Author: R. E. HallPublisher:
ISBN:
Category :
Languages : en
Pages : 14
Book Description
PT IP-183-A-98-FP Evaluation on Projection Fuel Elements for Use in K Process Tubes
Author: R. E. Hallיונה מזרחית
Author: Supplement A to PT-IP-183-A-98-FP
Author: Publisher:
ISBN:
Category :
Languages : en
Pages : 10
Book Description
The objective of this supplement is to authorize charging of ten tubes of ''bumper'' fuel elements and controls into each K Reactor. The test is designed to reevaluate the reduction in hot-spot incidence associated with fuel alignment within K Reactor ribbed process tubes for both natural and enriched uranium I & E fuel elements of the KIV geometry.
Supplement A to PT-UP-183-A-98-FP Evaluation of Projection Fuel Elements for Use in K Process Tubes
Author: M. A. ClintonEnergy Research Abstracts
Author: Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 806
Book Description
Semiannual, with semiannual and annual indexes. References to all scientific and technical literature coming from DOE, its laboratories, energy centers, and contractors. Includes all works deriving from DOE, other related government-sponsored information, and foreign nonnuclear information. Arranged under 39 categories, e.g., Biomedical sciences, basic studies; Biomedical sciences, applied studies; Health and safety; and Fusion energy. Entry gives bibliographical information and abstract. Corporate, author, subject, report number indexes.
Design of Supplement B to PT-IP-262-A-11-FP, Evaluation of Projection Fuel Elements for Use in Ribbed Process Tubes
Author: Publisher:
ISBN:
Category :
Languages : en
Pages : 17
Book Description
One of the three major categories of HAPO fuel element failures is the side corrosion type rupture. The majority of side-corrosion failures has been characterized by oval or tear-drop shaped flow patterns containing evidence of accelerated corrosion. Thorough examination of many of these so-called 'hot spot' failures has indicated the failure was caused by poor heat transfer associated with misalignment, dimensional distortion or poor jacket-to-core bonding. It has been postulated that misalignment of the fuel element is a necessary condition for formation of hot spots under the present reactor operating conditions. Neither tru-line contours nor X-8001 alloy are successful in the prevention of misalignment and associated ruptures; therefore, it has been proposed to test the effectiveness of projections on the side of the fuel element toward preventing fuel misalignment in ribbed process tubes. A previous test of this element termed the 'bumper fuel element' was encouraging; however, it failed to provide the conclusive proof required to justify a large-scale demonstration loading. Supplement A to the basic test was written to obtain necessary preliminary data. This report presents an outline of further testing required to accelerate evaluation of the bumper concept.
Supplement A, Production Test IP-262-A-11-FP
Author: R. E. HallProduction Test IP-262-A-11-FP
Author: R. E. HallDesign of Production Test IP-262-A-11-FP -- Evaluation of Projection Fuel Elements for Use in Ribbed Process Tubes -- Demonstration Loading
Author: Publisher:
ISBN:
Category :
Languages : en
Pages : 9
Book Description
For several years, a major category of fuel element failures has been the side corrosion type, characterized by localized accelerated fuel element jacket corrosion. Since it has been demonstrated 1 that misalignment of fuel elements in a process tube will produce flow patterns and accelerated corrosion, termed ''hot spots'', failure to align the fuel elements in process tubes is considered a contributing factor in the production of side corrosion failures. Preliminary testing of both self-supporting and ''bumper'' fuel elements is underway. Data on the self-supporting fuel elements have demonstrated that the bridge-rail projections have sufficient support strength, do not of themselves create a corrosion problem and in actuality probably eliminate any hot-spot areas. Although one tube of bumper fuel elements in KW Reactor 3 has been discharged, data are not as yet available. Potentially, the most sever corrosion conditions exist during the summer months when reactor inlet temperatures are high. It is desirable then, provided bumper fuel elements limit hot- spot corrosion, to evaluate the bumper concept for large scale use possibly by the summer of 1960. To accomplish this, a demonstration loading of the bumper type fuel elements must be underway by about July, 1959. The purpose of this report is to present the design of a test to evaluate the fabrication process and irradiation performance of fuel elements having projections, which may prevent misalignment in ribbed process tubes and meet the aforementioned goals.
Supplement A to PT-IP-263-A-FP Evaluation of Chemically Nickel Plated Fuel Elements
Author: Publisher:
ISBN:
Category :
Languages : en
Pages : 11
Book Description
Irradiation of the initial test in this program involving ten tubes of alternately charged nickel-plated C-64 alloy clad test elements and X-8001 alloy control elements has been successfully completed. The test indicated that the nickel-plate spalling problem has been resolved as no significant spalling or flaking was observed during the post-irradiation examination. The second test in this program will be to verify the performance of nickel-plate with a pilot loading (up to 100 charges) of fuel elements which have been nickel-plated on a production basis. The objectives of this test are to demonstrate with a larger scale test that nickel-plate performs satisfactorily and that reducing the nominal plate thickness from .6 mil to .2 mil will not affect the performance of the nickel-plate fuel element. This test authorizes the irradiation of up to 100 columns of OIIN, chemically nickel-plated, C-64 alloy jacketed fuel elements to 200% of normal goal exposure to extend the evaluation of nickel-plated fuel elements on a pilot scale at DR Reactor. Seventy columns will be plated to a nominal thickness of .6 mil and thirty columns to a nominal .2 mil thickness. Twenty measured columns, ten representing each plate thickness, will be charged to monitor the irradiation performance. Effluent samples will be obtained during the course of the test from a pair of tubes, each tube containing a measured monitor charge representing each plate thickness.