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in subjects: "Radioactive Materials"

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Experience base for Radioactive Waste Thermal Processing Systems: A preliminary survey

In the process of considering thermal technologies for potential treatment of the Idaho National Engineering Laboratory mixed transuranic contaminated wastes, a preliminary survey of the experience base available from Radioactive Waste Thermal Processing Systems is reported. A list of known commercial radioactive waste facilities in the United States and some international thermal treatment facilities are provided. Survey focus is upon the US Department of Energy thermal treatment facilities. A… more

Date: April 1, 1992

Creator: Mayberry, J.; Geimer, R.; Gillins, R.; Steverson, E.M.; Dalton, D. (Science Applications International Corp., Idaho Falls, ID (United States)) & Anderson, G.L. (EG and G Idaho, Inc., Idaho Falls, ID (United States))

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

DWPF waste glass Product Composition Control System

The Defense Waste Processing Facility (DWPF) will be used to blend aqueous radwaste (PHA) with solid radwaste (Sludge) in a waste receipt vessel (the SRAT). The resulting SRAT material is transferred to the SME an there blended with ground glass (Frit) to produce a batch of melter feed slurry. The SME material is passed to a hold tank (the MFT) which is used to continuously feed the DWPF melter. The melter. The melter produces a molten glass wasteform which is poured into stainless steel canist… more

Date: January 1, 1992

Creator: Brown, K.G. & Postles, R.L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

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

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.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Programmable multi-timer for TRU waste analysis applications

A programmable, multiple-function timing module has been developed for use in transuranic (TRU) waste analysis applications at the Idaho National Engineering Laboratory. The Programmable Multi-Timer (PRMT) is an expanded version of a module originally built for accelerator-based active photon interrogation experiments. During the course of the experiments, it became obvious that a more versatile timer was needed to meet several unforeseen requirements. The PRMT was designed to meet the new requ… more

Date: January 1, 1981

Creator: Lawrence, R.S.; Nieschmidt, E.B. & Tsang, F.Y.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Development of a mathematical model of a packed column for benzene removal from salt solutions

A mathematical model of a packed column was developed to describe the removal of benzene from radioactive salt solutions at the Savannah River Site. The model was developed from existing, generalized mass transfer correlations for randomly dumped packing, and the correlations were adapted for structured packing. Thermophysical data specific to the solutions of interest were incorporated into the model. Verification of the code was completed using operating data from stripping columns at other l… more

Date: January 1, 1989

Creator: Georgeton, G.K.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Compatibility testing of vitrified waste forms

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.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Characterization of low-level waste from the industrial sector, and near-term projection of waste volumes and types

A telephone survey of low-level waste generators has been carried out in order to make useful estimates of the volume and nature of the waste which the generators will be shipping for disposal when the compacts and states begin operating new disposal facilities. Emphasis of the survey was on the industrial sector, since there has been little information available on characteristics of industrial LLW. Ten large industrial generators shipping to Richland, ten shipping to Barnwell, and two whose w… more

Date: January 1, 1988

Creator: MacKenzie, D.R.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Evaluation of environmental dosimetry models for applicability to possible radioactive waste repository discharges

This report presents the results of a review of the available codes, for application to the National Waste Terminal Storage (NWTS) Program. Consideration was given to the types of radionuclides which may be of concern, the possible modes of release of these radionuclides and the various pathways by which members of the general public in the vicinity of a terminal storage facility may be exposed to the releases. Results reveal that the types and quantities of radioactive material requiring dispo… more

Date: September 1, 1977

Creator: Mauro, J. J.; Michlewicz, D. & Letizia, A.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Relevance of biotic pathways to the long-term regulation of nuclear waste disposal. A report on Tasks 1 and 2 of Phase I. [Shallow land burial]

The purpose of the work reported here was to evaluate the relevance of biotic transport to the assessment of impacts and licensing of low-level waste disposal sites. Available computer models and their recent applications at low-level waste disposal sites are considered. Biotic transport mechanisms and processes for both terrestrial and aquatic systems are presented with examples from existing waste disposal sites. Following a proposed system for ranking radionuclides by their potential for bio… more

