Facility Details: VERCORS

Organization / Localization: CEA
Country: France
Test Identification: 1
SA-Related Topics / Phenomena: Fuel degradation, fission-product (FP) behaviour and aerosol characteristics
Measured Parameters: burn-up=42.9 GWd/tu, Max T=2130 K
Simulation Code: ASTEC
Experimental Research Program: HEVA/VERCORS Program
References: J.P. Leveque et al., "The HEVA experimental programme", Nuclear Technology, Vol. 108, (1994), 33 [2] G. Ducros, P.P. Malgouyres, M. Kissane, D. Boulaud, M. Durin, "Fission Product release under severe accidental conditions; general presentation of the program and synthesis of VERCORS 1 to 6 results" ; Nuclear Engineering and Design 208, (2001), 191 [3] Y. Pontillon, P. P. Malgouyres, G. Ducros, G. Nicaise, R. Dubourg, M. Kissane, M. Baichi, "Study of the Active Role Played by UO2-ZrO2-FP Interactions on Irradiated Fuel Collapse Temperature from VERCORS Tests", J. Nucl. Mat., 344, (2005), 265
IP/Copyright Situation: To be checked
Organization / Localization: CEA
Country: France
Test Identification: 2
SA-Related Topics / Phenomena: Fuel degradation, fission-product (FP) behaviour and aerosol characteristics
Measured Parameters: burn-up=38,3 GWd/tu, Max T=21350 K
Simulation Code: ASTEC
References: J.P. Leveque et al., "The HEVA experimental programme", Nuclear Technology, Vol. 108, (1994), 33 [2] G. Ducros, P.P. Malgouyres, M. Kissane, D. Boulaud, M. Durin, "Fission Product release under severe accidental conditions; general presentation of the program and synthesis of VERCORS 1 to 6 results" ; Nuclear Engineering and Design 208, (2001), 191 [3] Y. Pontillon, P. P. Malgouyres, G. Ducros, G. Nicaise, R. Dubourg, M. Kissane, M. Baichi, "Study of the Active Role Played by UO2-ZrO2-FP Interactions on Irradiated Fuel Collapse Temperature from VERCORS Tests", J. Nucl. Mat., 344, (2005), 266
IP/Copyright Situation: To be checked
Organization / Localization: CEA
Country: France
Test Identification: 3
SA-Related Topics / Phenomena: Fuel degradation, fission-product (FP) behaviour and aerosol characteristics
Measured Parameters: burn-up=38.3 GWd/tu, Max T=2570 K
Simulation Code: ASTEC
References: J.P. Leveque et al., "The HEVA experimental programme", Nuclear Technology, Vol. 108, (1994), 33 [2] G. Ducros, P.P. Malgouyres, M. Kissane, D. Boulaud, M. Durin, "Fission Product release under severe accidental conditions; general presentation of the program and synthesis of VERCORS 1 to 6 results" ; Nuclear Engineering and Design 208, (2001), 191 [3] Y. Pontillon, P. P. Malgouyres, G. Ducros, G. Nicaise, R. Dubourg, M. Kissane, M. Baichi, "Study of the Active Role Played by UO2-ZrO2-FP Interactions on Irradiated Fuel Collapse Temperature from VERCORS Tests", J. Nucl. Mat., 344, (2005), 267
IP/Copyright Situation: To be checked
Organization / Localization: CEA
Country: France
Test Identification: 4
SA-Related Topics / Phenomena: Fuel degradation, fission-product (FP) behaviour and aerosol characteristics
Measured Parameters: burn-up=38.3 GWd/tu, Max T=2570 K
Simulation Code: ASTEC
