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Supplement to Reactor Containment Design Study

Description: Summary: Report SL-1868 is a technical and economic feasibility study of four containment methods, i.e., standard containment, pressure relief, pressure supression and low pressure containment, for 44 MWe direct cycle and 180 and 300 MWe dual cycle boiling water reactor plants.
Date: April 23, 1962
Creator: Johnson, R. A. & Nelson, I.
Partner: UNT Libraries Government Documents Department

Studies of Reactor Containment

Description: The following report includes a description of apparatus and techniques for the observation of the behavior of blast shield segments and materials when impulsively loaded, some preliminary dynamic stress-strain data, and some observations of compression wave propagation in porous media.
Date: August 1958
Creator: Napadensky, H. S.; Pinsky, J. & Stresau, R.
Partner: UNT Libraries Government Documents Department


Description: An attempt is made to present available information pentinent to reactor containment. This is done directly, by summary and reference, or by reference alone. To provide a reference framework, the first review document must necessarily be handled differently from supplemental periodic reviews. The plan is to: (3) provide a detailed account of the problem and suggestions for work needed to yield adequate solutions; (2) present the accumulated knowledge and accomplishments; (3) give an account of experience in applying the containment concept; and (4) append extensive bibliographical material. An attempt is made in each case to indicate the significance of the information and its relation to the problems outlined. (A.C.)
Date: May 1, 1959
Creator: Brittan, R.O.
Partner: UNT Libraries Government Documents Department

Reactor Containment Design Study

Description: Introduction: Sargent & Lundy was authorized on November 1, 1960, to make an economic and technical feasibility study of various reactor containment designs which are being utilized for several power plants now under construction.
Date: May 18, 1961
Creator: Johnson, R. A. & Nelson, I.
Partner: UNT Libraries Government Documents Department

Hanford prototype-barrier status report: FY 1995

Description: Surface barriers (or covers) have been proposed for use at the Hanford Site as a means to isolate certain waste sites that, for reasons of cost or worker safety or both, may not be exhumed. Surface barriers are intende to isolated the wastes from the accessible environment and to provide long-term protection to future populations that might use the Hanford Site. Currently, no ``proven`` long-term barrier system is available. For this reason, the Hanford Site Permanent Isolation Surface-Barrier Development Program (BDP) was organized to develop the technology needed to provide long-term surface barrier capability for the Hanford Site for the US Department of Energy (DOE). Designs have been proposed to meet the most stringent needs for long-term waste disposal. The objective of the current barrier design is to use natural materials to develop a protective barrier system that isolates wastes for at least 1000 years by limiting water, plant, animal, and human intrusion; and minimizing erosion. The design criteria for water drainage has been set at 0.5 mm/yr. While other design criteria are more qualitative, it is clear that waste isolation for an extended time is the prime objective of the design. Constructibility and performance. are issues that can be tested and dealt with by evaluating prototype designs prior to extensive construction and deployment of covers for waste sites at Hanford.
Date: November 1, 1995
Creator: Gee, G.W.; Ward, A.L.; Gilmore, B.G.; Ligotke, M.W. & Link, S.O.
Partner: UNT Libraries Government Documents Department

105-KE Basin isolation barrier leak rate test analytical development. Revision 1

Description: This document provides an analytical development in support of the proposed leak rate test of the 105-KE Basin. The analytical basis upon which the K-basin leak test results will be used to determine the basin leakage rates is developed in this report. The leakage of the K-Basin isolation barriers under postulated accident conditions will be determined from the test results. There are two fundamental flow regimes that may exist in the postulated K-Basin leakage: viscous laminar and turbulent flow. An analytical development is presented for each flow regime. The basic geometry and nomenclature of the postulated leak paths are denoted.
Date: May 9, 1995
Creator: Irwin, J. J.
Partner: UNT Libraries Government Documents Department

Studies of reactor containment structures : bi-monthly progress report, March 1, 1962 to February 28, 1962

Description: A report about analyzing the responses of containment vessels, the effect of openings on the strength of containment vessels, bulging experiments on pressurized cylinders of finite length, and the development of the containment handbook.
Date: 1962
Creator: Weil, N. A.; Chiapetta, R. L.; Costantino, C. J.; Hodge, Philip Gibson, 1920-; Morse, Stearns A. & Salmon, M. A.
Partner: UNT Libraries Government Documents Department

