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Acceptance sampling plans

Description: A compilation is presented of attributes and variables acceptance sampling plans and procedures which may be used as a ready reference to provide protection to both supplier and purchaser whenever sampling inspection is involved. Some of the basic and underlying principles involved in these plans and procedures are discussed. The plans and procedures provide for selection of adequate sample quantities and evaluation of inspection data for the purpose of determining conformance to the specified lot tolerance percent defective (LTPD) and BETA error acceptance criteria. (auth)
Date: November 1, 1973
Partner: UNT Libraries Government Documents Department

Evaluation of the computer program CREEP--PLAST (CDC version)

Description: From ASME annual winter meeting; Detroit, Michigan, USA (Dec 1973). The results of an evaluation of the CREEP-PLAST Program are reported. The assumptions in the formulation of the Program are reviewed. Program operations and user oriented features that were added to the Program are discussed. Selected benchmark problems are then solved and the results are compared with known solutions. (10 references) (auth)
Date: January 1, 1973
Creator: Hsu, M.B.; Berman, I. & Pai, D.H.
Partner: UNT Libraries Government Documents Department

An Assessment of Visual Testing

Description: In response to increasing interest from nuclear utilities in replacing some volumetric examinations of nuclear reactor components with remote visual testing, the Pacific Northwest National Laboratory has examined the capabilities of remote visual testing for the Nuclear Regulatory Commission. This report describes visual testing and explores the visual acuities of the camera systems used to examine nuclear reactor components. The types and sizes of cracks typically found in nuclear reactor components are reviewed. The current standards in visual testing are examined critically, and several suggestions for improving these standards are proposed. Also proposed for future work is a round robin test to determine the effectiveness of visual tests and experimental studies to determine the values for magnification and resolution needed to reliably image very tight cracks.
Date: November 1, 2004
Creator: Cumblidge, Stephen E.; Anderson, Michael T. & Doctor, Steven R.
Partner: UNT Libraries Government Documents Department

Preparation of system design descriptions

Description: A standard is presented which prescribes the purpose, scope, organization, and content of system design descriptions (SSD's), in order to promulgate a unified approach to their preparation and use by a project as the principal means to establish, describe, and control the individual system designs from conception and throughout the lifetime of the system. SDD's are comprehensive technical documents that specifically and completely define the design, including operation, maintenance, and reliability requirements, of individual systems which comprise a nuclear power plant or test facility. SDD's are prepared and maintained current by the responsible system designer and are the principal means of system design definition and control common to the designer and the other participating organizations responsible for the project. (auth)
Date: December 1, 1975
Partner: UNT Libraries Government Documents Department

Transportation of critical components and equipment

Description: A standard is presented which covers recommended practices in the planning, coordination, and administration of shipments of critical components and equipment for nuclear facilities. The standard supplements and is additive to the rules and regulations of freight classifications and tariffs governing carriers and shipping, and has the purpose of minimizing the liklihood of physical damage or deterioration of critical components and equipment due to collision, upset, shock, vibration, corrosion, or other conditions of the transport environment. (auth)
Date: January 1, 1976
Partner: UNT Libraries Government Documents Department

Memorandum on Chemical Reactors and Reactor Hazards

Description: Two important problems in the investigation of reactor hazards are the chemical reactivity of various materials employed in reactor construction and the chracteristics of heat transfer under transient conditions, specifically heat transfer when driven by an exponentially increasing heat source (exp t/T). Although these problems are independent of each other, when studied in relation to reactor hazards they may occur in a closely coupled sequence. For example the onset of a dangerous chemical reactor may be due to structural failure of various reactor components under an exponentially rising heat source originating with a runaway nuclear reactor. For this reason, these two problems should eventually be studied together after an exploratory experimental survey has been made in which they are considered separately.
Date: July 5, 1951
Creator: Mills, M.M.; Pearlman, H.; Ruebsamen, W. & Steele, G., Chrisney, J.
Partner: UNT Libraries Government Documents Department