Design of Production Test IP-262-A-11-FP -- Evaluation of Projection Fuel Elements for Use in Ribbed Process Tubes -- Demonstration Loading PDF Download
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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.
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.
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.
Author: Publisher: ISBN: Category : Languages : en Pages : 8
Book Description
To evaluate the self-supported fuel element concept, tests are underway to determine the performance of collapsible bridge-rail supported fuel elements in ribless process tubes under present reactor conditions at B Reactor. It appears expedient, however, to extend this evaluation to future operating conditions in order to establish the relative feasibility of conversion to self-supported fuel elements in ribless tubes in present reactors. Utilization of 1.47% U-235 enrichment will provide fuel element powers comparable to those attainable under proposed future conditions. Since I & E fuel elements of this enrichment have previously attained exposures in excess of 2000 MWD/T at specific powers averaging 75 KW/ft in C Reactor, this test will specifically evaluate the feasibility of the self-supported fuel element concept. The purpose of this report is to present the design of a test to fabricate and evaluate self-supported fuel elements under conditions of comparable severity to those expected for future loadings of this geometry.
Author: Publisher: ISBN: Category : Languages : en Pages : 10
Book Description
The objectives of the test described in this report are to evaluate the integrity of I & E MINT fuel elements canned by the ''C'' process to determine the conversion ratio of I & E geometry E-N ''striped loadings, '' and to provide a demonstration loading for a full reactor loading incorporating a ''striped'' center loading and a fringe ''blanket'' loading. This test will involve two portions a 26 tube block loading of I & E enriched uranium and MINT fuel elements arranged in a striped array, and a 10 tube fringe blanket loading of MINT fuel elements supported by the required enriched uranium fuel columns, and accompanied by controls. Either portion may be charged independently.
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Author: R. E. Hall
Author: R. E. Hall
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Author: W. H. Hodgson
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Author: R. E. Hall