Instrumentation of a prestressed concrete containment vessel model

Description: A series of static overpressurization tests of scale models of nuclear containment structures is being conducted by Sandia National Laboratories for the Nuclear Power Engineering Corporation of Japan and the U.S. Nuclear Regulatory Commission. At present, two tests are being planned: a test of a model of a steel containment vessel (SCV) that is representative of an improved, boiling water reactor (BWR) Mark II design; and a test of a model of a prestressed concrete containment vessel (PCCV). This paper discusses plans and the results of a preliminary investigation of the instrumentation of the PCCV model. The instrumentation suite for this model will consist of approximately 2000 channels of data to record displacements, strains in the reinforcing steel, prestressing tendons, concrete, steel liner and liner anchors, as well as pressure and temperature. The instrumentation is being designed to monitor the response of the model during prestressing operations, during Structural Integrity and Integrated Leak Rate testing, and during test to failure of the model. Particular emphasis has been placed on instrumentation of the prestressing system in order to understand the behavior of the prestressing strands at design and beyond design pressure levels. Current plans are to place load cells at both ends of one third of the tendons in addition to placing strain measurement devices along the length of selected tendons. Strain measurements will be made using conventional bonded foil resistance gages and a wire resistance gage, known as a {open_quotes}Tensmeg{close_quotes}{reg_sign} gage, specifically designed for use with seven-wire strand. The results of preliminary tests of both types of gages, in the laboratory and in a simulated model configuration, are reported and plans for instrumentation of the model are discussed.
Date: September 1995
Creator: Hessheimer, M. F.; Rightley, M. J. & Matsumoto, T.
Partner: UNT Libraries Government Documents Department

Surface Environmental Surveillance Procedures Manual

Description: Environmental surveillance data are used in assessing the impact of current and past site operations on human health and the environment, demonstrating compliance with applicable local, state, and federal environmental regulations, and verifying the adequacy of containment and effluent controls. SESP sampling schedules are reviewed, revised, and published each calendar year in the Hanford Site Environmental Surveillance Master Sampling Schedule. Environmental samples are collected by SESP staff in accordance with the approved sample collection procedures documented in this manual.
Date: September 20, 2000
Creator: Hanf, RW & Poston, TM
Partner: UNT Libraries Government Documents Department

Technical Assistance in Review of Source Term-Related Issues of Advanced Reactors

Description: The distribution of iodine in containment during an AP-600 design-basis accident was evaluated using models in the "TRENDS" code. The AP-6003BE accident sequmce calculations showed that a pH >7 was maintained for at least 30 days. Because the pH was maintained at this level, most of the iodine was in the form of iodid~ only 3 x 10-3% was present as aqueous 12, and only 1 x 10< `/0 was present as J in the vapor phase.
Date: October 1, 1998
Creator: Beahm, E.C.; Dillow, T.A. & Weber, C.F.
Partner: UNT Libraries Government Documents Department

Test report for PAS-1 cask certification for shipping payload B

Description: This test report documents the successful inspection and testing to certify two NuPac PAS-1 casks in accordance with US Department of Energy Certificate of Compliance (CoC) USA/9184/B(U). The primary and secondary containment vessels of each cask met the acceptance criteria defined in the CoC and the test plan.
Date: October 13, 1998
Creator: MERCADO, J.E.
Partner: UNT Libraries Government Documents Department


Description: The objective of this analysis is to explore the Uncanistered Fuel (UCF) Tube Design waste package (WP) resistance to rock falls. This analysis will also be used to determine the size of rock that can strike the WP without causing failure in the containment barriers from a height based on the starter tunnel dimensions. The purpose of this analysis is to document the models and methods used in the calculations.
Date: October 18, 1996
Creator: Ceylan, Z.
Partner: UNT Libraries Government Documents Department

Wildfire Suppression Spending: Background, Issues, and Legislation in the 115th Congress

Description: This report provides background information and analysis of federal funding for wildfire suppression operations on federal lands or for fires that began on federal land. The report provides a discussion of the issues facing Congress and concludes by summarizing several legislative proposals under consideration by the 115th Congress.
Date: October 5, 2017
Creator: Hoover, Katie & Lindsay, Bruce R.
Partner: UNT Libraries Government Documents Department