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SRE CONTROL ROD SHIELDING REQUIREMENTS

Description: Data taken on radiation traverse of the Mark 1 control rod were analyzed. Future radiation levels for all SRE control and safety rods were predicted from this. The shielding necessary to ship a complete rod and that necessary to protect a person doing maintenance work on these rods were calculated. The unshielded gamma dose rate 1 cm from the surface of the most highly activated portion of the control rod was calculated to be 5.0 x 10/sup 4/ r/hr 14 days after shutdown following an extended pow… more
Date: October 22, 1957
Creator: Whittum, H.O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hazards control progress report No. 58, April-September 1979

Description: Progress is reported on research in the areas of radiation protection and industrial hygiene. Subject areas include: (1) basic computer programs for counting room automation; (2) a computing portable neutron spectrometer; (3) preliminary measurements of the neutron energy response of CR-39 carbonate plastic; (4) effect of high-expansion foam on self-1 contained breathing apparatuses; (5) permeation of organic solvents through glove samples; (6) determining neutron dose rates and 9-to-3 in. sphe… more
Date: February 22, 1980
Creator: Griffith, R.V. (ed.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Collection of CASIM calculations

Description: Monte Carlo calculations of hadronic cascades at Fermilab have usually been done using the code CASIM written by A. Van Ginneken. These calculations are often performed to determine the quantity of shielding required for radiation protection purposes. A number of examples of such calculations have been presented previously. Several years of practical experience have led the author to develop the collection of additional cases included in the present report. These results along with those given … more
Date: October 22, 1982
Creator: Cossairt, J.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Benchmarking of Resrad-Offsite : Transition From Resrad (Onsite) Toresrad-Offsite and Comparison of the Resrad-Offsite Predictions With Peercodes.

Description: The main purpose of this report is to document the benchmarking results and verification of the RESRAD-OFFSITE code as part of the quality assurance requirements of the RESRAD development program. This documentation will enable the U.S. Department of Energy (DOE) and its contractors, and the U.S. Nuclear Regulatory Commission (NRC) and its licensees and other stakeholders to use the quality-assured version of the code to perform dose analysis in a risk-informed and technically defensible manner… more
Date: May 22, 2006
Creator: Yu, C.; Gnanapragasam, E.; Cheng, J. J. & Biwer, B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Multidisciplinary training program to create new breed of radiation monitor: the health and safety technician

Description: A multidiscipline training program established to create a new monitor, theHealth and Safety Technician, is described. The training program includes instruction in fire safety, explosives safety, industrial hygiene, industrial safety, health physics, and general safety practices.
Date: October 22, 1979
Creator: Vance, W.F.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Qualitative risk assessment for the 100-HR-3 groundwater operable unit

Description: This report provides the qualitative risk assessment for the 100-HR-3 operable unit on the Hanford Reservation. 100-HR-3 is a ground water unit. The purpose of the QRA at the 100-HR-3 operable unit is to focus on a predefined set of human and environmental exposure scenarios in order to provides sufficient information that will assist the Tri-Party signatories (Washington State Department of Ecology, EPA and US DOE) in making defensible decisions on the necessity of Interim Remedial Measures. F… more
Date: September 22, 1994
Creator: Vukelich, S. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Report of an air contamination study made in Room 7 in the 222B Building, 200 East Area

Description: As the result of repeated over tolerance monitoring samples taken by H.I. Survey in Room 7 of 2228 Bldg., 200 East Area, an Industrial Hygiene study of the air contamination in this room has been made at the request of the H.I. Area Supervisor. Observations made during the preliminary survey and throughout the study indicate that the ventilation system together with the decontamination operations; slurping operation, Goldberg operation, and certain activities during bench determination of proce… more
Date: June 22, 1950
Creator: Gill, W. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department Monthly Record Report: December 1959

