SADD - Severe accident database directory

Corium properties and ATF (COPRAT) (1)

Facility Description: Different facilities for properties measurements
Test Identification:
SA-Related Topics / Phenomena: corium
Measured Parameters: Kinematic viscosity (C-100: 62UO2 + 38ZrO2; C-22: 62UO2 + 8.4ZrO2 + 29.6Zr) Thermal conductivity (C-22: U-69mass%, Zr-16.7 mass%; C-100: U-68.2 mass%, Zr-16.7 mass%) Density (C-100: U/Zr = 1.528) Surface tension (C-22; C-32; C-100) Electric conductivity (C-22; C-50; C-100)
Modelling:
Simulation Code:
Experimental Research Program: RASPLAV
Link to PIRT:

Show/Hide Additional Details ▼

References: V.G. Asmolov, S.S. Abalin, A.V. Merzliakov, V.N. Zagryazkin, Ye.V. Astakhova, I.D. Daragan, V.D. Daragan, Ye.K. D’yakov, A.Yu. Kotov, A.S. Maskaev, Ye.M. Rakitskaja, V.M. Repnikov, V.Yu. Vishnevsky, V.V. Volkov, A.G. Popkov, V.F. Strizhov. 2000. RASPLAV Final Report Attachment C. Properties Studies: Methodology and Results
Contributed By:
IP/Copyright Situation: OECD project

Focus area 1: Fission product release (including in-vessel, ex-vessel) (1)

Facility Description: study the behavior of molten core materials (corium) in the lower head of a reactor pressure vessel during severe accidents
Test Identification: EVAN
SA-Related Topics / Phenomena:
Measured Parameters: Melt oxidation index, melted surface temperature, carrier gas temperature, FP mass release and aerosol composition
Modelling: Zr oxidation index: 70,80 and 100%; gas atmosphere Ar with 0 to 20% O2; pool temperture 2800-2970 K
Simulation Code: IVTANTHERMO GEMINI/NUCLEA MAVR-TA RATEG/SVECHA
Experimental Research Program: ISTC METCOR, METCOR-P, EVAN projects and NEA/OECD MASCA program
Link to PIRT: WP-1.5 ST-5

Show/Hide Additional Details ▼

References: [1] S.V. Bechta et al.,
«Influence of corium oxidation on fission product release from molten pool», Nuclear Engineering and Design, vol. 240-5,
p. 1229-1241, 2010, https://doi.org/10.1016/j.nucengdes.2010.01.008https://doi.org/10.1016/j.nucengdes.2010.01.008
[2] Yu.B. Shmelkov et al., «Development and validation of the MAVR-TA code for analyzing the release and transport of fission products during a severe accident at a VVER NPP. Part 3 – Modelling of the release of fission products from the melt», Nuclear Engineering and Design, vol. 415, p. 112694, 2023, https://doi.org/10.1016/j.nucengdes.2023.112694
[3] A. Sulatsky et al., «Experimental study of oxidic-metallic melt oxidation», Nuclear Engineering and Design, vol. 363, p. 110618, 2020, https://doi.org/10.1016/j.nucengdes.2020.110618
[4] FSUE SPAEP, «Source Term Assessment at Ex-vessel Stage of Severe Accident», Final Project Technical Report, ISTC Project #3345, Moscow, Jan 2006

Facility Details: RASPLAV