Report of the OECD/NEA-Vattenfall T-Junction Benchmark exercise
Eric Mathet, OECD-NEA MASCA Seminar June 2004 PROJECT USE ONLY 1.
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Eric Mathet, OECD-NEA 1 MASCA Seminar June 2004 PROJECT USE ONLY
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Eric Mathet, OECD-NEA MASCA Seminar June 2004 PROJECT USE ONLY 3 OECD - RASPLAV –the corium melt behaved comparably to the simulant material in its natural circulation, therefore previous evaluations based on simulant material data could be scaled to prototypic reactor conditions –BUT... OECD - MASCA Sufficient knowledge of fission product spatial and chemical distributions in the melt pool as well as prototypic liquid corium stratification is lacking. Well ‑ designed experiments obtained with corium compositions prototypical of power reactors was supposed to provide the technical support for assessments of the in- vessel melt pool retention strategy as well as of ex-vessel phenomena. To address the conditions under which molten core material can be retained inside the reactor pressure vessel (RPV) by cooling of the vessel from outside OECD – MASCA2 The influence of an oxidizing atmosphere and the impact of non- uniform temperatures (presence of crusts or solid debris) is addressed in addition to scaling effects. The program is also intended to generate data on relevant physical properties of mixtures and alloys.
Transcript of Eric Mathet, OECD-NEA MASCA Seminar June 2004 PROJECT USE ONLY 1.
Eric Mathet, OECD-NEA 1MASCA Seminar June 2004
PROJECT USE ONLY
Eric Mathet, OECD-NEA 2MASCA Seminar June 2004
PROJECT USE ONLY
Special thanksto
Organizing Committee Members
Mr. Richard GONZALEZ IRSN FRANCE (Chairman)Dr. Mani MATHEW AECL CANADADr. Harri TUOMISTO FORTUM Nuclear Services Ltd FINLAND
Dr. Christoph MULLER GRS GERMANYDr. Zoltan HOZER AEKI HUNGARYMr. Nickolay KISSELEV KURCHATOV RUSSIAN FEDERATIONDr. Valerii STRIZHOV NSI/ RAS RUSSIAN FEDERATION
Dr. Alireza BEHBAHANI NRC USA
and to the IRSN staff for its help with the organization
Eric Mathet, OECD-NEA 3MASCA Seminar June 2004
PROJECT USE ONLY
OECD - RASPLAV– the corium melt behaved
comparably to the simulant material in its natural circulation, therefore previous evaluations based on simulant material data could be scaled to prototypic reactor conditions
– BUT ...
OECD - MASCASufficient knowledge of fission product
spatial and chemical distributions in the melt pool as well as prototypic liquid corium stratification is lacking. Well‑designed experiments obtained with corium compositions prototypical of power reactors was supposed to provide the technical support for assessments of the in-vessel melt pool retention strategy as well as of ex-vessel phenomena.
To address the conditions under which molten core material can be retained inside the reactor pressure vessel (RPV) by cooling of the vessel from outside
1994-1999
2000-2003
2003-2006
OECD – MASCA2The influence of an oxidizing
atmosphere and the impact of non-uniform temperatures (presence of crusts or solid debris) is addressed in addition to scaling effects. The program is also intended to generate data on relevant physical properties of mixtures and alloys.
