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Tensoes termicas no vaso de pressao de um reator a agua pressurizada (PWR)BASSEL, WAGEEH S. 09 October 2014 (has links)
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Simulacao do modelo termodinamico de pressurizador tipico de PWR em regime transiente por meio do programa CSMPWOISKI, EMANUEL R. 09 October 2014 (has links)
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Estudo de acidente de perda de refrigerante por grande ruptura na usina nuclear Angra-1BORGES, EDUARDO M. 09 October 2014 (has links)
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Analise termo-hidraulica e neutronica de reatores a agua pressurizada (PWR)ALVES, CARLOS H. 09 October 2014 (has links)
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Tensoes termicas no vaso de pressao de um reator a agua pressurizada (PWR)BASSEL, WAGEEH S. 09 October 2014 (has links)
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Optimization of the axial power shape in pressurized water reactorsMelik, M. A January 1982 (has links)
Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1982. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE / Bibliography: leaves 112-114. / by Mushtaq Ahmad Malik. / M.S.
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The effect of axial power shaping on ore utilization in pressurized water reactorsKamal, Altamash January 1980 (has links)
Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1980. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE. / Bibliography: leaves 160-162. / by Altamash Kamal. / M.S.
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Set-theoretic control of a pressurized water nuclear power plantChenini, Abdelhamid January 1980 (has links)
Thesis (Nucl.E)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1980. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE. / Includes bibliographical references. / by Abdelhamid Chenini. / Nucl.E
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High pressure counterflow CHF.Walkush, Joseph Patrick January 1975 (has links)
Thesis. 1975. M.S.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering. / Includes bibliographical references. / This is a report of the experimental results of a program in countercurrent flow critical heat flux. These experiments were performed with Freon 113 at 200 psia in order to model a high pressure water system. An internally heated annulus was used to model a fuel pin in a channel. Only low flowrates were examined. The flow regime was always bubbly or slug, with the liquid primarily on the walls. It was found that critical heat flux of about .9 of the pool boiling value can be expected for up to 20% void. Beyond this, the CHF value decreases uniformly with void. Void fractions up to 70% were investigated, with the results being slightly conservative compared to a similar experiment carried out at atmospheric pressure by Avedisian. / M.S.
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Thermal/hydraulic analysis methods for PWR'sMoreno Palacios, Pablo January 1976 (has links)
Thesis. 1976. Nucl.E.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering. / Microfiche copy available in Archives and Science. / Includes bibliographical references. / by Pablo Moreno. / Nucl.E.
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