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An Evaluation of Through-Thickness Changes in Primary Damage Production in Commercial Reactor Pressure Vessels

Description: An extensive database of atomic displacement cascades in iron has been developed using the method of molecular dynamics (MD). More than 300 simulations have been completed at 100K with energies between 0.1 and 100 keV. This encompasses nearly all energies relevant to fission reactor irradiation environments since a 100 keV MD cascade corresponds to the average iron cascade following a collision with a 5.1 MeV neutron. Extensive statistical analysis of the database has determined representative average values for several primary damage parameters: the total number of surviving point defects, the fraction of the surviving point defects contained in clusters formed during cascade cooling, and a measure of the size distribution of the in-cascade point defect clusters. The cascade energy dependence of the MD-based primary damage parameters has been used to obtain spectrum-averaged defect production cross sections for typical fission reactor neutron energy spectra as a function of depth through the reactor pressure vessel. The attenuation of the spectrum-averaged cross sections for total point defect survival and the fraction of either interstitials or vacancies in clusters are quite similar to that for the NRT dpa. However, the cross sections derived to account for the energy dependence of the point defect cluster size distributions exhibit a potentially significant variation through the vessel. The production rate of large interstitial clusters decreases more rapidly than dpa whereas the production of large vacancy clusters is slower than dpa.
Date: February 14, 2001
Creator: Stoller, R. E.
Partner: UNT Libraries Government Documents Department
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Pressure Vessel Steel Surveillance Program for General Electric Power Reactors

Description: Abstract: "Pressure vessel steel surveillance programs are performed in nuclear power reactors to provide knowledge of the mechanical properties of the pressure vessel material as neutron irradiation proceeds. A standard surveillance program is described. Design of specimens, capsules, and associated equipment, as well as selection of test material and techniques for special preparation and testing, are discussed."
Date: January 8, 1965
Creator: Brandt, F. A.
Partner: UNT Libraries Government Documents Department
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Pressure and flow characteristics of restrictive flow orifice devices.

Description: A Restrictive Flow Orifice (RFO) can be used to enhance the safe design of a pressure system in several ways. Pressure systems frequently incorporate a regulator and relief valve to protect the downstream equipment from accidental overpressure caused by regulator failure. Analysis frequently shows that in cases of high-flow regulator failure, the downstream pressure may rise significantly above the set pressure of the relief valve. This is due to limited flow capacity of the relief valve. A different regulator or relief valve may need to be selected. A more economical solution to this problem is to use an RFO to limit the maximum system flow to acceptable limits within the flow capacity of the relief valve, thereby enhancing the overpressure protection of laboratory equipment. An RFO can also be used to limit the uncontrolled release of system fluid (gas or liquid) upon component or line failure. As an example, potential asphyxiation hazards resultant from the release of large volumes of inert gas from a 'house' nitrogen system can be controlled by the use of an RFO. This report describes a versatile new Sandia-designed RFO available from the Swagelok Company and specifies the gas flow characteristics of this device. Two sizes, 0.010 and 0.020 inch diameter RFOs are available. These sizes will allow enhanced safety for many common applications. This new RFO design are now commercially available and provide advantages over existing RFOs: a high pressure rating (6600 psig); flow through the RFO is equal for either forward or reverse directions; they minimize the potential for leakage by incorporating the highest quality threaded connections; and can enhance the safety of pressure systems.
Date: June 1, 2003
Creator: Shrouf, Roger D.
Partner: UNT Libraries Government Documents Department
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Reactor Safety Quarterly Progress Report for January-March 1957

