel Damage Experiment in ACRR with a BWR Control Blade and Channel Box", NUREG/CR-4671, SAND86 -1443, Sandia National Laboratories, Albuquerque, NM, November 1989; Gauntt R O, Gasser R D, Fryer C P and Walker J V, "Results and Phenomena Observed from the DF-4 BWR Control Blade-Channel Box Test", Proc. Intern. ENS/ANS Conf. on Thermal Reactor Safety, Avignon, France, October 2 -7, 1988; Gauntt R O and Gasser R D, "Results of the DF-4 BWR Control Blade-Channel Box Test", Proc. 18th NRC Water Reactor Safety Information Mtg. Rockville, MD, October 22 -24, 1990

IP/Copyright Situation: To be Checked
Organization / Localization: SNL
Country: Albuquerque, NM, USA
Test Identification: DF2
SA-Related Topics / Phenomena: initial fuel damage processes beginning with intact fuel rods undergoing heatup and progressing through oxidation in steam, hydrogen generation, melting and relocation of the fuel cladding, the formation of blockages, and the degradation of the fuel rod geometry
Measured Parameters: 9 UO2 rods, Steam, max T. =2600 K
References: Gasser R D, Fryer C P, Gauntt R O, Marshall A C, Reil K O, and Stalker K T, "Damaged Fuel Experiment DF-l: Results and Analysis", NUREG/CR-4668, SAND86-1030, Sandia National Laboratories, Albuquerque, NM, January 1990; Gasser R D, Fryer C P, Gauntt R O, Marshall A C, Reil K O, and Stalker K T, "Damaged Fuel Relocation Experiment DF-2: Results and Analysis", NUREG/CR-4669, SAND86-1441, Sandia National Laboratories, Albuquerque, NM, September 1992; Fryer C P, Gauntt R O and Cronenberg A W, "Damaged Fuel Experiment DF-3: Test Results", NUREG/CR-6006, SAND87-1212, Sandia National Laboratories, Albuquerque, NM, December 1992; Gauntt R O, Gasser R D and Ott L J, "The DF-4 Fuel Damage Experiment in ACRR with a BWR Control Blade and Channel Box", NUREG/CR-4671, SAND86 -1443, Sandia National Laboratories, Albuquerque, NM, November 1989; Gauntt R O, Gasser R D, Fryer C P and Walker J V, "Results and Phenomena Observed from the DF-4 BWR Control Blade-Channel Box Test", Proc. Intern. ENS/ANS Conf. on Thermal Reactor Safety, Avignon, France, October 2 -7, 1988; Gauntt R O and Gasser R D, "Results of the DF-4 BWR Control Blade-Channel Box Test", Proc. 18th NRC Water Reactor Safety Information Mtg. Rockville, MD, October 22 -24, 1990

IP/Copyright Situation: To be Checked
Organization / Localization: SNL
Country: Albuquerque, NM, USA
Test Identification: DF3
SA-Related Topics / Phenomena: initial fuel damage processes beginning with intact fuel rods undergoing heatup and progressing through oxidation in steam, hydrogen generation, melting and relocation of the fuel cladding, the formation of blockages, and the degradation of the fuel rod geometry
Measured Parameters: 8 UO2 + 1 AIC rods, Steam, max T. > 2400 K
References: Gasser R D, Fryer C P, Gauntt R O, Marshall A C, Reil K O, and Stalker K T, "Damaged Fuel Experiment DF-l: Results and Analysis", NUREG/CR-4668, SAND86-1030, Sandia National Laboratories, Albuquerque, NM, January 1990; Gasser R D, Fryer C P, Gauntt R O, Marshall A C, Reil K O, and Stalker K T, "Damaged Fuel Relocation Experiment DF-2: Results and Analysis", NUREG/CR-4669, SAND86-1441, Sandia National Laboratories, Albuquerque, NM, September 1992; Fryer C P, Gauntt R O and Cronenberg A W, "Damaged Fuel Experiment DF-3: Test Results", NUREG/CR-6006, SAND87-1212, Sandia National Laboratories, Albuquerque, NM, December 1992; Gauntt R O, Gasser R D and Ott L J, "The DF-4 Fuel Damage Experiment in ACRR with a BWR Control Blade and Channel Box", NUREG/CR-4671, SAND86 -1443, Sandia National Laboratories, Albuquerque, NM, November 1989; Gauntt R O, Gasser R D, Fryer C P and Walker J V, "Results and Phenomena Observed from the DF-4 BWR Control Blade-Channel Box Test", Proc. Intern. ENS/ANS Conf. on Thermal Reactor Safety, Avignon, France, October 2 -7, 1988; Gauntt R O and Gasser R D, "Results of the DF-4 BWR Control Blade-Channel Box Test", Proc. 18th NRC Water Reactor Safety Information Mtg. Rockville, MD, October 22 -24, 1990

IP/Copyright Situation: To be Checked
Organization / Localization: SNL
Country: Albuquerque, NM, USA
Test Identification: DF4
SA-Related Topics / Phenomena: initial fuel damage processes beginning with intact fuel rods undergoing heatup and progressing through oxidation in steam, hydrogen generation, melting and relocation of the fuel cladding, the formation of blockages, and the degradation of the fuel rod geometry
Measured Parameters: 14 UO2 + 1 AIC rods, Steam, max T. = 2720 K
References: Gasser R D, Fryer C P, Gauntt R O, Marshall A C, Reil K O, and Stalker K T, "Damaged Fuel Experiment DF-l: Results and Analysis", NUREG/CR-4668, SAND86-1030, Sandia National Laboratories, Albuquerque, NM, January 1990; Gasser R D, Fryer C P, Gauntt R O, Marshall A C, Reil K O, and Stalker K T, "Damaged Fuel Relocation Experiment DF-2: Results and Analysis", NUREG/CR-4669, SAND86-1441, Sandia National Laboratories, Albuquerque, NM, September 1992; Fryer C P, Gauntt R O and Cronenberg A W, "Damaged Fuel Experiment DF-3: Test Results", NUREG/CR-6006, SAND87-1212, Sandia National Laboratories, Albuquerque, NM, December 1992; Gauntt R O, Gasser R D and Ott L J, "The DF-4 Fuel Damage Experiment in ACRR with a BWR Control Blade and Channel Box", NUREG/CR-4671, SAND86 -1443, Sandia National Laboratories, Albuquerque, NM, November 1989; Gauntt R O, Gasser R D, Fryer C P and Walker J V, "Results and Phenomena Observed from the DF-4 BWR Control Blade-Channel Box Test", Proc. Intern. ENS/ANS Conf. on Thermal Reactor Safety, Avignon, France, October 2 -7, 1988; Gauntt R O and Gasser R D, "Results of the DF-4 BWR Control Blade-Channel Box Test", Proc. 18th NRC Water Reactor Safety Information Mtg. Rockville, MD, October 22 -24, 1990

IP/Copyright Situation: To be Checked




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