# Method for Computing the Maximum Water Temperature in a Fuel Pool Containing Spent Nuclear Fuel

TL;DR: In this paper, a method for computing the upper hound on the local water temperature rise with respect to the hulk temperature in a spent fuel pool is proposed, which involves casting the continuity and momentum relationships in integral form in terms of the unknown velocity functions.

Abstract: A method is proposed for computing the upper hound on the local water temperature rise with respect to the hulk temperature in a spent fuel pool. The solution involves casting the continuity and momentum relationships in integral form in terms of the unknown velocity functions. The method of collocation is used to solve the problem. Computer application of this method shows it to he an efficient and cost-effective design tool.

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01 Jan 2000

TL;DR: In this article, the authors investigated the impact of spent fuel reracking on thermal-hydraulic parameters of the NPP Krsko spent fuel pool and derived the total generated heat in the spent fuel pools at the end of its lifetime (year 2023).

Abstract: EXTENDED ABSTRACT The most attractive option for solving the problem of increasing spent fuel pool capacity is reracking of spent fuel assemblies. As by reracking the number of spent fuel assemblies and generated decay heat will be increased and the distance between spent fuel assemblies will be decreased, it will affect thermal-hydraulic parameters of spent fuel pool. Our aim was to develop a simple model of the spent fuel pool which will enable calculation of thermalhydraulic parameters of the reracked spent fuel pool. The capacity of the NPP Krsko spent fuel pool will be also increased by reracking. With the assumptions of 12 months working cycle and 40 years of operation, at the end of the NPP Krsko lifetime 1527 spent fuel assemblies will be stored in the spent fuel pool. We have investigated the impact of spent fuel reracking on thermal-hydraulic parameters of NPP Krsko spent fuel pool. The total generated heat in the spent fuel pool at the end of the NPP Krsko lifetime (year 2023) is calculated using the ORIGEN-PC computer code. The ORIGEN-PC computer code has been developed at Oak Ridge National Laboratory for calculation of isotopic inventory, activity and decay heat of nuclear fuel. According to discharge burnup and cooling time the NPP Krsko spent fuel assemblies are divided into 77 groups and decay heat of each group has been calculated using ORIGEN-PC. The total generated heat in the spent fuel pool at the end of the NPP Krsko lifetime (year 2023) has been estimated to 6.520 kW. The thermal-hydraulic modeling of the NPP Krsko reracked spent fuel pool has been performed using the computer code GOTHIC. The computer code GOTHIC is general purpose thermal-hydraulic computer code for designing, licensing as well as safety and operational analyses of containment and other confined buildings. A model of the NPP Krsko spent fuel pool for the computer code GOTHIC has been developed, containing 8 control volumes, 17 junctions, and 14 heat structures. Using this model and total generated heat of 6520 kW the NPP Krsko reracked spent fuel pool thermal–hydraulic parameters for steady state and during loss of cooling were determined.

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TL;DR: In this paper, a computing technique for low-speed fluid dynamics has been developed for the calculation of three-dimensional flows in the vicinity of one or more block-type structures, where the full time-dependent Navier-Stokes equations are solved with a finite-difference scheme based on the Marker-and-Cell method.

413 citations

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14 Dec 1992

TL;DR: The twenty-two chapters in this book are prefaced by brief descriptions of the computer codes referenced or listed within the pages that follow as discussed by the authors, and the remaining chapters address mechanical and thermal design as well as manufacturing.

Abstract: The twenty-two chapters in this book are prefaced by brief descriptions of the computer codes referenced or listed within the pages that follow. The first chapter, which contains an outline of the more accepted heat-exchanger types and basic design considerations, is followed by another outlining various design-stress criteria. The next twenty chapters contain considerable detailed information concerning the design and operation of heat exchangers. The authors devote 121 pages to one of the most important design considerations, flow-induced vibration. Another chapter is dedicated to methods of seismic analysis. The remaining chapters address mechanical and thermal design as well as manufacturing.

27 citations

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01 May 1983

TL;DR: GFLOW as mentioned in this paper is a three-dimensional numerical model of natural circulation thermal-hydraulics, developed as a tool for spent fuel pool design and licensing to compare predictive results with actual test data, a post-test GFLOW simulation using measured pool power levels and boundary conditions was exected after the measurements were completed.

Abstract: Experimental measurements of the thermal hydraulic conditions at the Maine Yankee spent nuclear fuel storage pool were made 25 days after reactor shutdown and the full core had been off-loaded for the ten-year vessel inspection The GFLOW computer code was used to pre-predict the experimental results as a guide to designing the experimental program GFLOW is a three-dimensional numerical model of natural circulation thermal-hydraulics, developed as a tool for spent fuel pool design and licensing To compare predictive results with actual test data, a post-test GFLOW simulation using measured pool power levels and boundary conditions was exected after the measurements were completed Both the measurements and the computer predictions indicate that the Maine Yankee fuel storage pool is very quiescent with nearly homogenous thermal conditions at any given elevation A thermal stratification exists in the vertical direction with temperatures varying from 92/sup 0/F(33/sup 0/C) at the pool bottom to 99/sup 0/F (37/sup 0/C) at the top surface The average fuel assembly exit temperature is 97/sup 0/F (36/sup 0/C) with a maximum coolant temperature in the hottest assemblies of approximately 104/sup 0/F (40/sup 0/C) The average fluid velocity in the pool predicted by GFLOW was 009 ft/sec (003 m/sec) Experimentally, velocitiesmore » were found to be 00 +- 02 ft/sec Temperatures and velocities were observed to fluctuate with time at any given location in the pool Representative magnitudes of these fluctuations are +-2/sup 0/F (+-1/sup 0/C) for temperature and +- 005 ft/sec (02 m/sec) for velocity In general, the GFLOW predicted temperatures were within 1/sup 0/F (05/sup 0/C) of the measured results« less

4 citations