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Modified Purification System Performance Test. Core 1, Seed 2. Test Results T-641124-A. Section 2

Description: The effectiveness of purification in controlling plant radioactivation rates was determined through comparison of the actual effects produced from plant operation with and without purification. With the purification system in service, there was no appreciable difficulty in maintaining the reactor coolant within reference water specifications. In addition, there was no discernible increase of crud deposition in the coolant system as determined by direct radiation measurements of the purification… more
Date: July 21, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of the radionuclide concentrations in soil and plants from the 1975 terrestrial survey of Bikini and Eneu Islands

Description: In June 1975 a radiological survey was conducted of the terrestrial environment of Bikini and Eneu islands (Bikini Atoll) to evaluate the potential radiation dose to the returning Bikini population. In this report, we present measurements of the radionuclide concentration in soil profiles and in dominant species of edible and nonedible, indicator plants. The use of these data to derive relationships to predict the plant uptake of radionuclides from soil is described. Approximately 620 soil and … more
Date: January 21, 1977
Creator: Colsher, C. S.; Robison, W. L. & Gudiksen, P. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactor safety. Quarterly technical progress report, October--December 1977. [LMFBR]

Description: The objectives of the program are to conduct tests that will characterize the behavior of sodium oxide, fuel, fission product, and other aerosols as they might be generated by various postulated LMFBR accidents; determine by analysis and confirm by experiment the generation and transport of these aerosols with respect to source (location, type, and configuration), for the entire course of events associated with real and hypothetical accident conditions; and conduct tests that will determine the… more
Date: March 21, 1978
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effects of the Maximum Credible Accident Relevant to the Design of the Containment Shell, Experimental Low-Temperature Process Heat Reactor Project

Description: The effects of the maximum credible accident relative to the design of the containment shell are discussed. The maximum credible accident is defined. The thermal and hydraulic effects of the maximum credible accident on the reactor system were analyzed. The extent to which fuelrod cladding will melt was estimated. The amount of energy released from the reactor system by the escaping steam and water and by a possible chemical reaction was calculated along with the corresponding pressure rise ins… more
Date: March 21, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

FLUOR HANFORD DECOMMISSIONING UPDATE

Description: Fluor Hanford is completing D&D of the K East Basin at the U.S. Department of Energy's (DOE's) Hanford Site in southeastern Washington State this spring, with demolition expected to begin in June. Located about 400 yards from the Columbia River, the K East Basin is one of two indoor pools that formerly contained irradiated nuclear fuel, radioactive sludge and tons of contaminated debris. In unique and path-breaking work, workers finished removing the spent fuel from the K Basins in 2004. In… more
Date: April 21, 2008
Creator: MS, GERBER
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Functions of the cask maintenance facility: A white paper

Description: The shipping cask systems are the mobile components of the transportation system, designed to safely transport spent nuclear fuel between different facilities under both normal and accident conditions. The cask system will consist of the heavily shielded cask, the cask transport vehicle (truck trailer or railcar), and any associated ancillary equipment (covers, impact limiters, lifting devices, etc.). The cask and certain parts of the cask system must be operated within the limits imposed by a … more
Date: July 21, 1987
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PJM Controller Testing with Prototypic PJM Nozzle Configuration

Description: The U.S. Department of Energy (DOE) Office of River Protection’s Waste Treatment Plant (WTP) is being designed and built to pre-treat and then vitrify a large portion of the wastes in Hanford’s 177 underground waste storage tanks. The WTP consists of three primary facilities—pretreatment, low-activity waste (LAW) vitrification, and high-level waste (HLW) vitrification. The pretreatment facility will receive waste piped from the Hanford tank farms and separate it into a high-volume, low-activity… more
Date: August 21, 2009
Creator: Bontha, Jagannadha R.; Nigl, Franz; Weier, Dennis R.; Leigh, Richard J.; Johnson, Eric D.; Wilcox, Wayne A. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Report for General Research December 26, 1950 to April 16, 1951 (Supporting Research Volume)

Description: This volume presents the quarterly results of that portion of the research and development which is directed towards establishing new techniques and instruments and towards improving present methods for determining levels of radioactivity accurately and safely. The locally developed amplifier of high gain and of wide dynamic range has been shown to provide plateaus suitable for the simultaneous counting of alpha and beta particles. Commercially available amplifiers have failed to exhibit suitab… more
Date: May 21, 1951
Creator: Haring, M. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Colloid-Associated Radionuclide Concentration Limits: ANL

Description: The purpose and scope of this report is to describe the analysis of available colloidal data from waste form corrosion tests at Argonne National Laboratory (ANL) to extract characteristics of these colloids that can be used in modeling their contribution to the source term for sparingly soluble radioelements (e.g., Pu). Specifically, the focus is on developing a useful description of the following waste form colloid characteristics: (1) composition, (2) size distribution, and (3) quantification… more
Date: December 21, 2000
Creator: Mertz, C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nominal Performance Biosphere Dose Conversion Factor Analysis

Description: The purpose of this report was to document the process leading to development of the Biosphere Dose Conversion Factors (BDCFs) for the postclosure nominal performance of the potential repository at Yucca Mountain. BDCF calculations concerned twenty-four radionuclides. This selection included sixteen radionuclides that may be significant nominal performance dose contributors during the compliance period of up to 10,000 years, five additional radionuclides of importance for up to 1 million years … more
Date: December 21, 2000
Creator: Wasiolek, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Award-Winning System Assays Radiation Waste With Radiation

