Search for dissertations about: "Severe accident management"

Showing result 1 - 5 of 10 swedish dissertations containing the words Severe accident management.

2. 1. Mobilization and Management of Tellurium in Severe Accident Scenarios

   Author : Anna-Elina Pasi; Chalmers tekniska högskola; []
   Keywords : TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; NATURVETENSKAP; NATURAL SCIENCES; nuclear; gamma irradiation; source term; severe accident; tellurium;

   Abstract : Safety is one of the highest priorities in any industry. In the nuclear industry, safety is in the essence since in case of a nuclear accident, the consequences can be long-lasting, hazardous, and devastating to the public, environment, and the industry. READ MORE

4. 2. Development of Risk Oriented Accident Analysis Methodology for Assessment of Effectiveness of Severe Accident Management Strategy in Nordic BWR

   Author : Sergey Galushin; Pavel Kudinov; Harri Tuomisto; KTH; []
   Keywords : Severe accident management; sensitivity; uncertainty; MELCOR; ROAAM; Svår haverihantering; känslighet och osäkerhetsanalys; MELCOR; ROAAM; Fysik; Physics;

   Abstract : Nordic Boiling Water Reactor (BWR) design employs ex-vessel debris coolability as a severe accident management strategy (SAM). In case of a severe accident, the debris ejected from the vessel are expected to fragment, quench and form a debris bed, which is coolable by a natural circulation of water. READ MORE

5. 3. Informing Severe Accident Management Guidelines for a Pressurized Water Reactor with MELCOR Simulations

   Author : Nan Zhao; Sevostian Bechta; Jinho Song; KTH; []
   Keywords : TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; Severe accident management guidelines SAMG ; SAMG verification validation; numerical simulation; SAMG entry condition; SAMG actions; primary-side bleed feed.; Kärnenergiteknik; Nuclear Engineering;

   Abstract : Severe accident management guidelines (SAMGs) play an important role in the hierarchical structure of the defense-in-depth (DiD) principle of reactor safety. Among different methods to verify and validate the effectiveness of SAMG on mitigating severe accident consequences, the approach of numerical simulations using best-estimate computer codes was extensively applied to evaluate the SAMG and SAM actions. READ MORE

6. 4. Development, validation and application of an effective convectivity model for simulation of melt pool heat transfer in a light water reactor lower head

   Author : Chi Thanh Tran; Truc-Nam Dinh; Florian Fichot; KTH; []
   Keywords : NATURVETENSKAP; NATURAL SCIENCES; light water reactor; hypothetical severe accident; accident progression; accident scenario; core melt pool; heat transfer; turbulent natural convection; heat transfer coefficient; phase change; mushy zone; crust; lower plenum; analytical model; effective convectivity model; CFD simulation.; Other physics; Övrig fysik;

   Abstract : Severe accidents in a Light Water Reactor (LWR) have been a subject of the research for the last three decades. The research in this area aims to further understanding of the inherent physical phenomena and reduce the uncertainties surrounding their quantification, with the ultimate goal of developing models that can be applied to safety analysis of nuclear reactors. READ MORE

7. 5. The Effective Convectivity Model for Simulation and Analysis of Melt Pool Heat Transfer in a Light Water Reactor Pressure Vessel Lower Head

   Author : Chi Thanh Tran; Tomas Lefvert; Harri Tuomisto; KTH; []
   Keywords : TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; light water reactor; hypothetical severe accident; accident progression; accident scenario; core melt pool; heat transfer; turbulent natural convection; heat transfer coefficient; phase change; mushy zone; crust; lower plenum; analytical model; effective convectivity model; CFD simulation; Thermal energy engineering; Termisk energiteknik;

   Abstract : Severe accidents in a Light Water Reactor (LWR) have been a subject of intense research for the last three decades. The research in this area aims to reach understanding of the inherent physical phenomena and reduce the uncertainties in their quantification, with the ultimate goal of developing models that can be applied to safety analysis of nuclear reactors, and to evaluation of the proposed accident management schemes for mitigating the consequences of severe accidents. READ MORE