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Decommissioning of a grout- and waste-filled storage tank in the 200 East Area of the Hanford Site

Description: A self-concentrating waste tank located at the Strontium Semiworks Facility in the 200 East Area of the Hanford Site will be decommissioned following waste removal. During a previous decommissioning phase, the tank, thought to be empty, was filled with grout to prevent it from collapsing over time. Several years later, an agitator rod was pulled from within the tank and found to contain significant amounts of radiation, indicating there was still radioactive waste in the tank. Several alternati… more
Date: January 1, 1991
Creator: Marske, S.G.
Partner: UNT Libraries Government Documents Department
open access

Severe accident core heatup transients in modular high temperature gas-cooled reactors without operating Reactor Cavity Cooling Systems

Description: The ultimate decay heat removal system for the current Modular High Temperature Gas-Cooled reactors is a completely passive natural convection air cooling loop. This paper considers an extremely remote accident scenario, where even this passive system fails, and heat rejection is only via a layer of thermal insulation to the reactor silo structure and the surrounding soil. The results show that even in this case the peak fuel temperatures remain well within safe limits. However, vessel and conc… more
Date: January 1, 1988
Creator: Kroeger, P. G.
Partner: UNT Libraries Government Documents Department
open access

Compatibility testing of vitrified waste forms

Description: An experimental program to evaluate candidate metals for use in the fabrication of canisters for long-term storage of vitrified radioactive wastes is described. The long-term compatibility of the candidate metal both with the contained vitrified radioactive waste and with the external environments expected in possible final storage locations will be determined. These tests involve heating combinations of waste forms and canister metals in intimate contact for up to 50,000 hr to accelerate any r… more
Date: March 6, 1978
Creator: Rankin, W.N.
Partner: UNT Libraries Government Documents Department
open access

Integrity of PWR pressure vessels during overcooling accidents

Description: The reactor pressure vessel in a pressurized water reactor is normally subjected to temperatures and pressures that preclude propagation of sharp, crack-like defects that might exist in the wall of the vessel. However, there is a class of postulated accidents, referred to as overcooling accidents, that can subject the pressure vessel to severe thermal shock while the pressure is substantial. As a result of such accidents vessels containing high concentrations of copper and nickel, which enhance… more
Date: January 1, 1982
Creator: Cheverton, R.D.; Iskander, S.K. & Whitman, G.D.
Partner: UNT Libraries Government Documents Department
open access

Cesium-137 source material for an irradiator

Description: The feasibility of using /sup 137/Cs for the gamma source in sludge irradiators is discussed. It was concluded that /sup 137/Cs, because of its availability in large quantities as a by-product of fission in nuclear reactors, is an excellent candidate source for use in sewage sludge irradiators. The capsules used to store /sup 137/CsCl in the Waste Encapsulation and Storage Facility embody the technology gained by extensive development and experience during the past 25 years. The WESF capsule pr… more
Date: January 1, 1980
Creator: Lamb, E.
Partner: UNT Libraries Government Documents Department
open access

Tilt-pour melt-caster for encapsulation of radioactive cesium

Description: Use of the tilt-pour melt-caster makes distinct improvements in the cesium encapsulation process. Compared to the vacuum castings system now in use, the tilt-pour equipment requires no reliance on heat-traced transfer lines, less sealing pressure for capsule filling, is less corrosive to capsules and is easier to repair. From the results of the extensive development program, it is concluded that the tilt-pour melt-caster can be operated to meet the cesium encapsulation production and maintenanc… more
Date: January 1, 1977
Partner: UNT Libraries Government Documents Department
open access

Investigation of breached depleted UF sub 6 cylinders

Description: In June 1990, during a three-site inspection of cylinders being used for long-term storage of solid depleted UF{sub 6}, two 14-ton cylinders at Portsmouth, Ohio, were discovered with holes in the barrel section of the cylinders. An investigation team was immediately formed to determine the cause of the failures and their impact on future storage procedures and to recommend corrective actions. Subsequent investigation showed that the failures most probably resulted from mechanical damage that oc… more
Date: January 1, 1991
Creator: DeVan, J. H.
Partner: UNT Libraries Government Documents Department
open access

Radiolytic Effects on Ion Exchangers During the Storage of Radioactive Wastes

Description: Radiolytic effects on ion exchangers are being recognized as a significant problem in the processing and storage of high-specific-activity radioactive waste forms. Two major literature surveys and a series of scoping experiments conducted during this investigation indicate that radiation decomposition of ion exchange materials has the potential for a variety of undesirable consequences. These include the ready dispersion of adsorbed radionuclides to the environment, corrosion and pressurization… more
Date: January 1, 1982
Creator: Pillay, K. K. S. & Palau, G. L.
Partner: UNT Libraries Government Documents Department
open access

