Download or read book PRESSURIZED WATER REACTOR PROGRAM TECHNICAL PROGRESS REPORT FOR THE PERIOD MAY 5 1955 TO JUNE 16 1955 written by and published by . This book was released on 1958 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The current PWR plant and core parameters are listed. Resign requirements are briefly summarized for a radiation monitoring system, a fuel handling water system, a coolant purification system, an electrical power distribution system, and component shielding. Results of studies on thermal bowing and stressing of UO2 are reported. A graph is presented of reactor power vs. reactor flow for various hot channel conditions. Development of U-- Mo and U-Nb alloys has been stopped because of the recent selection of UO2 fuel material for the PWR core and blanket. The fabrication characteristics of UO2 powders are being studied. Seamless Zircaloy-2 tubing has been tested to determine elastic limits, bursting pressures, and corrosion resistance. Fabrication techniques and tests for corrosion and defects in Zircaloy-clad U-Mo and UO2 fuel rods are described. The preparation of UO2 by various methods is being studied to determine which method produces a material most suitable for PWR fuel elements. The stability of UO2 compacts in high temperature water and steam is being determined. Surface area and density measurements have been performed on samples of UO2 powder prepared by various methods. Revelopment work on U-- Mo and U--Nb alloys has included studies of the effect on corrosion behavior of additions to the test water, additions to the alloys, homogenization of the alloys, annealing times, cladding, and fabrication techniques. Data are presented on relaxation in spring materials after exposure to a corrosive environment. Results are reported from loop and autoclave tests on fission product and crud deposition. Results of irradiation and corrosion testing of clad and unclad U--Mo and U-Nh alloys are described. The UO2 irradiation program has included studies of dimensional changes, release of fission gases, and activity in the water surrounding the samples. A review of the methods of calculating reactor physics parameters has been completed, and the established procedures have been applied to determination of PWR reference design parameters. Critical experiments and primary loop shielding analyses are described. (D.E.B.).

Download or read book Pressurized Water Reactors written by and published by . This book was released on 1959 with total page 64 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Civilian Power Reactor Program Addendum Core parameter studies for selected reactor types written by and published by . This book was released on 1960 with total page 512 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book PRESSURIZED WATER REACTOR PROGRAM TECHNICAL PROGRESS REPORT FOR THE PERIOD JUNE 17 1955 TO JULY 28 1955 written by and published by . This book was released on 2005 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A contract was awarded for the fabrication of the PWR pressurizing tank. The vessel is designed for 2600 psia, with dimensions of ahout 18 ft x 66 in. Tests were conducted on the feasibility of using a magnetic brake for holding a control rod in position when power to the motor is shut off. Fuel rod dimensions and tolerances are given. A longitudinal section drawing through the reactor is presented. Recent UNIVAC results indicate the effect of cladding clearances on the reference blanket fuel red will require further design modifications. A system for detecting fuel element failure by gamma radiation instrumentation is being tested. Further tests were made on fuel rod fabrication techniques, including the welding of end closures and in-pile radiation testing. Some additional data are reported on the crystal structure of U--5 wt.% Mo alloy. The thermal stability of this alloy (gamma phase) at 400 deg C with a constant stress of 15,000 psi does not appear to be effected. X-ray examination of a number of UO/sub 2/ samples was completed for samples with O/U ratios greater than 2. A large decrease in the unit cell size with increasing O/U ratio was not observed. Radiation effects on a number of UO/sub 2/ samples fabricated in different ways are reported. Other radiation testing was continued on U--Nb, U-- Mo, and Zircaloy-2 clad U--Nb alloys. The effoct of water, impurities, defect size, and stress on corrosion of U--12 wt.% Mo were studied. Corrosion studies were also made on U--Mo--Pt alloys, U-- Nb alloys, and clad fuel elements. Work was continued on the prepuration of UO/sub 2/ by various methods and on the physical and chemical properties of UO/sub 2/. In-pile loops were used for UO/ sub 2/ defect tests and U/Mo defect tests. The mechanism and consequences of PWR fuel element rupture due to waterlogging were studied. Coolant contamination was studied and docontamination and waste disposal procedures were discussed. Shielding, criticality, and design studies were continued. (D.E.B.).