Date: July 1, 1982

Creator: McKenzie, D. H.; Cadwell, L. L.; Cushing, C. E. Jr.; Harty, R.; Kennedy, W. E. Jr.; Simmons, M. A. et al.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Calculations of thermal-reactor spent-fuel nuclide inventories and comparisons with measurements

Comparisons with integral measurements have demonstrated the accuracy of CINDER codes and libraries in calculating aggregate fission-product properties, including neutron absorption, decay power, and decay spectra. CINDER calculations have, alternatively, been used to supplement measured integral data describing fission-product decay power and decay spectra. Because of the incorporation of the extensive actinide library and the use of ENDF/B-V data, it is desirable to compare the inventory of i… more

Date: January 1, 1982

Creator: Wilson, W. B.; LaBauve, R. J. & England, T. R.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Effect of fuel recycling on radioactivity and thermal power of high-level wastes

The radioactivity and thermal power of high-level and plutonium-bearing wastes from the nuclear fuel cycle have been calculated for the years 1975 to 2005 using the rate of generation of such wastes projected for the Generic Environmental Statement on Mixed Oxide Fuel (NUREG-0002). Three modes of fuel recycle are considered: (1) no recycle, (2) uranium recycle, and (3) prompt uranium and plutonium recycle. These cases are compared with a respect to radioactivity and thermal power of the generat… more

Date: October 1, 1977

Creator: Wachter, J.W.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Tritium half-life

Least squares analyses of calorimetric measurements made at Mound Laboratory on two tritide compounds over a period of 18 y were performed to determine the half-life of tritium. A half-life of 12.3232 +- 0.0043 mean solar years was obtained.

Date: December 22, 1977

Creator: Rudy, C. R. & Jordan, K. C.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Interaction of noble-metal fission products with pyrolytic silicon carbide

Fuel particles for the High-Temperature Gas-Cooled Reactor (HTGR) contain layers of pyrolytic carbon and silicon carbide, which act as a miniature pressure vessel and form the primary fission product barrier. Of the many fission products formed during irradiation, the noble metals are of particular interest because they interact significantly with the SiC layer and their concentrations are somewhat higher in the low-enriched uranium fuels currently under consideration. To study fission product-… more

Date: January 1, 1982

Creator: Lauf, R. J. & Braski, D. N.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Waste Isolation Pilot Plant site environmental report for calendar year 1990

The US Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) Operational Environmental Monitoring Plan (OEMP) monitors a comprehensive set of parameters in order to detect any potential environmental impacts and establish baselines for future quantitative environmental impact evaluations. Surface water and groundwater, soil, and biotics are measured for background radiation. Nonradiological environmental monitoring activities include meteorological, air quality, soil properties, and the… more

Date: January 1, 1990

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Response of a glass melter to steam explosion

As part of the safety assessment in the design of the glass melter for large-scale immobilization of high-level radioactive wastes, structural considerations of the containment shell include its dynamic responses to abnormal loading conditions such as that caused by a steam explosion. The postulated steam explosion, conservatively given an energy content equivalent to 13 pounds of TNT, is capable of exerting sudden pressures greater than 300 psi but less than 410 psi on the melter wall. By use … more

Date: January 1, 1984

Creator: Yau, W. F. & Durant, W. S.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Environmental monitoring at major U. S. Energy Research and Development Administration contractor sites: calendar year 1976. Volume 2

The purpose of this compilation is to present, in a central reference document, all of the individual annual reports summarizing the results of the environmental monitoring programs conducted at each of the Energy Research and Development Administration (ERDA) sites having a potential for environmental impact or which release a significant quantity of radioactivity or nonradioactive pollutants. Data on the levels of radioactivity and nonradioactive pollutants in effluents and the environs at ea… more

Date: August 1, 1977

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Microwave separation of organic chemicals from mixed hazardous waste

The feasibility of utilizing the differential heating characteristics of microwave energy (MW) to aid in the chemical extraction and separation process of hazardous organic compounds from mixed hazardous waste, was studied at the INEL. The long-term objective of this work was to identify a practical method of separating or enhancing the separation process of organic hazardous waste components from mixed waste using microwave (MW) frequency radiation. Methods using MW energy for calcination, sol… more

