The neutron Electric Dipole Moment Experiment at the Spallation Neutron Source requires an overall magnetic shielding factor of order 105 to attenuate external background magnetic fields. At present, the shielding design includes an external (room-temperature) multi-layer μ-metal magnetic shield, a cryogenic (4 Kelvin) Pb superconducting shield, and a cryogenic (4 Kelvin) ferromagnetic shield composed of Metglas ribbon. This research determined how to construct a Metglas shield using minimal material that produced axial and transverse shielding factors of ~267 and ~1500. In addition, the μ-metal and Metglas shields were modeled using finite element analysis. The FEA model includes external coils and their effect on the residual magnetic fields. This study will help with the design of the shielding.

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Beyond the protective confines of Earth's atmosphere and magnetosphere, spacecraft are subject to constant bombardment by high-energy charged particles originating from our Sun in the form of Solar Particle Events (SPEs), and from outside the solar system in the form of Galactic Cosmic Rays (GCRs). The harm these particles do can be reduced or mitigated outright through radiation shielding. Because protons and other charged particles comprise most of these radiation particles, strong magnetic fields could be generated around spacecraft to deflect incoming charged radiation particles. This thesis investigates the performance of specific configurations of toroidal superconducting solenoids to generate magnetic fields that deflect incoming energetic protons via the Lorentz force. Bulk material shielding configurations using various thicknesses of liquid water are similarly investigated, as are combination shielding configurations combining the best-performing toroidal shielding configurations with a small bulk material shield surrounding the spacecraft. The water shielding configurations tested included shields of uniform thicknesses from 1 cm to 10 cm surrounding an Apollo CSM-sized cylindrical candidate spacecraft. Water shielding was found to be very effective at reducing the SPE dose, from a 86\% reduction at 1 cm of water to a 94\% reduction at 10 cm. However water shielding was found to be minimally effective against the much higher energy Galactic Cosmic Ray protons, with no dose reduction at 1 cm and a paltry 1\% reduction at 10 cm. The toroidal shielding geometric configurations tested consisted of either 5 or 10 primary toroidal shields surrounding the candidate spacecraft, as was the addition of smaller nested toroidal shields inside the primary toroids and of toroids on the spacecraft's endcaps. The magnetic field strengths tested were 1.7 Tesla, 8.5 Tesla, and 17 Tesla. The best geometric configurations of electrodynamic shielding consisted of 5 primary toroidal shields, 5 total nested shields placed inside the primary toroids, and 2 total shields on the spacecraft's endcaps. The second best geometric configuration consisted of 10 primary toroidal shields plus two total endcap shields. These configurations at 1.7 Tesla reduced the SPE dose by 87\% and 87\%, and reduced the GCR dose by 11\% and 10\%. At 17 Tesla, these configurations both reduced the SPE dose by 90\%, and reduced the GCR dose by 76\% and 61\%. Combining these two configurations with a 1 cm-thick shield of water improved performance against SPE protons to 95\% and 93\% at 1.7 Tesla, and a 97\% and 96\% reduction at 17 Tesla. GCR dose reductions decreased slightly. Passive material shielding was found capable of providing substantial protection against SPE protons, but was minimally effective against GCR protons without very thick shielding. Electrodynamic shielding, at magnetic field strengths of 1.7 Tesla, was found to be similarly effective against SPE protons, and marginally more effective against GCR protons. Combining the best toroidal shielding configurations, at magnetic field strengths of 1.7 Tesla, with water shielding yielded high protection against SPE protons, but still marginal protection against GCR protons. Increasing the magnetic field strength to 17 Tesla was found to provide very high protection against SPE protons, and to significantly reduce the radiation dose from GCR protons. Of all shielding configurations tested, only those electrodynamic configurations with magnetic fields of 17 Tesla were able to reduce the GCR dose by more than half.

Denna rapport utreder skärmning som en metod för att minska störningsupptaget hos en blodperfusionsmätare, och därmed öka dess pålitlighet vid medicinsk användning. Ett nytt kretskort för den analoga elektroniken skapades för att underlätta skärmningen, och samtidigt analyserades kretsens karakteristik och anpassades efter behov. Beräkningar och simuleringar utfördes för att undersöka kretskortets teoretiska störningspåverkan, och jämförelser mellan ett skärmat och ett oskärmat kort visar att skärmning gör att kretskortet tar upp markant mindre störningar. Praktiska tester planerades men utfördes inte eftersom COVID-19-epidemin orsakade tidsbrist. / This report examines shielding as a method to reduce interference absorption in a blood perfusion monitor, and consequently increase its reliability in clinical use. A new circuit board for the analog electronics was created to facilitate shielding, and simultaneously the circuit’s charac­teristics were analyzed and adjusted where necessary. Calculations and simulations were made to examine the circuit board’s theoretical interference impact, and com­parisons between a shielded and an unshielded board shows that shielding causes the circuit board to absorb noticeably less interference. Practical tests were prepared but not per­formed because the COVID-19 epidemic caused lack of time.