Static and dynamic analyses on the MFTF-B vacuum vessel. Revision 1

Description: The Mirror Fusion Test Facility is a major magnetic fusion energy project at the Lawrence Livermore National Laboratory. An important component of this facility is the vacuum vessel, which forms the vacuum chamber. The vessel is supported on twenty-two pairs of legs that rest on reinforced concrete piers. In performing static and dynamic analyses on the vacuum vessel, we separately investigated the load distribution under gravity loads, pressure loads, electromagnetic loads, and thermal loads. … more
Date: January 15, 1984
Creator: Ng, D.S.
Partner: UNT Libraries Government Documents Department
open access

Nondestructive evaluation of LWR spent fuel shipping casks

Description: An analysis of nondestructive testing (NDT) methods currently being used to evaluate the integrity of Light Water Reactor (LWR) spent fuel shipping casks is presented. An assessment of anticipated NDT needs related to breeder reactor cask requirements is included. Specific R and D approaches to probable NDT problem areas such as the evaluation of austenitic stainless steel weldments are outlined.
Date: February 1, 1978
Creator: Ballard, D. W.
Partner: UNT Libraries Government Documents Department
open access

Uranium hexafluoride: Safe handling, processing, and transporting: Conference proceedings

Description: This conference seeks to provide a forum for the exchange of information and ideas of the safety aspects and technical issue related to the handling of uranium hexafluoride. By allowing operators, engineers, scientists, managers, educators, and others to meet and share experiences of mutual concern, the conference is also intended to provide the participants with a more complete knowledge of technical and operational issues. The topics for the papers in the proceedings are widely varied and inc… more
Date: January 1, 1988
Creator: Strunk, W.D. & Thornton, S.G. (eds.)
Partner: UNT Libraries Government Documents Department
open access

Investigation of cooling coil corrosion in storage tanks for radioactive waste

Description: The high frequency of cooling coil leaks observed in high-heat waste storage tanks soon after sludge removal operations is attributed to pitting, according to laboratory corrosion studies. Experiments show that the most likely series of events leading to coil leakage is (1) excessive dilution of basic nitrite in the supernate, (2) initiation of attack in crevices due to oxygen depletion cells, and (3) acceleration of the attack by sulfate dissolved from the sludge. When sludge was slurried with… more
Date: January 1, 1978
Creator: Ondrejcin, R.S.
Partner: UNT Libraries Government Documents Department
open access

CRBRP reactor system shield design and impact of new materials irradiation damage data

Description: Structural materials radiation damage data have received considerable attention in the design of LMFBR permanent reactor structures. A recent FFTF/CRBRP structural materials irradiation experiment, conducted as part of the national program plan for irradiation effects on mechanical properties of LMFBR out-of-core structural materials, has found engineering application in setting energy-dependent neutron exposure limits of irradiated structures. This paper describes the impact of the new irradia… more
Date: January 1, 1980
Creator: Wrights, G.N.
Partner: UNT Libraries Government Documents Department
open access

Three-dimensional thermal analysis of a baseline spent fuel repository

Description: A three-dimensional thermal analysis has been performed using finite difference techniques to determine the near-field response of a baseline spent fuel repository in a deep geologic salt medium. A baseline design incorporates previous thermal modeling experience and OWI recommendations for areal thermal loading in specifying the waste form properties, package details, and emplacement configuration. The base case in this thermal analysis considers one 10-year old PWR spent fuel assembly emplace… more
Date: June 5, 1980
Creator: Altenbach, T.J. & Lowry, W.E.
Partner: UNT Libraries Government Documents Department
open access

Design and analysis of PCRV core cavity closure

Description: Design requirements and considerations for a core cavity closure which led to the choice of a concrete closure with a toggle hold-down as the design for the Gas-Cooled Fast Breeder Reactor (GCFR) plant are discussed. A procedure for preliminary stress analysis of the closure by means of a three-dimensional finite element method is described. A limited parametric study using this procedure indicates the adequacy of the present closure design and the significance of radial compression developed a… more
Date: May 1, 1980
Creator: Lee, T.T.; Schwartz, A.A. & Koopman, D.C.A.
Partner: UNT Libraries Government Documents Department
open access

