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Multidimensional Modelling of Temperature Distribution in Spent Fuel Pools of Vver-1000 and Vver-440 Using Fluent Cfd Code

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Multidimensional Modelling of Temperature Distribution in Spent Fuel Pools of Vver-1000 and Vver-440 Using Fluent Cfd Code MULTIDIMENSIONAL MODELLING OF TEMPERATURE DISTRIBUTION IN SPENT FUEL POOLS OF VVER-1000 AND VVER-440 USING FLUENT CFD CODE Martin Blaha, Jan Frélich TES s.r.o., Pražská 597, 674 01 Třebíč, Czech Republic [email protected], [email protected] ABSTRACT The paper presents results of CFD calculations of spent fuel storage pool at VVER-440 and VVER-1000 units. The calculations were performed by the Fluent 6.2 CFD code. Standard nuclear safety problems of spent fuel pools, such as k eff calculation or spent fuel pool dry-out have been frequently discussed in many other papers. This paper pays special attention to more technical problems related to spent fuel pool operation in the Czech Republic NPP's Dukovany and Temelín. Following several problems had been identified during nuclear power plant operation and shutdown procedure validation: 1 Inadequate water temperature and water level measurements 2 Repeated cracking of pool stainless steel lining 3 Lack of data for shutdown procedure validation The first two items were supposed to have a common cause – significant non-uniformity of pool water temperature fields and related strong buoyancy effects. We have analysed flow patterns in spent fuel pools and temperature fields at pool walls using the Fluent CFD code to verify this assumption and to solve above-mentioned problems. Both steady state and transient calculations have been performed. This paper also includes basic comparison of flow pattern in spent fuel pools of VVER-440 and VVER-1000 and evaluation of typical large pool systems modelling features. 1 INTRODUCTION Nuclear power plants of VVER type are originally equipped with storage facilities for the wet storage of spent fuel assemblies (FA). The safety function of the spent fuel pool (SFP) and storage racks is to cool the spent fuel assemblies and maintain them in a subcritical array during all credible storage conditions. Subcriticality is maintained using high density boron substituted storage racks. Borated water is used as an extra insurance against criticality; however subcriticality has to be maintained in case of zero boron concentration in pool water. Thick water layer above stored FA provides for radiation shielding in any operational mode as well as for sufficient spent fuel cooling. Standard nuclear safety problems of spent fuel pools, such as k eff calculation or spent fuel pool dry-out have been frequently discussed in many other papers. This paper pays special attention to more technical problems related to spent fuel pool operation in the Czech Republic NPP's Dukovany (VVER-440/213, 4 units) and Temelín (VVER-1000/320, 2 units). Several SFP problems have been identified during nuclear power plant commissioning and operation. NPP Temelín experts realized that there is insufficient operational diagnostics of SFP temperature and level. SFP temperature measurement did not properly detect a pool temperature rising 2,5 hours after SFP loss of cooling accident, which occurred at 1st unit of NPP Temelín at 05/13/2004. There were also identified unphysical SFP measured level oscillations which repeatedly occurred after cooling system inlet flow temperature changes. Repeated cracking of SFP stainless steel lining was also identified. These events were supposed to have a common cause – significant non-uniformity of pool water temperature fields. To verify this assumption and to solve above-mentioned problems of NPP Temelín SFP we have analysed flow patterns in spent fuel pools and temperature fields at pool walls using the Fluent CFD code. Both steady state and transient calculations have been performed. This paper also includes results of CFD calculations of NPP Dukovany SFP. Main reasons for performing of CFD analysis of Dukovany SFP was lack of data for shutdown procedure validation and the need for evaluating of quality of SFP temperature measurement. 2 VVER-1000/320 SFP GEOMETRY AND BASIC DATA Each of two reactors of NPP Temelín is originally equipped with underwater storage of spent fuel assemblies and control rods. NPP Temelín spent fuel pools are sized to store fuel assemblies of 9 years of reactor operation (including forced unloading of complete operating core if necessary). Temelín SFP has a typical PWR SFP design (see Fig. 1). The pool is a rectangular enclosure constructed of reinforced concrete and lined with double-layer stainless steel plate. NPP Temelín SFP is divided into 4 sections. Section B01 and B03 are intended for standard refuelling. Section B02 (and part of section B03) is intended for forced unloading of complete core. All sections and are connected to each other and to the reactor shaft by channels. The pool is designed for two working water levels, which must provide for radiation shielding in any operational mode as well as for sufficient spent fuel