Description: More than half a million drums of radioactive waste are stored at 30 Department of Energy sites across the nation, with thousands more to come as facilities at weapons complex sites are dismantled. All of these drums must be assayed to determine and verify their contents and levels of radioactivity so they can be transported for permanent storage or disposal. A system that assays containers of radioactive waste safely, accurately, and nonintrusively has garnered a prestigious R and D 100 Award-… more
Date: August 21, 2000
Creator: Roberson, G. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Analysis of Radionuclide Migration through a 200-m Vadose Zone Following a 16-year Infiltration Event

Description: The CAMBRIC nuclear test was conducted beneath Frenchman Flat at the Nevada Test Site on May 14, 1965. The nuclear device was emplaced in heterogeneous alluvium, approximately 70 m beneath the ambient water table, which is itself 220 m beneath the ground surface. Approximately 10 years later, groundwater adjacent to the test was pumped steadily for 16 years to elicit information on the migration of residual radionuclide migration through the saturated zone. The pumping well effluent--containing… more
Date: September 21, 2004
Creator: Tompson, A. B.; Hudson, G. B.; Smith, D. K. & Hunt, J. R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

WRPS MEETING THE CHALLENGE OF TANK WASTE

Description: Washington River Protection Solutions (WRPS) is the Hanford tank operations contractor, charged with managing one of the most challenging environmental cleanup projects in the nation. The U.S. Department of Energy hired WRPS to manage 56 million gallons of high-level radioactive waste stored in 177 underground tanks. The waste is the legacy of 45 years of plutonium production for the U. S. nuclear arsenal. WRPS mission is three-fold: safely manage the waste until it can be processed and immobil… more
Date: February 21, 2012
Creator: JC, BRITTON
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Ambient environmental radiation monitoring at the Lawrence Livermore Laboratory

Description: Thermoluminescence dosimetry is the principal means of measuring ambient $gamma$ radiation at the Lawrence Livermore Laboratory. These dosimeters are used at 12 perimeter locations and 41 locations in the off-site vicinity of the Laboratory, and are exchanged quarterly. Control dosimeters are stored in a 75- mm-thick lead shield located out-of-doors to duplicate temperature cycling of field dosimeters. Effect of dosimeter response to radiation in the shield is determined each quarter. Calibrati… more
Date: November 21, 1975
Creator: Lindeken, C.L.; White, J.H.; Toy, A.J. & Sundbeck, C.W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Simplified scheme or radioactive plume calculations

Description: A simplified mathematical scheme to estimate external whole-body $gamma$ radiation exposure rates from gaseous radioactive plumes was developed for the Rio Blanco Gas Field Nuclear Stimulation Experiment. The method enables one to calculate swiftly, in the field, downwind exposure rates knowing the meteorological conditions and $gamma$ radiation exposure rates measured by detectors positioned near the plume source. The method is straightforward and easy to use under field conditions without the… more
Date: November 21, 1976
Creator: Gibson, T. A. & Montan, D. N.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department

Airborne radioactivity survey of portions of the Defiance Uplift and Carrizo Mountains, Apache County, Arizona

Description: Aerial image shows the result of an airborne radioactive survey over an area of 940 square miles in Apache County, Arizona with the approximate location of radioactivity anomalies found. Text describes methods used and discusses the anomalies.
Date: June 21, 1953
Creator: Moxham, Robert Morgan & Johnson, R. W.
Item Type: Refine your search to only Map
Partner: UNT Libraries Government Documents Department
open access

USE OF LIGHT AIRCRAFT FOR SURVEYING FOR RADIOACTIVE GROUND CONTAMINATION

Description: The recent Windscale incident has emphasized the need for available light aircraft and proper instrumentation for aerial surveys following a release of large quantities of airborne radioactive materials. Early tests (1951 and 1955) are reviewed, and the program now in effect at the Oak Ridge National Laboratory is presented. (auth)
Date: May 21, 1958
Creator: Davis, D. M. & Abee, H. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Comparison of gamma-ray exposure rate measurements at Bikini Atoll

Description: A radiological survey of Bikini and Eneu Islands of the Bikini Atoll was conducted during June 1975 to assess the potential radiation doses that may be received by the returning Bikinians. Bikini Atoll was one of the U.S. nuclear weapons testing sites in the Pacific. An integral part of the survey included measurements of the gamma-ray exposure rates at 1 m above the ground with portable NaI instruments at nearly 2700 locations on the two islands. For comparison purposes, similar measurements w… more
Date: November 21, 1975
Creator: Gudiksen, Paul H. & Crites, Thomas R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Characterization of the National Petroleum Reserve No. 3 (NPR-3) Site for Naturally Occurring Radioactive Material(NORM)

Description: The National Petroleum Reserve No. 3 site (NPR-3) near Casper, Wyoming is being prepared for transfer to private industry. Remediation of the NPR-3 site has already begun in anticipation of this transfer. This document describes the characterization of the NPR-3 site for Naturally Occurring Radioactive Materials (NORM). Data generated on radionuclide concentrations and radon emanation may be used to determine disposal options and the need for remediation at this site. A preliminary gamma survey… more
Date: January 21, 1999
Creator: White, G. J. & Rood, A. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Tank 241-T-105, cores 205 and 207 analytical results for the final report

Description: This document is the final laboratory report for tank 241-T-105 push mode core segments collected between June 24, 1997 and June 30, 1997. The segments were subsampled and analyzed in accordance with the {ital Tank Push Mode Core Sampling and Analysis Plan} (TSAP) (Field,1997), the {ital Tank Safety Screening Data Quality Objective} (Safety DQO) (Dukelow, et al., 1995) and {ital Tank 241-T-105 Sample Analysis} (memo) (Field, 1997a). The analytical results are included in Table 1. None of the su… more
Date: October 21, 1997
Creator: Esch, R.A., Westinghouse Hanford, Richland, WA
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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