Date: January 1, 1992

Creator: Anderson, A. A. & Albano, R. K.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Facilities evaluation report

The Buried Waste Integrated Demonstration (BWID) is a program of the Department of Energy (DOE) Office of Technology Development whose mission is to evaluate different new and existing technologies and determine how well they address DOE community waste remediation problems. Twenty-three Technical Task Plans (TTPs) have been identified to support this mission during FY-92; 10 of these have identified some support requirements when demonstrations take place. Section 1 of this report describes th… more

Date: April 1, 1992

Creator: Sloan, P.A. & Edinborough, C.R.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Preliminary assessment of tree mortality near F- and H-area seepage basins

A preliminary assessment was conducted to evaluate factors that may have been responsible for the vegetation damage that has occurred in groundwater seeps downslope from the F- and H-area seepage basins. The factors that were considered included altered hydrology, toxicity from hazardous chemical constituents associated with seepage basin operation, and toxicity from non-hazardous constituents associated with basin operation. It was concluded that the observed damage was not likely to have resu… more

Date: January 28, 1988

Creator: Loehle, C & Gladden, J

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Decommissioning of commercial shallow-land burial sites

Estimated costs and safety considerations for decommissioning LLW burial grounds have been evaluated. Calculations are based on a generic burial ground assumed to be located at a western and an eastern site. Decommissioning modes include: (1) site stabilization followed by long-term care of the site; and (2) waste relocation. Site stabilization is estimated to cost from $0.4 million to $7.5 million, depending on the site and the stabilization option chosen. Long-term care is estimated to cost a… more

Date: January 1, 1979

Creator: Murphy, E. S. & Holter, G. M.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Long-term leaching of irradiated spent fuel

Spent Light Water Reactor (LWR) fuel with burnups of 9, 28 and 54 MWd/kg U were leach tested at 25/sup 0/C in deionized water in a Paige apparatus. No discernible differences in leach rates were observed due to burnup. Additionally, the 28 MWd/kg U fuel was IAEA leach tested in five different leachants using the IAEA method. Deionized water gave the highest leach rates and a calcium chloride solution gave the lowest leach rates. An accelerated leaching period was observed during the Paige leach… more

Date: January 1, 1979

Creator: Katayama, Y. B. & Bradley, D. J.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Tritium storage development. Progress report No. 12, April--June 1977. [In metal hydride; polymer impregnated tritiated concrete]

Laboratory work was continued on hydriding of zirconium sponge and rod under varying conditions of temperature (400 to 900/sup 0/C) and pressure (0-1000 torr) to determine optimum conditions for the formation of hydrides with desirable mechanical properties. Titanium sponge and rod were also hydrided for comparison. Zirconium and titanium samples containing tritium were prepared and initial leach data were obtained. Leach rates for zirconium in distilled water ranged from 1.1 x 10/sup -6/ to 4.… more

Date: January 1, 1976

Creator: Colombo, P

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Evaluation of proposed designs for streamflow monitoring structures at waste disposal sites

Design of small surface water monitoring stations associated with waste sites requires an approach that balances several problems. The monitoring site must have a capacity for a wide range of flows, allow accurate measurements over the full performance range, minimize effects from accumulation of contaminated sediments, and minimize costs of construction and operation. Selecting a station design that takes these factors into consideration can be done systematically through use of formal decisio… more

Date: January 1, 1991

Creator: Clapp, R. B.; Borders, D. M.; Tardiff, M. F. & Huff, D. D.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Background radiation from fission pulses

Extensive source terms for beta, gamma, and neutrons following fission pulses are presented in various tabular and graphical forms. Neutron results from a wide range of fissioning nuclides (42) are examined and detailed information is provided for four fuels: /sup 235/U, /sup 238/U, /sup 232/Th, and /sup 239/Pu; these bracket the range of the delayed spectra. Results at several cooling (decay) times are presented. For ..beta../sup -/ and ..gamma.. spectra, only /sup 235/U and /sup 239/Pu result… more

Date: May 1, 1988

Creator: England, T. R.; Arthur, E. D.; Brady, M. C. & LaBauve, R. J.

Item Type: Report

Partner: UNT Libraries Government Documents Department