No description available.

Call number: LD2668 .T4 1963 B34 / Master of Science

Call number: LD2668 .T4 1985 T476 / Master of Science

Transport of low energy neutrons associated with the galactic cosmic ray cascade is analyzed in this dissertation. A benchmark quality analytical algorithm is demonstrated for use with B scRYNTRN, a computer program written by the High Energy Physics Division of N scASA Langley Research Center, which is used to design and analyze shielding against the radiation created by the cascade. B scRYNTRN uses numerical methods to solve the integral transport equations for baryons with the straight-ahead approximation, and numerical and empirical methods to generate the interaction probabilities. The straight-ahead approximation is adequate for charged particles, but not for neutrons. As N scASA Langley improves B scRYNTRN to include low energy neutrons, a benchmark quality solution is needed for comparison. The neutron transport algorithm demonstrated in this dissertation uses the closed-form Green's function solution to the galactic cosmic ray cascade transport equations to generate a source of neutrons. A basis function expansion for finite heterogeneous and semi-infinite homogeneous slabs with multiple energy groups and isotropic scattering is used to generate neutron fluxes resulting from the cascade. This method, called the F(N) method, is used to solve the neutral particle linear Boltzmann transport equation. As a demonstration of the algorithm coded in the programs M scGSLAB and M scGSEMI, neutron and ion fluxes are shown for a beam of fluorine ions at 1000 MeV per nucleon incident on semi-infinite and finite aluminum slabs. Also, to demonstrate that the shielding effectiveness against the radiation from the galactic cosmic ray cascade is not directly proportional to shield thickness, a graph of transmitted total neutron scalar flux versus slab thickness is shown. A simple model based on the nuclear liquid drop assumption is used to generate cross sections for the galactic cosmic ray cascade. The E scNDF/B V database is used to generate the total and scattering cross sections for neutrons in aluminum. As an external verification, the results from M scGSLAB and M scGSEMI were compared to A scNISN/P scC, a routinely used neutron transport code, showing excellent agreement. In an application to an aluminum shield, the F(N) method seems to generate reasonable results.

O transporte de materiais radioativos deve ser realizado em embalados capazes de suportar tanto condições normais, quanto acidentais de transporte. O objetivo deste trabalho foi a seleção de materiais que possam viabilizar a fabricação de um embalado para o transporte de substâncias que sejam fontes de alta radioatividade, em especial o Mo-99, cujo produto do decaimento radioativo é o Tc-99m, utilizado para fins diagnósticos na medicina nuclear. Para tanto, foi realizada a seleção dos possíveis materiais que podem ser utilizados para a fabricação de um embalado, com o auxílio do programa CES EduPack e a metodologia desenvolvida por Ashby. O programa ESTAR foi utilizado para verificar a ocorrência de radiação de freamento e o programa XCOM para o cálculo do coeficiente de atenuação da radiação gama de alguns dos materiais selecionados para compor a blindagem do embalado. Posteriormente, a espessura necessária para a blindagem da radiação foi calculada. A partir dos resultados obtidos, os materiais selecionados como candidatos potenciais para a fabricação da blindagem foram as ligas de tungstênio. Com relação à parte do embalado que oferece isolamento térmico e proteção ao impacto, destacam-se as madeiras, os aglomerados e os compensados. No que concerne ao revestimento interno e externo, os materiais selecionados se concentram nos aços. / The transport of radioactive materials must be done in packages able to withstand both normal and accidental conditions of transport. The aim of this work was the material selection that can enable the manufacture of a package for the transport of substances which are of high radioactivity sources, especially Mo-99, whose radioactive decay product is Tc-99m, used for diagnosis purposes in nuclear medicine. For this, the selection of possible materials that can be used for the manufacture of the main parts of the package was performed with the aid of CES Edupack program and the methodology developed by Ashby. The ESTAR program was used to check occurrence of Bremsstrahlung and the XCOM program was used to calculate the attenuation coefficient of gamma radiation from some of the selected materials for the shield. After, the thickness needed for the radiation shielding was calculated. From the results, the materials selected as potential candidates for the manufacture of the shielding was the tungsten alloys. Related to the thermal insulation and the impact protection, woods, plywoods and particleboards stand out. With regard to internal and external recipients, the selected materials focus on steels.