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Fluid mixing ANS flow distribution in the reactor circuit

Objective

The proposed work aims at enhancing the database and improving calculational modelling of fluid mixing and flow distribution phenomena in the PWR primary circuit. These phenomena are important for resolution of boron dilution and steam line break accident issues and for assessing the thermal loading of the primary components.
Mixing is the most important mitigate mechanism against reactivity insertion due to boron dilution or primary circuit overcooling as well as of pressurised thermal shock due to cold emergency cooling water injection. Understanding of the thermal loading is a critical issue for the plant life time-management.
The proposed work includes a well-defined set of mixing experiments in various flow-mixing facilities and justifying the computational fluid dynamic s models for these applications.

Funding Scheme

CSC - Cost-sharing contracts

Coordinator

RESEARCH CENTER ROSSENDORF
Address

01314 Weissig - Dresden
Germany

Participants (11)

AEA TECHNOLOGY PLC
United Kingdom
Address
Winfrith Technology Centre
DT2 8ZE Dorchester
FORTUM ENGINEERING LIMITED
Finland
Address
Rajatorpantie 8
01019 Vantaa
FORTUM NUCLEAR SERVICES OY
Finland
Address
Keilaniementie 1
00048 Espoo
GESELLSCHAFT FUER ANLAGEN- UND REAKTORSICHERHEIT (GRS) MBH
Germany
Address
Forschungsgelaende
85739 Garching
KFKI RESEARCH INSTITUTE FOR MATERIALS SCIENCE
Hungary
Address
Konkoly Thege 29-33
1525 Budapest
NUCLEAR RESEARCH INSTITUTE REZ A.S.
Czechia
Address

250 68 Rez - Praha
PAKS NUCLEAR POWER PLANT
Hungary
Address

7031 Paks
PAUL SCHERRER INSTITUT
Switzerland
Address

5232 Villigen
SERCO LTD
United Kingdom
Address
The Quadrant 404, Birchwood Park
WA3 6AT Warrington
VATTENFALL UTVECKLING AB
Sweden
Address

81426 Aalvkarleby
VUJE TRNAVA INC - ENGINEERING, DESIGN AND RESEARCH ORGANISATION
Slovakia
Address
Okruzna 5
918 64 Trnava