References: J.P. Leveque et al., "The HEVA experimental programme", Nuclear Technology, Vol. 108, (1994), 33 [2] G. Ducros, P.P. Malgouyres, M. Kissane, D. Boulaud, M. Durin, "Fission Product release under severe accidental conditions; general presentation of the program and synthesis of VERCORS 1 to 6 results" ; Nuclear Engineering and Design 208, (2001), 191 [3] Y. Pontillon, P. P. Malgouyres, G. Ducros, G. Nicaise, R. Dubourg, M. Kissane, M. Baichi, "Study of the Active Role Played by UO2-ZrO2-FP Interactions on Irradiated Fuel Collapse Temperature from VERCORS Tests", J. Nucl. Mat., 344, (2005), 268
IP/Copyright Situation: To be checked
Organization / Localization: CEA
Country: France
Test Identification: 5
SA-Related Topics / Phenomena: Fuel degradation, fission-product (FP) behaviour and aerosol characteristics
Measured Parameters: burn-up=38.3 GWd/tu, Max T=2570 K
Simulation Code: ASTEC
References: J.P. Leveque et al., "The HEVA experimental programme", Nuclear Technology, Vol. 108, (1994), 33 [2] G. Ducros, P.P. Malgouyres, M. Kissane, D. Boulaud, M. Durin, "Fission Product release under severe accidental conditions; general presentation of the program and synthesis of VERCORS 1 to 6 results" ; Nuclear Engineering and Design 208, (2001), 191 [3] Y. Pontillon, P. P. Malgouyres, G. Ducros, G. Nicaise, R. Dubourg, M. Kissane, M. Baichi, "Study of the Active Role Played by UO2-ZrO2-FP Interactions on Irradiated Fuel Collapse Temperature from VERCORS Tests", J. Nucl. Mat., 344, (2005), 269
IP/Copyright Situation: To be checked
Organization / Localization: CEA
Country: France
Test Identification: 6
SA-Related Topics / Phenomena: Fuel degradation, fission-product (FP) behaviour and aerosol characteristics
Measured Parameters: burn-up=60 GWd/tu, Max T=2620 K
Simulation Code: ASTEC
References: J.P. Leveque et al., "The HEVA experimental programme", Nuclear Technology, Vol. 108, (1994), 33 [2] G. Ducros, P.P. Malgouyres, M. Kissane, D. Boulaud, M. Durin, "Fission Product release under severe accidental conditions; general presentation of the program and synthesis of VERCORS 1 to 6 results" ; Nuclear Engineering and Design 208, (2001), 191 [3] Y. Pontillon, P. P. Malgouyres, G. Ducros, G. Nicaise, R. Dubourg, M. Kissane, M. Baichi, "Study of the Active Role Played by UO2-ZrO2-FP Interactions on Irradiated Fuel Collapse Temperature from VERCORS Tests", J. Nucl. Mat., 344, (2005), 270
IP/Copyright Situation: To be checked
Organization / Localization: CEA
Country: France
Test Identification: HT 2
SA-Related Topics / Phenomena: Fuel degradation, fission-product (FP) behaviour and aerosol characteristics
Measured Parameters: UO2, burn-up=47 GWd/tU, max T=2600
Simulation Code: ASTEC
References: J.P. Leveque et al., "The HEVA experimental programme", Nuclear Technology, Vol. 108, (1994), 33 [2] G. Ducros, P.P. Malgouyres, M. Kissane, D. Boulaud, M. Durin, "Fission Product release under severe accidental conditions; general presentation of the program and synthesis of VERCORS 1 to 6 results" ; Nuclear Engineering and Design 208, (2001), 191 [3] Y. Pontillon, P. P. Malgouyres, G. Ducros, G. Nicaise, R. Dubourg, M. Kissane, M. Baichi, "Study of the Active Role Played by UO2-ZrO2-FP Interactions on Irradiated Fuel Collapse Temperature from VERCORS Tests", J. Nucl. Mat., 344, (2005), 273
IP/Copyright Situation: To be checked
Organization / Localization: CEA
Country: France
Test Identification: HT 3
SA-Related Topics / Phenomena: Fuel degradation, fission-product (FP) behaviour and aerosol characteristics
Measured Parameters: UO2, burn-up=47 GWd/tU, max T=2750
Simulation Code: ASTEC
