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Application of Next-Generation Sensor Systems in HTRsJohnson, Matthew Paul 03 October 2013 (has links)
Accurate knowledge of the neutron flux distribution in a nuclear reactor has many tangible benefits. Perhaps the most important are the contributions to reactor safety. Detailed knowledge allows reactor operators to identify off-normal conditions quickly before they cause serious complications. Furthermore, reactor safety margins can be accurately quantified. As advanced reactor types are proposed, new sensor systems should be developed together with new algorithms for neutron flux reconstruction. This thesis develops neutron flux reconstruction methods for in-core sensors placed in HTRs. Sensor systems developed for current generation reactors cannot be used in HTRs. The high temperatures inside HTRs preclude the use of existing in-core sensors, and complex flux phenomena arising from the inner reflector and three-dimensional fuel block arrangements suggest that new flux reconstruction methods should be developed as well. Computer simulations were run to generate detailed in- core neutron flux distributions representative of HTRs. Next, this data was used to test two different flux reconstruction algorithms. It was found that the reconstruction algorithm based on the proper orthogonal decomposition performed better than the algorithm based on linear interpolation.
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Fabrication of tissue equivalent proportional counters, single- and multi-wire types, and their use in 14 MeV neutron dosimetry.January 1983 (has links)
by Chan Yiu Nam. / Chinese title: / Includes bibliographical references / Thesis (M.Phil.) -- Chinese University of Hong Kong, 1983
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Coarse mesh transport theory model for heterogeneous systemsIlas, Danut 05 1900 (has links)
No description available.
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Determination of thermal neutron flux spectra using the neutron balance equationAdams, Marvin L. January 1984 (has links)
Thesis (M.S.)--University of Michigan, 1984.
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The design of the University of Michigan subcritical nuclear reactor assembly a dissertation submitted in partial fulfillment ... for the degree of Master of Science in Engineering ... /Gyorey, Geza Leslie. Young, Po-shien. January 1957 (has links)
Thesis (M.S.)--University of Michigan, 1957. / Included in back pocket: Physics analysis of the subcritical reactor Model 9000/ by Poh-shien Young.
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A preliminary investigation on 3 Mev. Van de Graaff photoneutron spectra thesis : for the partial fulfillment of the degree of Master of Science in the Institute of Nuclear Science, Tsing Hua University ... /Ma, Pu-Yuan. Pai, Hsiang-Lin. Wang, Shin-Chen. Lee, Wellington S. Chien, Ji-Peng. January 1960 (has links)
Thesis (M.S.)--Tsing Hua University, 1960. / Research done at the University of Michigan.
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Characterization of the neutron flux spectrum at the Missouri University of Science and Technology Research ReactorKulage, Zachary Andrew. January 2010 (has links) (PDF)
Thesis (M.S.)--Missouri University of Science and Technology, 2010. / Vita. The entire thesis text is included in file. Title from title screen of thesis/dissertation PDF file (viewed April 7, 2010) Includes bibliographical references (p. 41-42).
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Neutronics analysis of a modified Pebble Bed Advanced High Temperature ReactorAbejón Orzáez, Jorge, January 2009 (has links)
Thesis (M.S.)--Ohio State University, 2009. / Title from first page of PDF file. Includes vita. Includes bibliographical references (p. 133-134).
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Determinacao dos parametros intermediarios de ressonancia no formalismo de multigrupo de energiaSANCHEZ, ANDREA 09 October 2014 (has links)
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03990.pdf: 5973232 bytes, checksum: 495568a9f1caded1dd992b8a431d36d3 (MD5) / Dissertacao (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
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The Fn method applied to multigroup transport theory in plane geometryMARTINEZ GARCIA, ROBERTO D. 09 October 2014 (has links)
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01485.pdf: 2055071 bytes, checksum: d7a431e820f8793828ac54edaacbd1d2 (MD5) / Tese (Doutoramento) / IPEN/T / Univ. North Carolina State
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