Safety of the Dry Spent Nuclear Fuel Storage. Thermal Regimes
Creators
- 1. A. Podgorny Institute of Mechanical Engineering Problems of the National Academy of Sciences of Ukraine,Kharkiv, (Ukraine)
- 2. V.N. Karzin Kharkiv National University, Kharkiv, (Ukraine)
Description
Safe thermal conditions of the spent fuel assemblies storage represent a key issue of the storage facility safety. The numerical estimation of the thermal state of fuel assemblies was carried out using the methodology of the conjugate heat transfer problems solving. Due to slow changes of decay heat of fuel assemblies during the storage, the modelling of thermal processes inside storage equipment is generally accepted to carry out in the quasi-static formulation. The study was conducted for ventilated storage container with hermetic storage cask filled by helium- containing 24 WWER-1000 fuel assemblies. Detailed structure of the storage cask was modelled taking into account conductive, convective and radiation heat transfer. The temperature field of the concrete container, guided tubes and temperature and velocity fields of the cooling helium inside the cask and cooling air outside the cask were calculated. The hottest assemblies and the maximum temperatures in each assembly were detected. The calculations have been performed for normal equipment operation at average summer temperatures of the place where the storage facility is located. The developed computational model was verified by comparison of calculated and measured temperatures of cooling air outside the storage cask.(author)
Availability note (English)
Also available on-line: http://www.jnrd-nuclear.ro/images/JNRD/No.16/jnrd_168_art2.pdfAdditional details
Identifiers
Publishing Information
- Journal Title
- Journal of Nuclear Research and Development
- Journal Issue
- no.16
- Journal Page Range
- p. 9-13
- ISSN
- 2247-191X
INIS
- Country of Publication
- Romania
- Country of Input or Organization
- Romania
- INIS RN
- 51083142
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Descriptors DEI
- AFTER-HEAT; AIR; CASKS; COMPARATIVE EVALUATIONS; CONCRETES; COOLING; EQUIPMENT; FUEL ASSEMBLIES; HEAT TRANSFER; HELIUM; OPERATION; SAFETY; SIMULATION; SPENT FUELS; STORAGE FACILITIES; TUBES; VELOCITY; WWER TYPE REACTORS
- Descriptors DEC
- BUILDING MATERIALS; CONTAINERS; ELEMENTS; ENERGY SOURCES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EVALUATION; FLUIDS; FUELS; GASES; MATERIALS; NONMETALS; NUCLEAR FUELS; POWER REACTORS; PWR TYPE REACTORS; RARE GASES; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 5 refs., 10 figs.; This record replaces 51003170