Pathfinder Atomic Power Plant Technical Progress Report For
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Pathfinder Atomic Power Plant Technical Progress Report For October 1958 December 1958
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Author :
language : en
Publisher:
Release Date : 1959
Pathfinder Atomic Power Plant Technical Progress Report For October 1958 December 1958 written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1959 with Nuclear power plants categories.
Dynamic and static high-temperature water corrosion tests are reported for Al alloys such as X800l + Mg and 198X, Data are presented for one dynamic comparison test for these two alloys at pH 5.5 with H/sub 3/PO/sub 4/. End closures of type 3003(Al--1.2% Mn) and X8001(Al--1% Ni) made by spinning were pressure leak tested and examined microscopically. Results are tabulated, and photomicrographs are included. All tubes that were spun but not welded had cracks, however, the fusion welded tubes were more sound. Progress in design activities related to reactor mechanical features is reported, including an analysis of boiler pressure drop and void distribution, and the recirculation system piping. Data on forces and moments due to thermal expansion in the loops under four conditions of support; and flow restraint at the pump are tabulated. Test information and conclusions on the design of control rods and guide tubes are given. An analysis of individual constituents of reactivity coefficients was conducted with the emphasis on nuclear parameters such as the thermal neutron spectrum, thermal disadvantage factors, resonance escape probability, fast fission factor, and epithermal neutron age. The reactivity changes produced by variations in these parameters are tabulated. Data are also given on the isoflux line patterns in the 64 rod core section obtained from calculations of flux and power distribution effects at the superheater boiler core interface. Control rod heating due to radiation was calculated as 1.22 x 10/sup 6/BTU/ft/sup 3/-hr. Shielding design based on calculated activity buildup due mainly to crud is described, and one possible arrangement is considered in relation to the neutron and gamma flux. Reactor water purification design modification includes the addition of a booster pump under the flash tank to be used during reactor shut- down. Descriptiona of control rod programming and circuits are presented, and a list of abnormal conditions to be considered in the design of a safety alarm system is given. Procedures for obtaining power and period measurements are given as well as the design of a steam pressure control device and a water level control and measurement system. Other instrument design work is reported on shut- down pump controls, leak and rupture detection, various emergency valves, flash tank controls, water pressure controller, resin protection controls, and various hand operated valves. Feasibility studies on fuel element design, fuel materials such as UO/sub 2/--stainless steel cermets, thermal expansion tests, air flow tests for superheater fiow characteristics, and a cooling test are reported. Drawings and photographs related to materials and designs are included. (For preceding period see AECU-3910)
Pathfinder Atomic Power Plant Technical Progress Report April 1 1959 June 30 1959
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Author :
language : en
Publisher:
Release Date : 1959
Pathfinder Atomic Power Plant Technical Progress Report April 1 1959 June 30 1959 written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1959 with Nuclear power plants categories.
Annealing, corrosion, and irradiation testing of aluminum base double alloy fuel elements were conducted. Interdiffusion anneals at 500 deg F for periods up to 83 days were accomplished. Heat transfer and fluid flow studies of the heat transfer loop, boiler fuel elements, and the water moderator in the superheater region are discussed. Progress on fuel element fabrication is reported. Welding tests were conducted on the reactor vessel shell and the final design is presented. Progress on the fabrication, installation, and testing of recirculation pumps, steam separators, control rods, guide tubes, and control rod drives is reported. An analysis of control rod worths, core burn-up, boiling effects in superheater, and shielding of fuel handling building is given. A description of the reactor burn-up and decay code (BAD), which has been programmed for the IBM-704, is given. The filter test loop and the radioactive gas decontamination system are described. Instrumentation and control features of the plant are discussed. A plant safety analysis is given. (For preceding period see ACNP-5909)
Power Reactor Technology
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Author :
language : en
Publisher:
Release Date : 1957
Power Reactor Technology written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1957 with Nuclear engineering categories.
Tid
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Author :
language : en
Publisher:
Release Date : 1961
Tid written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1961 with Energy development categories.
Small Power Reactor Projects Of The United States Atomic Energy Commission
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Author :
language : en
Publisher:
Release Date : 1961
Small Power Reactor Projects Of The United States Atomic Energy Commission written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1961 with Nuclear reactors categories.
U S Government Research Reports
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Author :
language : en
Publisher:
Release Date : 1961
U S Government Research Reports written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1961 with Science categories.
Nuclear Superheat Meeting
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Author :
language : en
Publisher:
Release Date : 1961
Nuclear Superheat Meeting written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1961 with Boiling water reactors categories.
Civilian Power Reactor Program Addendum Core Parameter Studies For Selected Reactor Types
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Author : U.S. Atomic Energy Commission
language : en
Publisher:
Release Date : 1960
Civilian Power Reactor Program Addendum Core Parameter Studies For Selected Reactor Types written by U.S. Atomic Energy Commission and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1960 with Nuclear energy categories.
Reactor Safety
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Author :
language : en
Publisher:
Release Date : 1963
Reactor Safety written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1963 with Nuclear reactors categories.
Selected Reactors Of The Power Reactor Demonstration Program
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Author : James M. Jacobs
language : en
Publisher:
Release Date : 1962
Selected Reactors Of The Power Reactor Demonstration Program written by James M. Jacobs and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1962 with Nuclear reactors categories.