Sökning: "fast reactor fuel"

Visar resultat 1 - 5 av 43 avhandlingar innehållade orden fast reactor fuel.

1. 1. Visionen om outtömlig energi : Bridreaktorn i svensk kärnkraftshistoria 1945–80

   Författare :Maja Fjæstad; Thomas Kaiserfeld; Thomas Jonter; Henrik Björck; KTH; []
   Nyckelord :HUMANIORA; HUMANITIES; HUMANIORA; HUMANITIES; HUMANIORA; HUMANITIES; nuclear power; nuclear energy; nuclear power history; nuclear weapons; breeder reactor; fast reactor; AB Atomenergi; history; history of science; history of technology; environmental history; Sweden; 20th century; vision; technological vision; interpretative flexibility; kärnkraft; kärnkraftshistoria; kärnvapen; bridreaktorer; snabba reaktorer; AB Atomenergi; historia; vetenskapshistoria; teknikhistoria; miljöhistoria; Sverige; svensk historia; 1900-tal; vision; tekniska visioner; utopi; tolkningsflexibilitet; History of technology; Teknikhistoria; History of science and ideas; Idé- o lärdomshistoria; History of science; Vetenskapshistoria;

   Sammanfattning : The fast breeder is a type of nuclear reactor that aroused much attention in the 1950s and 60s. Its ability to produce more nuclear fuel than it consumes offered promises of cheap and reliable energy, and thereby connected it to utopian ideas about an eternal supply of energy. LÄS MER

3. 2. Modelling the system Cr-Fe-Ni-Te via the CALPHAD method, DFT and experiments : for fast nuclear reactor applications

   Författare :Carl-Magnus Arvhult; Malin Selleby; Jean-Marc Joubert; KTH; []
   Nyckelord :TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; Phase diagrams; Calphad; thermodynamics; microscopy; XRD; thermal analysis; phase transitions; nuclear materials; Teknisk materialvetenskap; Materials Science and Engineering;

   Sammanfattning : In the pursuit of safer, more environmentally friendly and sustainable forms of energy production for our ever growing demands, a type of nuclear reactor cooled by liquid metal instead of water is under development. Specific to this type of reactor are special forms of corrosion of the material that encapsulates the fuel pins in the reactor core, called Fuel-Clad Chemical Interaction (FCCI) or Fission Product-induced Liquid Metal Embrittlement (FPLME). LÄS MER

4. 3. Experimental and theoretical studies of nitride fuels

   Författare :Merja Pukari; Janne Wallenius; Toru Ogawa; KTH; []
   Nyckelord :NATURVETENSKAP; NATURAL SCIENCES; fast reactor fuel; ab-initio modelling; fuel fabrication; inert matrix nitride fuel;

   Sammanfattning : With respect to nitrides being considered as potential fast reactor fuels, research is conducted on the out-of-pile thermophysical properties, sintering and fabrication processes, gas migration mechanisms, self-diffusion and point defect behaviour of actinide nitrides, their surrogate materials, and the inert matrix material ZrN . The experimental research, carried out in the framework of qualifying fuel for the European Lead Cooled Training Reactor (ELECTRA), shows that sintered ZrN and (Dy,Zr)N pellet densities are influenced by the oxygen concentration in the material. LÄS MER

5. 4. Transmutation of Americium in Fast Neutron Facilities

   Författare :Youpeng Zhang; Janne Wallenius; Sandra Dulla; KTH; []
   Nyckelord :NATURVETENSKAP; NATURAL SCIENCES; americium; transmutation; fast reactor; Nuclear physics; Kärnfysik; TECHNOLOGY; TEKNIKVETENSKAP;

   Sammanfattning : In this thesis, the feasibility to use a medium sized sodium cooled fast reactor fully loaded with MOX fuel for efficient transmutation of americium is investigated by simulating the safety performance of a BN600-type fast reactor loaded with different fractions of americium in the fuel, using the safety parameters obtained with the SERPENT Monte Carlo code. The focus is on americium mainly due to its long-term contribution to the radiotoxicity of spent nuclear fuel and its deterioration on core's safety parameters. LÄS MER

7. 5. Neutron Emission Spectrometry for Fusion Reactor Diagnosis : Method Development and Data Analysis

   Författare :Jacob Eriksson; Göran Ericsson; Carl Hellesen; Sean Conroy; Andreas Dinklage; Uppsala universitet; []
   Nyckelord :NATURVETENSKAP; NATURAL SCIENCES; NATURVETENSKAP; NATURAL SCIENCES; fusion; plasma diagnostics; neutron spectrometry; TOFOR; MPRu; tokamak; JET; fast ions; fuel ion density; relativistic kinematics; Fysik med inriktning mot tillämpad kärnfysik; Physics with specialization in Applied Nuclear Physics;

   Sammanfattning : It is possible to obtain information about various properties of the fuel ions deuterium (D) and tritium (T) in a fusion plasma by measuring the neutron emission from the plasma. Neutrons are produced in fusion reactions between the fuel ions, which means that the intensity and energy spectrum of the emitted neutrons are related to the densities and velocity distributions of these ions. LÄS MER