Description: ABS>Seven special safety elements of the Mark II design were rebuilt and are ready for resumption of lifetime testing. Precision-cast parts were received for ten Mark IV highpressure chambers; one set was assembled and pressdre tested to 2000 psi. Two special assemblies of the NAA 1093 experiment were completed and are being shipped to Hanford. Conductivity measurements on stainles s steel were continued in an effort to determine the cause of erratic behavior of the variable-cooled trigger. A vacuum chamber was used in am effort to eliminate local heat loss due to convection. A study of corrosion rates of various container materials in liquid-metal poisons was umdertaken. Experiments with the differential-pressure device on the rate of pressure rise thnt can be achieved by electrically heating a closed gas volume were continued. An exponential generator is being constructed to enable simulation of reactor periods from 30 msec to one sec. Three types of research reactor safety device were chosen for further study: the pyrophoric, the double-diaphragm, and the electronic-explosive. Preparations are in process for demonstrating models of the latter two devices in the KEWB facility. (For preceding period see NAA-SR1954.) (M.H.R.)
Date: December 1, 1957
Creator: Miller, N.C. ed.
Partner: UNT Libraries Government Documents Department
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Assessment of behavior and design of steel liners for concrete reactor vessels. Final report

Description: A procedure for the accurate independent assessment of the design and performance of steel liners for concrete reactor vessels is described. Descriptions presented include current design practice, evaluation of current design practice, design review information requirements, and design review guidelines. (55 references) (JWR)
Date: December 1, 1973
Creator: Lee, T.T. & Gurbuz, O.
Partner: UNT Libraries Government Documents Department
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High Pressure Low Resistance Joint

Description: The following report describes the usage of tin-foil to obtain a mechanical joint of low electrical resistance while providing a seal to hold water at a pressure of 300 psi.
Date: March 28, 1955
Creator: Peters, Ralph
Partner: UNT Libraries Government Documents Department
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REACTOR CONTAINMENT (INCLUDING A TECHNICAL PROGRESS REVIEW)

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

[Stresses in Reinforced Nozzle-Cylinder Attachments Under External Moment Loadings Analyzed by the Finite-Element Method: A Parameter Study: Stress Values]

Description: The following data presents stress value results from finite-element mesh studies described in its parent document, Stresses in Reinforced Nozzle-Cylinder Attachments Under External Moment Loadings Analyzed by the Finite-Element Method: A Parameter Study.
Date: 1979
Creator: Bryson, J. W.; Johnson, W. G. & Bass, B. R.
Partner: UNT Libraries Government Documents Department
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Stresses in Reinforced Nozzle-Cylinder Attachments Under External Moment Loadings Analyzed by the Finite-Element Method: A Parameter Study

Description: A report discussing work performed at the Oak Ridge National Laboratory in support of the ORNL Design Criteria for Piping and Nozzle Program being conducted for the U.S. Nuclear Regulatory Research.
Date: 1979
Creator: Bryson, J. W.; Johnson, W. G. & Bass, B. R.
Partner: UNT Libraries Government Documents Department
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Reducing Ultra-Clean Transportation Fuel Costs with HyMelt Hydrogen Quarterly Report: March-June 2006

Description: This report describes activities for the fifteenth quarter of work performed under this agreement. MEFOS, the gasification testing subcontractor, reported to EnviRes that the vendor for the pressure vessel for above atmospheric testing plans to deliver it by October 20, 2006. MEFOS performed a hazardous operation review of pressurized testing.
Date: July 1, 2006
Creator: Malone, Donald P. & Renner, William R.
Partner: UNT Libraries Government Documents Department
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Reducing Ultra-Clean Transportation Fuel Costs with HyMelt Hydrogen Quarterly Report

Description: This report describes activities for the eighth quarter of work performed under this agreement. We await approval from the Swedish pressure vessel board to allow us to proceed with the procurement of the vessel for super atmospheric testing.
Date: April 1, 2005
Creator: Malone, Donald P. & Renner, William R.
Partner: UNT Libraries Government Documents Department
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Reducing Ultra-Clean Transportation Fuel Costs with HyMelt Hydrogen Quarterly Report

Description: This report describes activities for the seventh quarter of work performed under this agreement. We await approval from the Swedish pressure vessel board to allow us to proceed with the procurement of the vessel for super atmospheric testing.
Date: October 1, 2004
Creator: Malone, Donald P. & Renner, William R.
Partner: UNT Libraries Government Documents Department
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