Pathfinder Atomic Power Plant Technical Progress Report for July 1, 1959- September 30, 1959 PDF Download
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Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
ABS>Fuel Element Research and Development. Dynamic and static corrosion tests on 8001 Al were completed. Annealmmmg of 1100 cladding on 5083 and M400 cladding on X2219 were tested at 500 deg C, and investigation continued on producing X8101 Al alloy cladding in tube plates by extrusion. Boiler fuel element capsule irradiation tests and subassembly tests are described Heat transfer loop studies and fuel fabrication for the critical facility are reported. Boiler fuel element mechanical design and testing progress is desc ribed. and the superheater fuel element temperature evaluating routine is discussed. Low- enrichment superheater fuel element development included design studies and stainless steel powder and UO/sub 2/ powder fabrication studies Reactor Mechanical Studies. Research is reported on vessel and structure design, fabrication, and testing, recirculation system design, steam separator tests, and control rod studies. Nuclear Analysis. Reactor physics studies are reported on nuclear constants, baffle plate analysis, comparison of core representations, delayed neutron fraction. and shielding analysis of the reactor building. Reactor and system dynamics and critical experiments were also studied. Chemistry. Progress is reported on recombiner. radioactive gas removal and storage, ion exchanger and radiochemical processing. (For preceding period see ACNP-5915.) (T.R.H.).
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
ABS>Fuel Element Research and Development. Dynamic and static corrosion tests on 8001 Al were completed. Annealmmmg of 1100 cladding on 5083 and M400 cladding on X2219 were tested at 500 deg C, and investigation continued on producing X8101 Al alloy cladding in tube plates by extrusion. Boiler fuel element capsule irradiation tests and subassembly tests are described Heat transfer loop studies and fuel fabrication for the critical facility are reported. Boiler fuel element mechanical design and testing progress is desc ribed. and the superheater fuel element temperature evaluating routine is discussed. Low- enrichment superheater fuel element development included design studies and stainless steel powder and UO/sub 2/ powder fabrication studies Reactor Mechanical Studies. Research is reported on vessel and structure design, fabrication, and testing, recirculation system design, steam separator tests, and control rod studies. Nuclear Analysis. Reactor physics studies are reported on nuclear constants, baffle plate analysis, comparison of core representations, delayed neutron fraction. and shielding analysis of the reactor building. Reactor and system dynamics and critical experiments were also studied. Chemistry. Progress is reported on recombiner. radioactive gas removal and storage, ion exchanger and radiochemical processing. (For preceding period see ACNP-5915.) (T.R.H.).
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
Progress in the development of the Sioux Falls Power Reactor is reported. Information is presented on: design of underwater control-rod cutting facility; xenon transient studies; dynamic performance; pre-critical testing; roddrop calculations; and design of instrumented superheater fuel element assemblies. (N.W.R.).
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
Progress made in the development of the Sioux Falls Power Reactor is reported. Information is presented on stainless steel corrosion in oxygenated steam, development of low-enrichment superheater fuel elements, nuclear analysis of first-core boron-stainless steel poison shims and transient simulator, and testing and stability of oscillator rod assembly and in-core ion chambers. (N.W.R.).
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
Technical progress on the research and development program being performed in connection with the design of the Sioux Falls Power Reactor is reported. Areas covered in detail include fuel element research and development, reactor mechanical studies, nuclear analysis, chemistry, instrumentation and control, plant safety analysis, feasibility studies, and steam plant and reactor auxiliary systems design. (For preceding period see ACNP-5924.) (W.D.M.).
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
Technical progress is reported on research and development associated with the design of the Pathfinder atomic power plant. Preconstruction work is reported on fuel elements, reactor mechanical studies, and nuclear analysis. Other design work is reported on the oscillator control rod mechanism, a superheating calorimeter, and superheater thermocouple lead connectors. (J.R.D.).
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Author: U.S. Atomic Energy Commission
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Author: J. A. Smith
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