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Energy balance of biomass heating plant
Žmolík, Václav ; Šen, Hugo (referee) ; Baláš, Marek (advisor)
This thesis deals with a design of a biomass heating plant combinating a Rankin-Clausius cyklus and a CHP unit. The CHP unit fuel is a biogas and the boiler fuel is a wooden chip. The adapted CHP unit regenerates feed-water of the R-C cycles. This design is technicaly and economicalty compared with the Rankin-Clausius cycle without feed-water regeneration by the CHP unit.
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The design of components for emergency cooling of reactor pressure vessel
Katzer, Milan ; Šen, Hugo (referee) ; Martinec, Jiří (advisor)
My thesis deals with the design of an experimental emergency cooling device of the reactor pressure vessel (RPV). It consists of two parts, the theoretical one and practical one. Different molten corium cooling methods in terms of their efficiency and comparison are introduced in the theoretical part. The design of an experimental emergency cooling device, which incorporates a model channel past the reactor pressure vessel , is presented in the practical part. The cooling device consists of a model channel past the reactor pressure vessel, condensator, which takes away the heat generated by the reactor pressure vessel and the pump of a secondary loop. Next, thermal and hydraulic calculations are given in this section. The conclusion is devoted to the evaluation of particular cooling technologies and their comparison in terms of nuclear and technical safety.
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Spent fuel storage casks thermal and physical properties investigation
Hlatký, Pavel ; Martinec, Jiří (referee) ; Šen, Hugo (advisor)
This work deals with questions of spent fuel storage casks thermal and physical properties investigation. Foundations of mathematics which are necessary for describing field of temperature are included. The work itself contains calculation methods which are split into two parts. The first one deals with simplified analytic solution and the second part solves the whole problem by the numerical computation.
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The Intermediate Heat Exchanger for ESFR reactor primary circuit
Švihel, Miroslav ; Baláš, Marek (referee) ; Šen, Hugo (advisor)
The thesis is mainly focused on the design of the intermediate heat exchanger primary circuit of the reactor ESFR. Heat exchanger is calculated heat, hydraulic and strength and is finally processed part drawings. There are designed the basic dimensions of the tube bundle and container heat exchanger. There are included an overview of concepts and so far used types IHX at the nuclear power plants with fast reactors. There are also mentioned basic parameters of the project ESFR and evaluated the safety and operational reliability of the heat exchanger.
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Inspection authorities of nuclear safety in the world and their purpose
Dvořák, Aleš ; Nerud, Pavel (referee) ; Šen, Hugo (advisor)
This thesis deals with issues of nuclear safety. The first section provides an overview of international organizations and associations, which control via their activities all regulations concerning nuclear safety, the technical state of equipments and systems in nuclear power plants. The second part deals with technical description of important equipment and systems of the nuclear powerplants at chosen nuclear reactors of II. and III. generation. The last part explains the conception of nuclear safety deeply. The reader can gain a deep overview of the different levels of protection and attention is also paid to the methods that contribute to the evaluation of nuclear safety.
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Ways of radioactive materials saving in the Czech Republic and in the world
Polák, Luboš ; Šen, Hugo (referee) ; Nerud, Pavel (advisor)
Management of spent nuclear fuel and radioactive waste are many. The aim of this thesis was to summarize the attitude of the Czech Republic and the other major countries on this issue. First is given the classification of radioactive waste according to various criteria. Consequently, it is defined and described the fuel cycle, as the largest producer of all types of radioactive waste. Then is analyzed approach of the Czech Republic to the management of all type radioactive waste and the attitude to deep geological repository. At the end are some, in this respect, major countries and their attitude to deal with spent nuclear fuel, radioactive waste and the method of final disposal.
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Trasfer Heat Analysis in Steam Generators in blocks of VVER 440
Roupec, Petr ; Pulec, Jiří (referee) ; Šen, Hugo (advisor)
The aim of this thesis is to analyze the heat transfer in steam generator of blocks in the nuclear power plant VVER 440. The steam generator represents the border between the primary and the secondary circuit. The heat is carried from a warm water from reactor to a cold water. The steam arises after the heat transfer and drives the steam turbine. An important quantity which represents the heat transfer is a heat transfer factor. This thesis is divided into theoretical and a practical part. In the theoretical part is mentioned a principle of the steam generator and the theoretical calculation of the heat transfer factor, which comes first of all from the character of the streaming in the steam generator. The practical part brings a comparison of the heat transfer factor calculated from data measured after the start of the third block of EDU in 1986, with the heat transfer factor which comes from the measurement after the power-increase for 105 % of nominal power of the same block in 2009. Further is shown the prediction of the heat transfer factor for next power-increase and the following service is shown too.
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Fuel of nuclear reactors and fuel cycle
Bátěk, David ; Nerud, Pavel (referee) ; Šen, Hugo (advisor)
This bachelor thesis describes nuclear fuels used in today's nuclear reactors as well as parts of fuel cycle, which includes all activities like uranium mining and prepairing, energy utilization and storage at the end of a cycle. There are also information about world production of uranium and posibilities of manipulation with used nuclear fuel, including transmutation technologies.
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Design of the steam generator for modular reactor
Černý, Marian ; Baláš, Marek (referee) ; Šen, Hugo (advisor)
Subject of this thesis is design of the steam generator for modular reactor. The dissertation consist of the theoretical part, where are described heat-exchangers and steam generators used in nuclear power plants. Second part contains theoretical calculations in the first approach (thermal, hydraulic and strenght calculation). In the next part are particular variants of steam generator selected. For the final variant are necessary calculations (introduced above) and drawings of selected parts are done. In the final statement is technical solution evaluated, and the parameters of the steam generator are compared with actually used steam generators.
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Improving of reliability for NPP
Dubovský, Dávid ; Šen, Hugo (referee) ; Nerud, Pavel (advisor)
The aim of this paper is to describe and evaluate the reliability of nuclear plants at Bohunice (EBO). Then illuminate the methods for increasing the reliability and specify one of them (INPO AP 913). After describing the methods, summarize the work results of this method and proposes the way of application.
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