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A thermal-hydraulic analysis of the cooling system for the 500 KW Virginia Polytechnic Institute and State University reactorLo, Ai-Tai January 1982 (has links)
In order to increase the usefulness of the nuclear research reactor, it is necessary to enhance the neutron fluxes available in the experimental facilities. One method of attaining this objective is to increase the power level of the reactor.
The VPI&SU 100 KW research reactor has been studied to investigate the feasibility of operation of 500 KW. From a thermal-hydraulic point of view, the following limiting conditions should not be exceeded for a 500 KW operation:
1) bulk boiling of the coolant should not occur,
2) surface boiling should not occur on any fuel plate,
3) fuel meltdown must not occur after a loss-of-flow or loss-of-coolant accident,
4) fuel plate vibration problems should not be significant.
The results of the investigation indicate that the above limiting conditions will not be exceeded provided that certain system modifications are made. Thus the operation of the VPI&SU reactor at 500 KW is feasible as far as thermal-hydraulics is concerned. / Master of Science
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SPATIAL BEHAVIOR OF THE REACTIVITY EFFECT OF LOCAL PERTURBATIONS IN THE UNIVERSITY OF ARIZONA TRIGA REACTOR.Khalil, Abdulkarim Mohamed. January 1982 (has links)
No description available.
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Flooding limits in a simulated nuclear reactor hot legKrolewski, Susan M January 1980 (has links)
Thesis (B.S.)--Massachusetts Institute of Technology, Dept. of Mechanical Engineering, 1980. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND ENGINEERING. / Bibliography: leaf 31. / by Susan M. Krolewski. / B.S.
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Time-dependent continuous-energy solutions in neutron transport theory for plane and spherical infinite mediaRoybal, Jerry Anthony January 1981 (has links)
No description available.
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THE STABILITY OF COUPLED-CORE NUCLEAR REACTOR SYSTEMS BY THE SECOND METHOD OF LIAPUNOVMurray, Hugh Sutherland, 1939- January 1965 (has links)
No description available.
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A health risk assessment for the decommissioning of the Georgia Institute of Technology Research reactorKiellman, Tracy Jo 12 1900 (has links)
No description available.
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An Improved Fission Product Pressure Model for Use in the Venus-II Disassembly CodeJensen, Ray Leland 01 April 1976 (has links)
The world's growing need for safe, reliable, and long-term energy sources has intensified the research being conducted in the development of nuclear power. The operation of power reactors is contingent upon the continued availability of the fissile material required to maintain a critic a l reactor. The only naturally occuring fissile material is an isotope of uranium, U-235, which only accounts for 0.76 percent of the uranium that is mined. Due to the relative scarcity of this important fissile material it is estimated the United States' sources of economically recoverable fissile material will be delinquished with in about twenty-five years.^1
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The spherical harmonics method for critical spheresCallen, James Donald. January 1964 (has links)
Call number: LD2668 .T4 1964 C15 / Master of Science
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INFLUENCE OF SOURCE STRENGTH ON THE CRITICAL BEHAVIOR OF URANYL NITRATE SOLUTIONS.Dulco, Gerald Bruce. January 1982 (has links)
No description available.
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SYMBOLIC MANIPULATION IN REACTOR PHYSICS.Sadeghi, Mohammad Mehdi, 1959- January 1986 (has links)
No description available.
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