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in subjects: "Protective Clothing"  
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Chemistry research and development. Progress report, December 1978-May 1979. [Component, pilot plant, instrumentation]

Description: Progress and activities are reported on component development, pilot plant development, and instrumentation and statistical systems. Specific items studied include processing of pond sludge, transport of radioactive materials and wastes, corrosion, decontamination and cleaning, fluidized-bed incineration, Pu contamination of soils, chemical analysis, radiometric analysis, security. (DLC)
Date: June 30, 1980
Creator: Miner, F. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Tritium protective clothing

Description: Occupational exposures to radiation from tritium received at present nuclear facilities and potential exposures at future fusion reactor facilities demonstrate the need for improved protective clothing. Important areas relating to increased protection factors of tritium protective ventilation suits are discussed. These areas include permeation processes of tritium through materials, various tests of film permeability, selection and availability of suit materials, suit designs, and administrativ… more
Date: June 1, 1979
Creator: Fuller, T. P. & Easterly, C. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Analysis of production reactor response during a postulated Loss-of-River Water event using CONTAIN/SR

Description: This report discusses the CONTAIN/SR computer code, developed at the Savannah River Technology Center and Sandia National Laboratories for Probabilistic Safety Assessment (PSA) applications, which is used to analyze K Reactor plant conditions following a design basis earthquake to assist post-accident recovery planning. The postulated event, a Loss-of-River Water (LORW) accident, requires analysis of the K Reactor confinement system assuming seismic event-caused loss of forced air flow through … more
Date: June 1, 1992
Creator: O'Kula, K.R.; Wooten, L.A. (Westinghouse Savannah River Co., Aiken, SC (United States)) & Jenkins, T.B. (Concord Associates, Inc., Knoxville, TN (United States))
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Improved airline-type supplied-air plastic suit. [For personnel protection against inhalation of airborne plutonium and tritium]

Description: Two piece supplied-air plastic suits are used extensively at the Savannah River Plant for personnel protection against inhalation of airborne plutonium and tritium. Worker comfort and noise level problems gave impetus to development of an improved suit and aid distribution system. The resulting plastic suit and development work are discussed. The plastic suit unit cost is less than $20, the hearing zone noise level is less than 75 dBA, protection factors exceed 10,000, and user comfort is appro… more
Date: June 1, 1978
Creator: Jolley, L. Jr.; Zippler, D. B.; Cofer, C. H. & Harper, J. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

A Multi-Methods Approach to HRA and Human Performance Modeling: A Field Assessment

Description: The Advanced Test Reactor (ATR) is a research reactor at the Idaho National Laboratory is primarily designed and used to test materials to be used in other, larger-scale and prototype reactors. The reactor offers various specialized systems and allows certain experiments to be run at their own temperature and pressure. The ATR Canal temporarily stores completed experiments and used fuel. It also has facilities to conduct underwater operations such as experiment examination or removal. In review… more
Date: June 1, 2012
Creator: Hugo, Jacques & Gertman, David I
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Health and Safety Plan for Operations Performed for the Environmental Restoration Program: Task, Characterization of Potential Waste Sources at Auxiliary Reactor Area-1 Operable Unit 5--07 site ARA-02

Description: This document constitutes the generic health and safety plan for the Environmental Restoration Program (ERP). It addresses the health and safety requirements of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA); Occupational Safety and Health Administration (OSHA) 29 CFR 1910.120 standard; and EG&G Idaho, Inc. This plan is a guide to individuals who must complete a health and safety plan for a task performed for the ERP. It contains a task specific addendum that… more
Date: June 1, 1992
Creator: Pickett, S. L. & Morton, S. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Evaluation of nuclear facility decommissioning projects: Summary status report: Three Mile Island Unit 2. Radioactive waste and laundry shipments

Description: This document summarizes information concerning radioactive waste and laundry shipments from the Three Mile Island Nuclear Station Unit 2 to radioactive waste disposal sites and to protective clothing decontamination facilities (laundries) since the loss of coolant accident experienced on March 28, 1979. Data were collected from radioactive shipment records, summarized, and placed in a computerized data information retrieval/manipulation system which permits extraction of specific information. … more
Date: June 1, 1988
Creator: Doerge, D. H. & Haffner, D. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Health and Safety Plan for Operations Performed for the Environmental Restoration Program: Task, Characterization of Potential Waste Sources at Auxiliary Reactor Area-1 Operable Unit 5--07 site ARA-02

Description: This document constitutes the generic health and safety plan for the Environmental Restoration Program (ERP). It addresses the health and safety requirements of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA); Occupational Safety and Health Administration (OSHA) 29 CFR 1910.120 standard; and EG G Idaho, Inc. This plan is a guide to individuals who must complete a health and safety plan for a task performed for the ERP. It contains a task specific addendum that… more
Date: June 1, 1992
Creator: Pickett, S. L. & Morton, S. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Analysis of production reactor response during a postulated Loss-of-River Water event using CONTAIN/SR

Description: This report discusses the CONTAIN/SR computer code, developed at the Savannah River Technology Center and Sandia National Laboratories for Probabilistic Safety Assessment (PSA) applications, which is used to analyze K Reactor plant conditions following a design basis earthquake to assist post-accident recovery planning. The postulated event, a Loss-of-River Water (LORW) accident, requires analysis of the K Reactor confinement system assuming seismic event-caused loss of forced air flow through … more
Date: June 1, 1992
Creator: O`Kula, K. R.; Wooten, L. A. & Jenkins, T. B.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

SITE GENERATED RADIOLOGICAL WASTE HANDLING SYSTEM DESCRIPTION DOCUMENT

Description: The Site Generated Radiological Waste Handling System handles radioactive waste products that are generated at the geologic repository operations area. The waste is collected, treated if required, packaged for shipment, and shipped to a disposal site. Waste streams include low-level waste (LLW) in solid and liquid forms, as-well-as mixed waste that contains hazardous and radioactive constituents. Liquid LLW is segregated into two streams, non-recyclable and recyclable. The non-recyclable stream… more
Date: June 20, 2000
Creator: Khamankar, S. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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