Mixed debris treatment at the Idaho National Engineering Laboratory (INEL)

International Nuclear Information System (INIS)

Garcia, E.C.; Porter, C.L.; Wallace, M.T.

1993-01-01

August 18, 1992 the EPA published the final revised treatment standards for hazardous debris, including mixed debris. Whereas previous standards had been concentration based, the revised standards are performance based. Debris must be treated prior to land disposal, using specific technologies from one or more of the following families of debris treatment technologies: Extraction, destruction, or immobilization. Seventeen specific technologies with generic application are discussed in the final rule. The existing capabilities and types of debris at the INEL were evaluated against the debris rule to determine an overall treatment strategy for the INEL. Seven types of debris were identified: Combustible, porous, non-porous, inherently hazardous, HEPA filters, asbestos contaminated, and reactive metals contaminated debris. With the exception of debris contaminated with reactive metals treatment can be achieved utilizing existing facilities coupled with minor modifications

Simion 3D Version 6.0 User`s Manual

Energy Technology Data Exchange (ETDEWEB)

Dahl, D.A.

1995-11-01

The original SIMION was an electrostatic lens analysis and design program developed by D.C. McGilvery at Latrobe University, Bundoora Victoria, Australia, 1977. SIMION for the PC, developed at the Idaho National Engineering Laboratory, shares little more than its name with the original McGilvery version. INEL`s fifth major SIMION release, version 6.0, represents a quantum improvement over previous versions. This C based program can model complex problems using an ion optics workbench that can hold up to 200 2D and/or 3D electrostatic/magnetic potential arrays. Arrays can have up to 10,000,000 points. SIMION 3D`s 32 bit virtual Graphics User Interface provides a highly interactive advanced user environment. All potential arrays are visualized as 3D objects that the user can cut away to inspect ion trajectories and potential energy surfaces. User programs have been greatly extended in versatility and power. A new geometry file option supports the definition of highly complex array geometry. Extensive algorithm modifications have dramatically improved this version`s computational speed and accuracy.

Characterization of INEL compactible wastes, compactor options study, and recommendations

International Nuclear Information System (INIS)

Gillins, R.L.; Larsen, M.M.; Aldrich, W.C.

1986-03-01

This report provides the results of a detailed characterization and evaluation of low-level radioactive waste generated at the Idaho National Engineering Laboratory (INEL) and an evaluation of compactors available commercially. The results of these evaluations formed the basis for a study of compactor options suitable for compacting INEL-generated low-level waste. Seven compactor options were evaluated. A decision analysis performed on the results of the compactor option study and cost analysis showed that a 200-ton box compactor and a 5000-ton box supercompactor were the best options for an INEL compaction facility other than the RWMC. Two compactor locations were considered: WERF and CPP. The WERF location is recommended on the basis of existing facilities to house the compactor and store the waste, the presence of a trained waste-handling staff, and the desirability of maintaining a single location for processing INEL-generated low-level waste

Summary and recommendations of the NRC/INEL Activated Carbon Testing Program

International Nuclear Information System (INIS)

Scarpellino, C.D.; Sill, C.W.

1986-01-01

The Committee on Nuclear Air and Gas Treatment (CONAGT) of the American Society of Mechanical Engineers (ASME) sponsored an interlaboratory testing program, round-robin, of nuclear-grade activated carbon. The results of this round-robin revealed gross differences in penetration of radio-labeled methyl iodide as measured by the various laboratories when using Method A of the ASTM D-3803-79 Standard. These differences prompted the Nuclear Regulatory Commission (NRC) to establish the NRC/INEL Activated Carbon Testing Program to determine the causes of these discrepancies and to provide recommendations that could lead to an accurate and reliable testing procedure that would ensure an adequate method for assessing the capability of activated carbon to remove radioiodine from gas streams within commercial nuclear power plants. The NRC/INEL Activated Carbon Testing Program has conducted formal and informal interlaboratory comparisons to identify problems with the test method and its application and to assess the effectiveness of changes to procedures and equipment voluntarily implemented by commercial laboratories to mitigate the disparity of test results. The results of the first formal NRC/INEL Interlaboratory Comparison (IC) essentially verified the CONAGT round-robin results despite the use of a detailed test protocol. This data indicated that many of the participating laboratories probably had been operating outside the ASTM specifications for relative humidity (RH) and flow. In addition, this process provided information which was used to modify the testing protocol employed for the second NRC/INEL Interlaboratory Comparison (IC-2) to make it more rugged and reliable. These changes to the protocol together with the results of INEL sensitivity testing are the basis for the recommendations presented