Download or read book Civilian Power Reactor Program written by U.S. Atomic Energy Commission and published by . This book was released on 1960 with total page 104 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book TID written by and published by . This book was released on 1958 with total page 446 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Reactor Safety written by and published by . This book was released on 1963 with total page 144 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book U S Government Research Reports written by and published by . This book was released on 1958 with total page 214 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Irradiation Testing of UO2 written by and published by . This book was released on 1960 with total page 24 pages. Available in PDF, EPUB and Kindle. Book excerpt: Included are 167 references to unclassified reports and scientific journals on irradiation testing of unalloyed UO2. Irradiation behavior and effects, heat transfer calculations, fission gas release, post-irradiation examination, and irradiation capsule design are the subject areas covered.

Download or read book PRESSURIZED WATER REACTOR PROGRAM TECHNICAL PROGRESS REPORT FOR THE PERIOD FEBRUARY 10 1955 TO MARCH 24 1955 written by and published by . This book was released on 2005 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Current PWR plant parameters are reviewed. Process specifications for the melting of U--Mo and U--Nb alloys are presented. The preparation of sintered UO/sub 2/ pellets containing polyvinyl alcohol as a binder was achieved without loss of corrosion resistance characteristic of such pellets. Volumetric O/U ratios were investigated in the high- and low-pressure oxidation of U by steam to UO/sub 2/. The corrosion of compacted UO/sub 2/ was then studied in water at 650 deg C. Further results are reported on studies of the chemical reaction betwoeen Zr and UCZ. Previously reported investigations on the water corrosion of U--Mo, U--Mo--Hb, U-Mo--Pt, and U--Nb were extended. The corrosion of Zircaloy cladding for these alloys was also tested. The effect of melting, drawing, extruding, annealing, and fabrication conditions on corrosion was also considered. No cracking or serious pitting was observed on a group of stainless steels exposed to citric acid solution for 1 hr at 180 deg F. The effects of radiation on the corrosion life of clad and unclad U--Mo and bare U--Si alloys were investigated. Radiation effects on Zircaloy-clad UO/sub 2/ dimensional stability, state of aggregntion, and fission gas release were examined. It has been determined that a 52% power fraction for the U--Mo blanket will exist for a 3/1 H/sub 2/O-to-U volume ratio. Operation of the seeded core for 3000 hr operation calls for a tentative loading of 69 kg of U/sup 235/. For an oxide blanket with the same H/sub 2/O-to-U ratio, the blanket power fraction is 60% and a loading of 52 kg of U/sup 235/is indicated. (D.E.B.).

Download or read book Criticality Studies written by and published by . This book was released on 1959 with total page 122 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Fuel Breeding written by and published by . This book was released on 1959 with total page 74 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Report Announcement Bulletin Unclassified Reports for Civilian Applications written by U.S. Atomic Energy Commission and published by . This book was released on 1957 with total page 24 pages. Available in PDF, EPUB and Kindle. Book excerpt: ""The U.S. Atomic Energy Commission is conducting a large-scale review of its research and development reports to make as much information as possible available through the Civilian Application Program. Report Announcement Bulletin ; Unclassified Reports For Civilian Applications is being published to announce immediately, the release of newly declassified reports. ...All reports announced in the Bulletin are available from: Office of Technical Services, Department of Commerce, Washington 25, D.C., at the price listed with each title."--P.iii.

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1973 with total page 1412 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book The Shippingport Pressurized Water Reactor Project Catalog of Document Abstracts written by and published by . This book was released on 1961 with total page 342 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book AEC Reports Declassified written by and published by . This book was released on 1957 with total page 326 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Heat Transfer and Fluid Flow written by James M. Jacobs and published by . This book was released on 1958 with total page 444 pages. Available in PDF, EPUB and Kindle. Book excerpt: A total of 2519 annotated references to the unclassified report literature is presented. Subjects covered under heat transfer and fluid flow include radioinduced heating; boiling; boiler, evaporators, pump, and heat exchanger design; hydrodynamics; coolants and their properties; thermal and flow instrumentation; high temperature materials; thermal properties of materials; and thermal insulation. Subjects covered less completely include thermodynamics; aerodynamics; high temperature corrosion; corrosion specific to heat transfer systems; erosion; mass transfer; corrosion film formation and effects; coolant processing and radioactivity; radiation effects of heat transfer materials; and pertinent data of thermonuclear processes. Subject, report number availability, and author indexes are given.