• Keine Ergebnisse gefunden

Severe Accident Volatile Iodine Release from Containment vs.

N/A
N/A
Protected

Academic year: 2022

Aktie "Severe Accident Volatile Iodine Release from Containment vs. "

Copied!
1
0
0

Wird geladen.... (Jetzt Volltext ansehen)

Volltext

(1)

The 2nd Meeting of the “European MELCOR User Group”

Organized by Nuclear Research Institute Řež plc.

Hosted by Czech Republic State Office for Nuclear Safety, Prague, Czech Republic March 1-2, 2010

Severe Accident Volatile Iodine Release from Containment vs.

Sump Alkalinity

by

Gabor L. Horvath, NUBIKI,Budapest

ABSTRACT

MELCOR 1.8.6 Iodine Pool Model (IPM) has been applied to VVER-440/213 severe accident using a Full Circuit Input Model (FCIM) without IMP and a simplified version called Stand Alone Containment input model (SACIM) but with IPM. The stand alone model gets mass end energy and aerosol source terms calculated by the full circuit model. This approach made possible to calculate the behaviour of volatile iodine by the IPM model several orders of magnitude faster then with the FCIM with IPM up to 1 month process time. Results show that with proper alkalinity in the sump the release of volatile iodine on the long term does not pose an extra threat to public compared to initial aerosol form release of iodine, but lack of proper alkalizing makes long term troubles.

Experience of application and shortcomings of the MELCOR 1.8.6 IPM model are highlighted.

Visualisation of the results using the ATLAS (GRS) software will be demonstrated.

Referenzen

ÄHNLICHE DOKUMENTE

The secondary circuit input model is limited to two SGs connected to the double primary loop on natural circulation.. Secondary coolant in these two SGs is cooled by a

Volatile I released to environment 1345 32 Volatile I suspended in operating rooms 3910 88 Volatile iodine does not pose a problem with proper alkalizing. compared to aerosol

Model of the core barrel bottom lower grid (grid supporting movable assemblies). ∙ Old model — user defined SS, failure criterion 1200 K,

 C1-C2: Injection into RPV to terminate/mitigate MCCI inside the reactor cavity (by volume control system, accumulators and/or from SFP), maximizing heat removal from

55.0 Spray water from RWST 135 seconds delay to reach full flow of 253 kg/s (linear ramp). Accumulators empty 56.1 End of reflood 195.0 Froth

Design-basis accident source term calculations are used to establish the adequacy of siting for commercial nuclear power plants and to ensure. that adequate radiation protection

— MELCOR reference code in Tractebel for severe accident calculation includes a point kinetic model (not valid for degraded geometries)..  Development of a surrogate model

• Comparison of the APROS containment model using detail nodalization of room A201 of VVER 440/V213 containment with the MELCOR 1.8.5. containment model showed applicability of