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ASTEC extension to other reactor types than Generation II PWR J.P. Van Dorsselaere (IRSN), B.Schwinges (GRS), M.Buck (IKE), W.Ma (KTH), M.Constantin (INR), J.Jancovic (VUJE), G.Ratel (CEA). Contents. ASTEC adaptation to Gen.II VVER ASTEC adaptation to Gen.III PWR (incl. EPR)

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  1. ASTEC extension to other reactor types than Generation II PWRJ.P. Van Dorsselaere (IRSN), B.Schwinges (GRS), M.Buck (IKE), W.Ma (KTH), M.Constantin (INR), J.Jancovic (VUJE), G.Ratel (CEA)

  2. Contents • ASTEC adaptation to Gen.II VVER • ASTEC adaptation to Gen.III PWR (incl. EPR) • ASTEC adaptation to BWR • ASTEC adaptation to CANDU • Conclusions

  3. ASTEC requirements on NPP types • Initial IRSN-GRS requirements: to cover present and future PWR, VVER, BWR. • Priority was given to Gen.II PWR and VVER in the last years, • Under way: adaptation to BWR, • Next important stage: to cover new Gen.III+ designs, such as EPR in priority, then advanced NPP with capability of In-Vessel-Melt-Retention (IVMR). • At SARNET’s start, the objective to cover all European NPP was added, and reinforced in SARNET2  need of extension to CANDU reactors. • In ASTEC Topic, several partners worked with IRSN and GRS to investigate the modelling needs for BWR (IKE, KTH + PSI review) and CANDU (INR + AECL support)  ASTEC V2 plans and SARNET2 work.

  4. ASTEC adaptation to Gen.II VVER (1/2) • Many benchmarks on VVER plant applications were performed by partners in SARNET, either on VVER-1000 or VVER-440, and for various SA scenarios (LOCA, SBO, LOFW…)  Shows ASTEC V1 applicability to VVER, up to iodine behaviour in containment. primary side secondary side VVER-440 case: assumptions to account for canisters  improv. in ASTEC V2 by BWR work Optimisation of horizontal SG CESAR nodalisation

  5. ASTEC adaptation to Gen.II VVER (2/2) • Good results of VVER-specific validation: • CESAR on PACTEL scaled-down facility of Loviisa VVER-440/V213: natural circulation in primary system for single- and two- phase flow regimes, • Former CPA application to EREC T5 (LBLOCA) VVER-440 containment t/h exp., with bubble condenser towers. Containment pressure in EREC T5 Primary pressure on PACTEL-ISP33

  6. ASTEC adaptation to EPR (1/2) • IRSN applied ASTEC stand-alone modules (MEDICIS, CPA) and analytical models in 2006 to EPR SA scenarios: • No model extension needed for RCS thermalhydraulics (CESAR) and core degradation (ICARE2), • No mod.extension for containment, esp. the two-room concept (CPA), • Only need: couple/“integrate” several existing models in ASTEC for core-catcher behaviour. • 1st integrated possible simulation with ASTEC V2.0 in March 09 (improvements will follow..).

  7. ASTEC adaptation to EPR (2/2) • Modelling of core-catcher in 4 different parts: • MCCI in cavity: MEDICIS use with new model of radiative exchanges (absorbing atmosphere) between corium, vessel LH and cavity walls. Account for possible melt-through of concrete upper cavity walls. • Erosion of cavity substrate and corium pouring kinetics into the core-catcher: simple model (Bernoulli flow approach, MDB properties). • Corium spreading along spreading chamber: 2 levels of approaches, • At first: simplified analytical correlation (probably based on KTH one) for cases of fast and complete spreading, later a further correlation • Later on, more detailed model (such as LAVA GRS code) for cases of slow spreading. If incomplete spreading: flag for the user, out of ASTEC scope.Necessary also for existing PWR and BWR 69 • MCCI in spreading chamber with upward water cooling: MEDICIS use with boundary conditions for cooling circuit in the basemat (interface with 2D thermal codes for detailed analysis of these cooling structures).