References: J.P. Leveque et al., "The HEVA experimental programme", Nuclear Technology, Vol. 108, (1994), 33 [2] G. Ducros, P.P. Malgouyres, M. Kissane, D. Boulaud, M. Durin, "Fission Product release under severe accidental conditions; general presentation of the program and synthesis of VERCORS 1 to 6 results" ; Nuclear Engineering and Design 208, (2001), 191 [3] Y. Pontillon, P. P. Malgouyres, G. Ducros, G. Nicaise, R. Dubourg, M. Kissane, M. Baichi, "Study of the Active Role Played by UO2-ZrO2-FP Interactions on Irradiated Fuel Collapse Temperature from VERCORS Tests", J. Nucl. Mat., 344, (2005), 272
IP/Copyright Situation: To be checked
Organization / Localization: CEA
Country: France
Test Identification: HT1
SA-Related Topics / Phenomena: Fuel degradation, fission-product (FP) behaviour and aerosol characteristics
Measured Parameters: UO2, burn-up=47 GWd/tU, max T=2900
Simulation Code: ASTEC
References: J.P. Leveque et al., "The HEVA experimental programme", Nuclear Technology, Vol. 108, (1994), 33 [2] G. Ducros, P.P. Malgouyres, M. Kissane, D. Boulaud, M. Durin, "Fission Product release under severe accidental conditions; general presentation of the program and synthesis of VERCORS 1 to 6 results" ; Nuclear Engineering and Design 208, (2001), 191 [3] Y. Pontillon, P. P. Malgouyres, G. Ducros, G. Nicaise, R. Dubourg, M. Kissane, M. Baichi, "Study of the Active Role Played by UO2-ZrO2-FP Interactions on Irradiated Fuel Collapse Temperature from VERCORS Tests", J. Nucl. Mat., 344, (2005), 271
IP/Copyright Situation: To be checked
Organization / Localization: CEA
Country: France
Test Identification: RT 1
SA-Related Topics / Phenomena: Fuel degradation, fission-product (FP) behaviour and aerosol characteristics
Measured Parameters: UO2, burn-up=47 GWd/tU, max T=2570
Simulation Code: ASTEC
References: J.P. Leveque et al., "The HEVA experimental programme", Nuclear Technology, Vol. 108, (1994), 33 [2] G. Ducros, P.P. Malgouyres, M. Kissane, D. Boulaud, M. Durin, "Fission Product release under severe accidental conditions; general presentation of the program and synthesis of VERCORS 1 to 6 results" ; Nuclear Engineering and Design 208, (2001), 191 [3] Y. Pontillon, P. P. Malgouyres, G. Ducros, G. Nicaise, R. Dubourg, M. Kissane, M. Baichi, "Study of the Active Role Played by UO2-ZrO2-FP Interactions on Irradiated Fuel Collapse Temperature from VERCORS Tests", J. Nucl. Mat., 344, (2005), 274
IP/Copyright Situation: To be checked
Organization / Localization: CEA
Country: France
Test Identification: RT 2
SA-Related Topics / Phenomena: Fuel degradation, fission-product (FP) behaviour and aerosol characteristics
Measured Parameters: MOX, burn-up=41 GWd/tU, max T=2440
Simulation Code: ASTEC
References: J.P. Leveque et al., "The HEVA experimental programme", Nuclear Technology, Vol. 108, (1994), 33 [2] G. Ducros, P.P. Malgouyres, M. Kissane, D. Boulaud, M. Durin, "Fission Product release under severe accidental conditions; general presentation of the program and synthesis of VERCORS 1 to 6 results" ; Nuclear Engineering and Design 208, (2001), 191 [3] Y. Pontillon, P. P. Malgouyres, G. Ducros, G. Nicaise, R. Dubourg, M. Kissane, M. Baichi, "Study of the Active Role Played by UO2-ZrO2-FP Interactions on Irradiated Fuel Collapse Temperature from VERCORS Tests", J. Nucl. Mat., 344, (2005), 275
