会议专题

NUMERICAL SIMULATION OF THE INSULATION MATERIAL TRANSPORT TO A PWR CORE UNDER LOSS OF COOLANT ACCIDENT CONDITIONS

In 1992, strainers on the suction side of the ECCS pumps in Barseb?ck NPP Unit 2 became partially clogged with mineral wool because after a safety valve opened the steam impinged on thermally-insulated equipment and released mineral wool. This event pointed out that strainer clogging is an issue in the course of a loss-of-coolant accident. Modifications of the insulation material, the strainer area and mesh size were carried out in most of the German NPPs. Moreover, back flushing procedures to remove the mineral wool from the strainers and differential pressure measurements were implemented to assure the performance of emergency core cooling during the containment sump recirculation mode. Nevertheless, it cannot be completely ruled out, that a limited amount of small fractions of the insulation material is transported into the RPV. During a postulated cold leg LOCA with hot leg ECC injection, the fibers enter the upper plenum and can accumulate at the fuel element spacer grids, preferably at the uppermost grid level. This effect might affect the ECC flow into the core and could result in degradation of core cooling. It was the aim of the numerical simulations presented to study where and how many mineral wool fibers are deposited at the upper spacer grid. The 3D, time dependent, multi-phase flow problem was modelled applying the CFD code ANSYS CFX. The CFD calculation does not yet include steam production in the core and also does not include re-suspension of the insulation material during reverse flow. This will certainly further improve the coolability of the core. The spacer grids were modelled as a strainer, which completely retains all the insulation material reaching the uppermost spacer level. There, the accumulation of the insulation material gives rise to the formation of a compressible fibrous cake, the permeability of which to the coolant flow is could still enter the core. 

Thomas H(o)hne Alexander Grahn S(o)ren Kliem Ulrich Rohde Frank-Peter Weiss

Forschungszentrum Dresden-Rossendorf (FZD) -Institute of Safety Research P.O.Box 510119, D-01314 Dresden, Germany

国际会议

18th International Conference on Nuclear Engineering(第18届国际核能工程大会 ICONE 18)

西安

英文

1-10

2010-05-17(万方平台首次上网日期,不代表论文的发表时间)