Description: This document details activities of the irradiation processing department during the month of December, 1959. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; Employee Relations Operation; and Financial Operation.
Date: January 22, 1960
Creator: Greninger, A. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nuclear and chemical safety analysis: Purex Plant 1970 thorium campaign

Description: The purpose of this document is to discuss the flowsheet and the related processing equipment with respect to nuclear and chemical safety. The analyses presented are based on equipment utilization and revised piping as outlined in the design criteria. Processing of thorium and uranium-233 in the Purex Plant can be accomplished within currently accepted levels of risk with respect to chemical and nuclear safety if minor instrumentation changes are made. Uranium-233 processing is limited to a rat… more
Date: May 22, 1970
Creator: Boldt, A. L. & Oberg, G. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Investigation into Nanostructured Lanthanum Halides and CeBr{sub 3} for Nuclear Radiation Detection

Description: This slide-show presents work on radiation detection with nanostructured lanthanum halides and CeBr{sub 3}. The goal is to extend the gamma energy response on both low and high-energy regimes by demonstrating the ability to detect low-energy x-rays and relatively high-energy activation prompt gamma rays simultaneously using the nano-structured lanthanum bromide, lanthanum fluoride, cerium bromide, or other nanocrystal material. Homogeneous and nano structure cases are compared.
Date: June 22, 2011
Creator: Guss, P., Guise, R., Mukhopadhyay, S., Yuan, D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Special Analysis: Radionuclides Screening Analysis for E Area

Description: It was recently discovered that waste being disposed of onsite contained radionuclides that had not been analyzed by the Performance Assessment (PA). These radionuclides had been eliminated from the PA in an earlier screening evaluation because they were not expected to be contained in SRS-generated waste or that received from offsite generators. This Special Analysis (SA) is being prepared to establish the screening criteria and level of evaluation for all radionuclides potentially significant… more
Date: July 22, 2004
Creator: COOK, JAMES
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Princeton Plasma Physics Laboratory Annual Site Environmental Report for Calendar Years 2002 and 2003

Description: This report provides the U.S. Department of Energy (DOE) and the public with information on the level of radioactive and non-radioactive pollutants (if any) that are added to the environment as a result of Princeton Plasma Physics Laboratory's (PPPL) operations. The results of the 2002 and 2003 environmental surveillance and monitoring program for PPPL are presented and discussed. The report also summarizes environmental initiatives, assessments, and programs that were undertaken in 2002 and 20… more
Date: December 22, 2004
Creator: Virginia L. Finley, Editor
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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RELAP5 / MOD3.2 analysis of INSC standard problem INSCSP - R7 : void fraction distribution over RBMK fuel channel height for experiments performed in the ENTEK BM test facility.

Description: The RELAP5/MOD3.2 computer program has been used to analyze a series of tests investigating void fraction distribution over height in RBMK fuel channels performed in Facility BM at the ENTEK. This is RBMK Standard Problem 7 in Joint Project 6, which is the investigation of Computer Code Validation for Transient Analysis of RBMK and VVER Reactors, between the United States and Russian Minatom International Nuclear Safety Centers. The experiment facility and data, RELAP5 nodalization, and results… more
Date: August 22, 2002
Creator: Garner, P. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Supplemental Release Limits for the Directed Reuse of Lead in Shielding Products by the Department of Energy

Description: The DOE National Center of Excellence for Metals Recycle (NMR) proposes to define and implement a complex-wide directed reuse strategy for surplus radiologically impacted lead (Pb) as part of the U.S. Department of Energy's commitment to the safe and cost-effective recycle or reuse of excess materials and equipment across the DOE complex. NMR will, under this proposal, act on behalf of the DOE Office of Environmental Management, Office of Technical Program Integration (specifically EM-22), as t… more
Date: August 22, 2001
Creator: Coleman, R.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hazard Evaluation for Storage of Spent Nuclear Fuel (SNF) Sludge at the Solid Waste Treatment Facility