IP/Copyright Situation: To be checked
Organization / Localization: CEA
Country: France
Test Identification: RT 3
SA-Related Topics / Phenomena: Fuel degradation, fission-product (FP) behaviour and aerosol characteristics
Measured Parameters: MOX, burn-up=3 cycles, Fuel melting
Simulation Code: ASTEC
References: J.P. Leveque et al., "The HEVA experimental programme", Nuclear Technology, Vol. 108, (1994), 33 [2] G. Ducros, P.P. Malgouyres, M. Kissane, D. Boulaud, M. Durin, "Fission Product release under severe accidental conditions; general presentation of the program and synthesis of VERCORS 1 to 6 results" ; Nuclear Engineering and Design 208, (2001), 191 [3] Y. Pontillon, P. P. Malgouyres, G. Ducros, G. Nicaise, R. Dubourg, M. Kissane, M. Baichi, "Study of the Active Role Played by UO2-ZrO2-FP Interactions on Irradiated Fuel Collapse Temperature from VERCORS Tests", J. Nucl. Mat., 344, (2005), 278
IP/Copyright Situation: To be checked
Organization / Localization: CEA
Country: France
Test Identification: RT 4
SA-Related Topics / Phenomena: Fuel degradation, fission-product (FP) behaviour and aerosol characteristics
Measured Parameters: UO2/ZrO2 debris bed, burn-up=3 cycles, Fuel collapse
Simulation Code: ASTEC
References: J.P. Leveque et al., "The HEVA experimental programme", Nuclear Technology, Vol. 108, (1994), 33 [2] G. Ducros, P.P. Malgouyres, M. Kissane, D. Boulaud, M. Durin, "Fission Product release under severe accidental conditions; general presentation of the program and synthesis of VERCORS 1 to 6 results" ; Nuclear Engineering and Design 208, (2001), 191 [3] Y. Pontillon, P. P. Malgouyres, G. Ducros, G. Nicaise, R. Dubourg, M. Kissane, M. Baichi, "Study of the Active Role Played by UO2-ZrO2-FP Interactions on Irradiated Fuel Collapse Temperature from VERCORS Tests", J. Nucl. Mat., 344, (2005), 277
IP/Copyright Situation: To be checked
Organization / Localization: CEA
Country: France
Test Identification: RT 5
SA-Related Topics / Phenomena: Fuel degradation, fission-product (FP) behaviour and aerosol characteristics
Measured Parameters: UO2, burn-up=60 GWd/tU, Fuel collapse
Simulation Code: ASTEC
References: J.P. Leveque et al., "The HEVA experimental programme", Nuclear Technology, Vol. 108, (1994), 33 [2] G. Ducros, P.P. Malgouyres, M. Kissane, D. Boulaud, M. Durin, "Fission Product release under severe accidental conditions; general presentation of the program and synthesis of VERCORS 1 to 6 results" ; Nuclear Engineering and Design 208, (2001), 191 [3] Y. Pontillon, P. P. Malgouyres, G. Ducros, G. Nicaise, R. Dubourg, M. Kissane, M. Baichi, "Study of the Active Role Played by UO2-ZrO2-FP Interactions on Irradiated Fuel Collapse Temperature from VERCORS Tests", J. Nucl. Mat., 344, (2005), 276
IP/Copyright Situation: To be checked
Organization / Localization: CEA
Country: France
Test Identification: RT 6
SA-Related Topics / Phenomena: Fuel degradation, fission-product (FP) behaviour and aerosol characteristics
Measured Parameters: UO2, burn-up=6 cycles, Fuel melting
Simulation Code: ASTEC