LWR-PV damage estimate methodology

Description: A credible estimate of the pressure vessel lifetime due to neutron-induced embrittlement is studied. The first step toward this goal is the accurate prediction of fluence and neutron energy spectrum at the pressure vessel. This, in turn, is obtained from least squares unfolding techniques of dosimetry measurements at a surveillance position, transport calculations, and a translation of information obtained at the surveillance position to the damage position. Including a prototypic neutron field… more
Date: January 1, 1980
Creator: Wagschal, J.J.; Maerker, R.E. & Broadhead, B.L.
Partner: UNT Libraries Government Documents Department
open access

Methods for measuring the surface tritium inside TFTR using beta decay

Description: Three potential methods for measuring the surface tritium content of the TFTR vacuum vessel are described, each based on a different technique for measuring the in situ beta emission from tritium. These methods should be able to provide both a local and a global assessment of the tritium content within the top [approx] 1[mu]m of the inner wall surface.
Date: January 1, 1994
Creator: Zweben, S. J.; Johnson, D. & Hill, K. (Princeton Univ., NJ (United States). Plasma Physics Lab.) (and others)
Partner: UNT Libraries Government Documents Department
open access

Assessment of the response of spent fuel transports to malevolent acts

Description: This paper describes the results of a program conducted at Sandia National Laboratories (SNL) for the US Department of Energy to provide an experimental data base for more accurately assessing the radiological consequences from a hypothetical sabotage attack on a spent fuel shipping cask. The primary objectives of the program were limited to: (1) evaluating the effectiveness of selected high explosive devices (HED) in breaching full-size spent fuel casks, (2) quantifying and characterizing rele… more
Date: December 20, 1983
Creator: Sandoval, R.P.
Partner: UNT Libraries Government Documents Department
open access

Startup test strategy for demonstrating the ability of DWPF to comply with the WAPS

Description: This document discusses Startup Test Program for the Defense Waste Processing Facility (DWPF) which has been formulated to demonstrate that the DWPF can be operated in a safe, environmentally responsible manner to produce a product that will meet the requirements of the Waste Acceptance Preliminary Specifications. Startup will be managed in four distinct phases: Integrated Water Runs, Cold Chemical Runs, Waste Qualification Runs, and Radioactive Operation. A variety of feeds will be used for Wa… more
Date: January 1, 1992
Creator: Sproull, J.F. & Marra, S.L.
Partner: UNT Libraries Government Documents Department
open access

The electrical insulation of the DIII-D advanced divertor electrode

Description: The electrode for biasing experiments on the DIII-D tokamak was installed in the summer of 1990 and biasing experiments have shown positive results. For the electrode, electrical insulation had to provide voltage standoff in the DIII-D divertor environment of neutral pressures in the range of 10{sup {minus}8} to 5 {times} 10{sup {minus}2} torr, variable magnetic fields, and in the presence of ionizing radiation. The electrical insulation system was designed and tested in air and vacuum for volt… more
Date: October 1, 1991
Creator: Smith, J. P.; Schaffer, M. J. & Hyatt, A. W.
Partner: UNT Libraries Government Documents Department
open access

Radioactive fuel cask railcar humping study

Description: The response of two radioactive shipping casks due to railroad humping shocks was calculated using a spring-mass model. The two railcars for these casks had different coupling mechanisms and different tiedown arrangements. Humping tests had been performed on one of the railcars (ATMX-600) and the resulting shock spectra was used to adjust the spring-mass model to get matching results. One car (designed for cask shipment) was equipped with Freightmaster E-15 end of car coupler and had about /sup… more
Date: January 1, 1978
Creator: Wilson, L.T. (comp.)
Partner: UNT Libraries Government Documents Department
open access

Telescopic zoom lens attachment for magnified views in underwater radiation environments

Description: This document consists of the notes that accompany a slide presentation (15 slides). The discussion begins with the need for the Telescopic Zoom Lens or TZL; why is was designed and fabricated as well as the design restraints that dictated its final form and function. Next is the use and modification of existing equipment; equipment that was used to remotely scan a nuclear reactor tank using eddy current and ultrasound. The uniqueness of the TZL mechanism itself is discussed; how it meets the d… more
Date: January 1, 1991
Creator: Appel, D.K.
Partner: UNT Libraries Government Documents Department
open access

Packaging and shipment of U. S. breeder reactor experiments

Description: Irradiation testing of fuels and materials in the Fast Test Reactor (FTR) required development of a shipping cask (designated T-3) and associated hardware for loading and shipping of these experiments to postirradiation examination facilities. The T-3 shipping-cask program included design, fabrication, and testing of internal cask packages to protect the experiments during loading, shipping, and unloading. The cask was designed for loading in both the vertical and horizontal attitudes.
Date: January 1, 1980
Creator: Berger, J. D.
Partner: UNT Libraries Government Documents Department
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