دانلود رایگان مقاله لاتین آنالیز حرارتی بشکه کرچک از سایت الزویر
عنوان فارسی مقاله:
آنالیز حرارتی بشکه کرچک RBMK-1500 در طول ذخیره سازی طولانی مدت سوخت هسته ای
عنوان انگلیسی مقاله:
Thermal analysis of CASTOR RBMK-1500 casks during long-term storage of spent nuclear fuel
سال انتشار : 2017
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مقدمه انگلیسی مقاله:
1. Introduction
The Ignalina Nuclear Power Plant (INPP) in Lithuania operated two RBMK-1500 water-cooled graphite-moderated channel-type power reactors. The first reactor was shutdown at the end of 2004, and the second one was closed at the end of 2009. For storage of spent nuclear fuel (SNF), the so-called ‘‘dry” storage technology was selected. Using this technology, SNF is pre-stored in water pools (at least for 5 years) and then loaded into metal CASTOR RBMK-1500 or metal-concrete CONSTOR RBMK-1500 casks, and then stored in the open-type SNF storage facility that was commissioned in 1999; the planned interim storage period is 50 years. A new closed-type storage facility for larger capacity CONSTOR RBMK-1500/M2 casks where the remaining SNF will be stored is under construction. However, commissioning of the geological repository for disposal of SNF is foreseen later than the planned interim storage period ends. In relation to this, the possibility to extend the long-term storage period (up to 300 years) needs to be considered. For safe storage of SNF for such a long period of time, it is necessary to ensure nuclear safety, radiation safety, and safe thermal conditions. In order to fulfill the requirements set for the safety of fuel bundles, casks and storage facilities where casks are stored, deep understanding of different processes that take place in a cask and also its interaction with the environment is crucial. From the thermal point of view, the main parameters determining the safe storage of SNF in casks are the maximum allowed fuel rod cladding temperature and the maximum allowed cask external surface temperature. It is established that in the case of long-term storage in an inert helium or nitrogen environment (i.e. for normal conditions), the RBMK SNF cladding maximum temperatures should not exceed 300 C (Kalinkin et al., 2010) or 350 C (Vatulin et al., 2003). A cask’s thermal regime is determined by the decay heat release from the stored SNF, the cask construction, and the storage conditions. Nuclear fuel with enrichment of 2–2.8%, with and without erbium absorber, was used at the INPP. Radiological characteristics and decay heat of the fuel used at the INPP were analyzed in detail in Šmaizˇys et al. (2014). The most significant changes of the decay heat release occur during the first five years while the fuel is stored in the water pools. During the subsequent storage period, the release of decay heat monotonically decreases. The previous study (Poškas et al., 2006) presented the thermal modeling results of CASTOR RBMK-1500 and CONSTOR RBMK- 1500 casks in the stage of the interim storage for up to 50 years using the numerical modeling code ALGOR (USA). Characteristic temperatures of the casks at different storage conditions (a single cask or a cask in a storage facility just loaded with SNF but pre-stored for not less than 5 years in water pools, or after 50 years of storage, in summer/winter conditions, with/without assessment of solar insolation) were presented. Other codes and approaches have also been used for thermal analysis of the casks. In Lee et al. (2009), the code FLUENT (USA) was applied for the analysis of the casks with SNF from pressurized water reactors (PWR). In Alyokhina et al. (2015), a Computational Fluid Dynamics model developed by the authors was used for the analysis of the containers with SNF from reactors WWER-1000. Comparison of different methods for assessment of maximum cladding temperature was presented in Kim et al. (2014). This study presents a thermal assessment of CASTOR casks for long-term – up to 300 years – storage of RBMK-1500 SNF at the INPP using the numerical modeling code ALGOR. Also, the parameters that mostly influence the temperature distribution are selected, and a local sensitivity analysis is performed.
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کلمات کلیدی:
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