References: J.P. Leveque et al., "The HEVA experimental programme", Nuclear Technology, Vol. 108, (1994), 33 [2] G. Ducros, P.P. Malgouyres, M. Kissane, D. Boulaud, M. Durin, "Fission Product release under severe accidental conditions; general presentation of the program and synthesis of VERCORS 1 to 6 results" ; Nuclear Engineering and Design 208, (2001), 191 [3] Y. Pontillon, P. P. Malgouyres, G. Ducros, G. Nicaise, R. Dubourg, M. Kissane, M. Baichi, "Study of the Active Role Played by UO2-ZrO2-FP Interactions on Irradiated Fuel Collapse Temperature from VERCORS Tests", J. Nucl. Mat., 344, (2005), 280
IP/Copyright Situation: To be checked
Organization / Localization: CEA
Country: France
Test Identification: RT 7
SA-Related Topics / Phenomena: Fuel degradation, fission-product (FP) behaviour and aerosol characteristics
Measured Parameters: UO2, burn-up=6 cycles, Fuel melting
Simulation Code: ASTEC
References: J.P. Leveque et al., "The HEVA experimental programme", Nuclear Technology, Vol. 108, (1994), 33 [2] G. Ducros, P.P. Malgouyres, M. Kissane, D. Boulaud, M. Durin, "Fission Product release under severe accidental conditions; general presentation of the program and synthesis of VERCORS 1 to 6 results" ; Nuclear Engineering and Design 208, (2001), 191 [3] Y. Pontillon, P. P. Malgouyres, G. Ducros, G. Nicaise, R. Dubourg, M. Kissane, M. Baichi, "Study of the Active Role Played by UO2-ZrO2-FP Interactions on Irradiated Fuel Collapse Temperature from VERCORS Tests", J. Nucl. Mat., 344, (2005), 279
IP/Copyright Situation: To be checked
Organization / Localization: CEA
Country: France
Test Identification: RT 8
SA-Related Topics / Phenomena: Fuel degradation, fission-product (FP) behaviour and aerosol characteristics
Measured Parameters: UO2, burn-up=47 GWd/tU, max T=2900
Simulation Code: ASTEC
References: J.P. Leveque et al., "The HEVA experimental programme", Nuclear Technology, Vol. 108, (1994), 33 [2] G. Ducros, P.P. Malgouyres, M. Kissane, D. Boulaud, M. Durin, "Fission Product release under severe accidental conditions; general presentation of the program and synthesis of VERCORS 1 to 6 results" ; Nuclear Engineering and Design 208, (2001), 191 [3] Y. Pontillon, P. P. Malgouyres, G. Ducros, G. Nicaise, R. Dubourg, M. Kissane, M. Baichi, "Study of the Active Role Played by UO2-ZrO2-FP Interactions on Irradiated Fuel Collapse Temperature from VERCORS Tests", J. Nucl. Mat., 344, (2005), 281
IP/Copyright Situation: To be checked
Organization / Localization: CEA Cadarache
Country: France
Facility Description: Investigate fission product release and transport during severe accident conditions in nuclear reactor
Facility Status: Closed
Test Identification: VERCORS 1 to 6 VERCORS HT-RT
SA-Related Topics / Phenomena: Quantification of FP release kinetics and released rates as function of accident scenario (thermal cycle, atm) and nature of fuel. Quantification of gas and aerosols produced. Understand the fuel degradation phenomena
Measured Parameters: Release kinetics
Modelling: 1-1.5 bar; from RT to 2600°C; various atmosphere Ar, H2O (steam)/H2 (reducing or oxidising ratio), air, H2; irradiated and re-irradiated at low linear power (in order to recreate the short half-life FP) UO2 and MOX fuel
Simulation Code: ASTEC, AC2, MELCOR
Experimental Research Program: VERCORS
Link to PIRT: WP-1.5 ST-3, ST-5
References: "[1] G. Ducros et al., « Fission product release under severe accidental conditions: general presentation of the program and synthesis of VERCORS 1–6 results », Nuclear Engineering and Design, vol. 208, no 2, p. 191‑203, sept. 2001, doi: 10.1016/S0029-5493(01)00376-4.