Description: As part of the Spent Nuclear Fuel (SNF) storage basin clean-up project, sludge that has accumulated in the K Basins due to corrosion of damaged irradiated N Reactor will be loaded into containers and placed in interim storage. The Hanford Site Treatment Complex (T Plant) has been identified as the location where the sludge will be stored until final disposition of the material occurs. Long term storage of sludge from the K Basin fuel storage facilities requires identification and analysis of po… more
Date: August 22, 2000
Creator: SCHULTZ, M.V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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WASTE TREATMENT BUILDING SYSTEM DESCRIPTION DOCUMENT

Description: The Waste Treatment Building System provides the space, layout, structures, and embedded subsystems that support the processing of low-level liquid and solid radioactive waste generated within the Monitored Geologic Repository (MGR). The activities conducted in the Waste Treatment Building include sorting, volume reduction, and packaging of dry waste, and collecting, processing, solidification, and packaging of liquid waste. The Waste Treatment Building System is located on the surface within t… more
Date: June 22, 2000
Creator: Habashi, F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HRP-CP: An evaluation of the design features of blanket processing loop P - 1

Description: The design features and the performance of UO/sub 2/SO/sub 4/ blanket processing Loop P-1 are evaluated from an engineering viewpoint. This unique experiment development loop was operated with pump heating to study the behavior of plutonium in 1.4 M UO/sub 2/SO/sub 4/at 250 deg C and was designed for mixed O/ sub 2/-H/sub 2/ gas pressurization The canned loop and the feed and sampling systems in glove boxes completely contained the plutonium throughout the experimental program. (auth)
Date: October 22, 1958
Creator: Snider, J. W. & Clinton, S. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Irradiation Processing Department, monthly record report, February, 1960

Description: This document details activities of the irradiation processing department at the Hanford Reservation during the month of February, 1960. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operation; Manufacturing Operation; Facilities Engineering Operation; Relations Practices Operation; Financial Operation; and NPR operation.
Date: March 22, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Irradiation Processing Department Monthly Record Report: September 1959

Description: This document details activities of the irradiation processing department during the month of September, 1959. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; Employee Relations Operation; and Financial Operation.
Date: October 22, 1959
Creator: Greninger, A. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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AEC Group Shelter

Description: As a result of atomic shelter tests and field experiments condueted over the past nine years, it has been conclusively shown that shelters provide the only promising means of civilian protection in the event of a nuclear war. Design details are presented for a group shelter to accommodate 100 persons of all age groups and both sexes. The shelter structure is a multiplate corrugated- steel arch set on a concrete slab with end walls of bridge plate sheathing. The entire structure is covered with … more
Date: June 22, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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TART 2000: A Coupled Neutron-Photon, 3-D, Combinatorial Geometry, Time Dependent, Monte Carlo Transport Code

Description: TART2000 is a coupled neutron-photon, 3 Dimensional, combinatorial geometry, time dependent Monte Carlo radiation transport code. This code can run on any modern computer. It is a complete system to assist you with input Preparation, running Monte Carlo calculations, and analysis of output results. TART2000 is also incredibly FAST; if you have used similar codes, you will be amazed at how fast this code is compared to other similar codes. Use of the entire system can save you a great deal of ti… more
Date: November 22, 2000
Creator: Cullen, D.E
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Multi Canister Overpack (MCO) Handling Machine Independent Review of Seismic Structural Analysis

Description: The following separate reports and correspondence pertains to the independent review of the seismic analysis. The original analysis was performed by GEC-Alsthom Engineering Systems Limited (GEC-ESL) under subcontract to Foster-Wheeler Environmental Corporation (FWEC) who was the prime integration contractor to the Spent Nuclear Fuel Project for the Multi-Canister Overpack (MCO) Handling Machine (MHM). The original analysis was performed to the Design Basis Earthquake (DBE) response spectra usin… more
Date: September 22, 2000
Creator: SWENSON, C.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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