  8. Void fraction Twall hpipe Tpipe CESAR : closed loop ASTEC adaptation to IVMR (1/2) • CEA assessment of CESAR-DIVA capabilities: • CESAR calculation of external circuit as an independent channel. • Coupling CESAR-DIVA between vessel external surface and coolant. DIVA corium and LH

  9. ASTEC adaptation to IVMR (2/2) • CEA validated CESAR (stand-alone mode) on SULTAN (CEA) and ULPU (Univ. Santa Barbara) experiments.  CESAR acceptable stability to simulate two-phase flow in natural convection but still numerical oscillations. • Further validation of CESAR-DIVA coupling on LIVE (FZK) and HERMES-HALF (KAERI) experiments. Example on SULTAN: Good results with correct reproduction of S-shape of pressure drop linked to the flow in a heating canal. CESAR simulation of SULTAN

  10. ASTEC adaptation to BWR (1/4) • KTH-IKE-GRS ranking concluded on: • Applicability of most ASTEC V1 models: few adaptations are necessary, • Main needs: • To adapt core degradation models, • New models for lower plenum (CRGTs..), formation of ex-vessel debris bed and coolability. • This was confirmed by ASTEC V1exploratory calculations: • DIVA application by IKE to the CORA-18 experiment on degradation of a BWR bundle, but application to real core • BWR benchmark by GRS on containment thermalhydraulics with COCOSYS code, • (under way) CESAR calculations by GRS of steady-state and transient (front end) with comparison to ATHLET code results.

  11. ASTEC adaptation to BWR (2/4) CORA-18 bundle geometry Fuel temperatures at 750 mm Final ASTEC state of degraded bundle Hydrogen mass

  12. ASTEC adaptation to BWR (3/4) • CPA application by GRS to a scenario “Loss of main heat sink plus loss of pressure limitation” in a German BWR (’72) containment • Global agreement between ASTEC and COCOSYS results, • but some differences (e.g. temperatures, mass flow rates through vent pipes), likely due to different heat transfer models. pressure temperature

  13. ASTEC adaptation to BWR (4/4) • Conclusions on core degradation models: • Review of modelling in ASTEC and other SA codes indicates that BWR core components can be modelled based on available or only slightly modified ASTEC models, • But major effort required on t/h feedback with core degradation  need of a 2D CESAR in-core t/h (planned by IRSN in ASTEC V2). • Other main needs of model adaptations: • ICARE2 for complex geometry of lower plenum (CRGT…)  Should not create large difficulties… • Models for formation of debris beds at corium slump into a flooded cavity (plus its coolability). • Verification (or extension) of validity of containment iodine models up to 800K temperatures.

  14. ASTEC adaptation to CANDU (1/4) • INR analysis of existing ASTEC models and of needs of adaptations: • Applicability of most ASTEC V1 models: very few adaptations are necessary, • Need to adapt core degradation models. • This was confirmed by INR exploratory plant applications in SARNET to CANDU: • Physically reliable results of coupled SOPHAEROS-CPA-IODE calculation on FP transport and behaviour  PHT plays a good filter role for FPs; similar results to literature ones. • CESAR simulation of PHT thermalhydraulics (benchmark with CATHENA code from AECL to be performed).  Consistent with BARC (India) conclusions, as presented in ERMSAR-2007.

  15. ASTEC adaptation to CANDU (2/4) Example of CESAR and CPA INR nodalisations resp. for PHT and containment

  16. ASTEC adaptation to CANDU (3/4) • Needs of ICARE2 model adaptations: • Heat transfers between fuel bundles, pressure tubes and moderator  adaptation of existing models, • Oxidation (internal and external) of pressure tubes, heat-up and deformation of fuel bundles  adaptation of existing models, • Good results of INR validation of fuel channels oxidation models on AECL experiments. • Ballooning and sagging (“disassembly”) of fuel channels  new specific models, • Formation of solid 3D debris beds on calandria, heat transfer between debris and water from the protection tank  use of the 2D ICARE/CATHARE debris models as basis for this investigation.

  17. ASTEC adaptation to CANDU (4/4) • In SARNET2, INR will continue their investigations, with support of AECL knowledge: • Further validation of ASTEC models, • Benchmarks with AECL codes (CATHENA, MAAP4-CANDU). • All this work will take a great benefit of the strong bilateral collaboration on CANDU models between IRSN and BARC (India) that will still be reinforced from 2009.

  18. Conclusions • ASTEC V1 is today fully applicable to Gen.II PWR and VVER (440 and 1000), and partly to CANDU reactors (BWR investigations are under way with promising results). • The 1st version V2.0 of the new series of ASTEC versions, to be released in March 09, will allow to simulate: • SA scenarios in EPR, • In-Vessel-Melt-Retention for some Gen.III designs. • The identification and ranking of needs of model adaptations to BWR and CANDU, done in SARNET, will lead to a further step in SARNET2, with model developments and assessment (validation and benchmarks). • Plans to get mid-2011 the 1st version applicable to the major part of SA sequences in BWR and CANDU.

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