Search for dissertations about: "MCNP code"
Showing result 1 - 5 of 7 swedish dissertations containing the words MCNP code.
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1. Studies of Accelerator-Driven Systems for Transmutation of Nuclear Waste
Abstract : Accelerator-driven systems for transmutation of nuclear waste have been suggested as a means for dealing with spent fuel components that pose potential radiological hazard for long periods of time. While not entirely removing the need for underground waste repositories, this nuclear waste incineration technology provides a viable method for reducing both waste volumes and storage times. READ MORE
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2. High-sensitivity Radioactive Xenon Monitoring and High-accuracy Neutron-proton Scattering Measurements
Abstract : Two aspects of applied nuclear physics have been studied in this thesis; Monte Carlo simulations for high-sensitivity monitoring of radioactive xenon and high-accuracy neutron-proton scattering measurements for neutron physics applications and fundamental physics. The Monte Carlo simulations have been performed for two systems for detection of radioactive xenon, using the MCNP code. READ MORE
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3. Novel Diagnostics and Computational Methods of Neutron Fluxes in Boiling Water Reactors
Abstract : The focus in this thesis is to improve knowledge of the BWR related uncertainties void, channel bow, and control rods. The presence of void determines the moderation of neutrons in BWRs. A high void fraction is less efficient in moderating neutrons than a low one. READ MORE
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4. Transmutation of Americium in Fast Neutron Facilities
Abstract : 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. READ MORE
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5. Segmented HPGe detectors for post-irradiation examination of nuclear fuel : Design and demonstration in gamma emission tomography
Abstract : Gamma emission tomography (GET) is a proven non-invasive technique for post-irradiation examination of nuclear fuel. In the past, collimated HPGe detectors were used for GET measurements due to their good energy resolution. READ MORE