cooling. The operational level is 8,13 m in depth and the refuelling level is 15,5 m in depth. High density fuel storage racks are located on the floor of the pool. Fuel assemblies are placed in vertical hexagonal tubes (288 mm centre-to-centre, tube height 3,6 m, stainless steel). Material of these tubes is 1% boron substituted to maintain sufficiently low neutron multiplication constant (even when fresh fuel is loaded into the rack). Borated water is used as an extra protection against criticality; however subcriticality has to be maintained in case of zero boron concentration in pool water. There are 3 cooling circuits for SFP Temelín. Each of circuits is designed for SFP maximum decay heat removal 10,5 MW. The maximum DH calculated in Temelín Safety Report is 8 MW (using conservative approach). The maximum operational pool temperature shall not exceed 45°C for normal operation and 58°C for fuel reloading. Each SFP section is equipped with the temperature and level measurement. The temperature measurement in each section is provided by one thermocouple placed near the pool wall approx. 5 cm above pool floor (see the yellow line in Fig. 1 which represents a thermocouple guide tube). The water level measurement is provided by thermocouple measurement. Water level indicating thermocouples are placed along the thermocouple guide tube. Figure 1. VVER-1000/320 spent fuel pool geometry 3 VVER-1000 SFP PRELIMINARY CALCULATION Preliminary SFP calculations were performed in order to verify convenience of Fluent CFD code application in this case, to reveal potentially weak points of CFD model and calculation and to reduce number of SFP modes to be analyzed. Typical flow patterns should have been analysed and assumption of strong pool temperature nonhomogeneity should have been verified. The operator request for preliminary calculation extent was to perform post-test CFD analysis of spent fuel pool loss of cooling accident which occurred at 1st unit of NPP Temelín at 05/13/2004. Temelín experts found out that the pool temperature measurement did not properly detect a pool temperature rising for 165 minutes after complete loss of cooling system flow. Spent fuel pool mode before loss of cooling (Initial Conditions) The SFP was in standard refueling mode (water level 15,5 m). Sections B01 and B03 were connected to the section B04. There was an empty storage rack in section B03 and no internals in the section B04. 163 fuel assemblies were located in part of middle section B01. The total heat generation in the pool 3,9 MW t was determined by using standard plant measurement from energy balance on cooling system heat exchanger. One cooling system (CS) was connected to the section B01 (both inlet and outlet). Cooling system flow was 440 m3/hr, temperature 36,5°C. Accident scenario (Boundary Conditions): 0 s total loss of SFP cooling system flow 165 min CS flow restoration 290 min B01, B03 and B04 pool water surface temperature 55°C (by hand thermometer) SFP model description A relatively coarse SFP model was developed (45 000 cells) using hybrid mesh. Storage racks and fuel assemblies were modelled as porous media. Uniform distribution of DH power over loaded part of the storage rack in section B01 was applied. Cooling system distribution header was modelled as simplified boundary condition (uniform flow from the pool floor). Pressure boundary condition was applied in cooling system outlet pipe. Heat losses on the pool walls and water surface were neglected. K-omega turbulence model was applied. Figure 2. Example of preliminary SFP model surface mesh VVER-1000 preliminary calculations results Three different states of SFP loss of cooling accident (both steady-state and transient) are presented bellow: 1 Steady state - just before CS flow termination 2 Transient1 - 165 min after pump shut-down and just before CS pump restart 3 Transient2 - 165 min after CS pump restart and CS flow restoration The presented figures represent cross sectional views, which intersect the centre of loaded part of the storage rack, the upper figures front views and the lower figures side views. SFP section disposition should be clear from legend. In order to compare all calculated modes, all presented figures have the same thermal spectrum range. Steady state - before CS flow termination The calculation took 8 hrs of CPU time on Opteron 246 processor. The calculation of steady state mode (the pool cooling system is under normal operation) indicates that the pool temperature distribution below CS outlet pipe is stratified in the vertical direction with an inlet flow temperature of 36,5°C and with average FA outlet temperature of 45°C. There is relatively strong upstream from FA outlets, which tends to outlet pipe. Buoyancy effects accelerate flow through heated (loaded) storage rack channels. Hot upstream from loaded rack channels is subsequently reversed under the water surface and a strong momentum of this stream leads to creating of water circulation regions above the storage rack outlet, thus there is relatively high temperature homogeneity above CS outlet pipe.
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