[2] Y. Pontillon et al., « Behaviour of fission products under severe PWR accident conditions VERCORS experimental programme—Part 1: General description of the programme », Nuclear Engineering and Design, vol. 240, no 7, p. 1843‑1852, juill. 2010, doi: 10.1016/j.nucengdes.2009.06.028.
[3] Y. Pontillon et G. Ducros, « Behaviour of fission products under severe PWR accident conditions: The VERCORS experimental programme—Part 2: Release and transport of fission gases and volatile fission products », Nuclear Engineering and Design, vol. 240, no 7, p. 1853‑1866, juill. 2010, doi: 10.1016/j.nucengdes.2009.06.024.
[4] Y. Pontillon et G. Ducros, « Behaviour of fission products under severe PWR accident conditions. The VERCORS experimental programme—Part 3: Release of low-volatile fission products and actinides », Nuclear Engineering and Design, vol. 240, no 7, p. 1867‑1881, juill. 2010, doi: 10.1016/j.nucengdes.2009.06.025.
[5] G. Ducros et al., « Synthesis of the VERCORS experimental programme: Separate-effect experiments on Fission Product release, in support of the PHEBUS-FP programme », Annals of Nuclear Energy, vol. 61, p. 75‑87, nov. 2013, doi: 10.1016/j.anucene.2013.02.033.
[6] Y. Pontillon et al., « Lessons learnt from VERCORS tests.: Study of the active role played by UO2–ZrO2–FP interactions on irradiated fuel collapse temperature », Journal of Nuclear Materials, vol. 344, no 1, p. 265‑273, sept. 2005, doi: 10.1016/j.jnucmat.2005.04.053
[7] A. Germain, « Etude de l’impact des équilibres chimiques locaux dans le combustible sur le terme source : de l’accidentel à la fusion du coeur », Thèse, vol. Université Aix-Marseille, 2022."

Organization / Localization: CEA
Country: France
Facility Description: The HT loop consists of many equipment such as a furnace, a thermal gradient tube, impactor, aerosol filter, condeser dryers, cold traps, etc.
Test Identification: VERCORS 1 to 6; VERCORS RT1 to RT4, RT6 to RT8; VERCORS HT1 to HT3
SA-Related Topics / Phenomena: Release and Transport of FPs at high temperature
Measured Parameters: Fuel temperature, FP and transuranic compounds by gamma spectrometry and chemical analysis
Modelling: Fuel burnup, max fuel temperature (1860-1350 °) and duration, nature and initial state of the fuel, atmosphere (H2O+H2, H2, H2O), steam flow rate, hydrogen flowrate
Simulation Code: MAAP4 ASTEC/ELSA ASTEC/SOPHAEROS ALCYONE
Experimental Research Program: VERCORS HT experimental programme
Link to PIRT: ST12, ST13
References: [1] Ducros et al. Synthesis of the VERCORS experimental programme: Separate-effect experiments on Fission Product release, in support of the PHEBUS-FP programme. Annals Nuclear Energy 61 (2013) 75–87. https://doi.org/10.1016/j.anucene.2013.02.033
[2] P. Malgouyres et al., The VERCORS HT facility for studies up to molten fuel conditions. In: Proceedings of the European Working Group Hot Laboratory and Remote Handling Meeting, Windscale, UK, 1998
[3] E. Beuzet et al., Ruthenium release modelling in air and steam atmospheres under severe accident conditions using the MAAP4 code,
Nuclear Engineering and Design, 246, 157-162, 2012, https://doi.org/10.1016/j.nucengdes.2011.08.025
IP/Copyright Situation: partially published




Implemented as part of the Seaknot EU funded project (HORIZON-EURATOM-2021-NRT-01 under Grant Agreement No. 101060327) - WP2.6 UNIPI (2024-2026)