Supplemental investigations in support of environmental assessments by the Idaho INEL Oversight Program at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

1992-01-01

This document reports on the status of supplemental investigations in support of environmental assessments by the Idaho INEL Oversight Program at the Idaho National Engineering Laboratory. Included is information on hydrology studies in wells open through large intervals, unsaturated zone contamination and transport processes, surface water-groundwater interactions, regional groundwater flow, and independent testing of air quality data

Decision analysis for INEL hazardous waste storage

Energy Technology Data Exchange (ETDEWEB)

Page, L.A.; Roach, J.A.

1994-01-01

In mid-November 1993, the Idaho National Engineering Laboratory (INEL) Waste Reduction Operations Complex (WROC) Manager requested that the INEL Hazardous Waste Type Manager perform a decision analysis to determine whether or not a new Hazardous Waste Storage Facility (HWSF) was needed to store INEL hazardous waste (HW). In response to this request, a team was formed to perform a decision analysis for recommending the best configuration for storage of INEL HW. Personnel who participated in the decision analysis are listed in Appendix B. The results of the analysis indicate that the existing HWSF is not the best configuration for storage of INEL HW. The analysis detailed in Appendix C concludes that the best HW storage configuration would be to modify and use a portion of the Waste Experimental Reduction Facility (WERF) Waste Storage Building (WWSB), PBF-623 (Alternative 3). This facility was constructed in 1991 to serve as a waste staging facility for WERF incineration. The modifications include an extension of the current Room 105 across the south end of the WWSB and installing heating, ventilation, and bay curbing, which would provide approximately 1,600 ft{sup 2} of isolated HW storage area. Negotiations with the State to discuss aisle space requirements along with modifications to WWSB operating procedures are also necessary. The process to begin utilizing the WWSB for HW storage includes planned closure of the HWSF, modification to the WWSB, and relocation of the HW inventory. The cost to modify the WWSB can be funded by a reallocation of funding currently identified to correct HWSF deficiencies.

Decision analysis for INEL hazardous waste storage

International Nuclear Information System (INIS)

Page, L.A.; Roach, J.A.

1994-01-01

In mid-November 1993, the Idaho National Engineering Laboratory (INEL) Waste Reduction Operations Complex (WROC) Manager requested that the INEL Hazardous Waste Type Manager perform a decision analysis to determine whether or not a new Hazardous Waste Storage Facility (HWSF) was needed to store INEL hazardous waste (HW). In response to this request, a team was formed to perform a decision analysis for recommending the best configuration for storage of INEL HW. Personnel who participated in the decision analysis are listed in Appendix B. The results of the analysis indicate that the existing HWSF is not the best configuration for storage of INEL HW. The analysis detailed in Appendix C concludes that the best HW storage configuration would be to modify and use a portion of the Waste Experimental Reduction Facility (WERF) Waste Storage Building (WWSB), PBF-623 (Alternative 3). This facility was constructed in 1991 to serve as a waste staging facility for WERF incineration. The modifications include an extension of the current Room 105 across the south end of the WWSB and installing heating, ventilation, and bay curbing, which would provide approximately 1,600 ft 2 of isolated HW storage area. Negotiations with the State to discuss aisle space requirements along with modifications to WWSB operating procedures are also necessary. The process to begin utilizing the WWSB for HW storage includes planned closure of the HWSF, modification to the WWSB, and relocation of the HW inventory. The cost to modify the WWSB can be funded by a reallocation of funding currently identified to correct HWSF deficiencies

INEL Waste and Environmental Information Integration Project approach and concepts

International Nuclear Information System (INIS)

Dean, L.A.; Fairbourn, P.J.; Randall, V.C.; Riedesel, A.M.

1994-06-01

The Idaho National Engineering, Laboratory (INEL) Waste and Environmental Information integration Project (IWEIIP) was established in December 1993 to address issues related to INEL waste and environmental information including: Data quality; Data redundancy; Data accessibility; Data integration. This effort includes existing information, new development, and acquisition activities. Existing information may not be a database record; it may be an entire document (electronic, scanned, or hard-copy), a video clip, or a file cabinet of information. The IWEIIP will implement an effective integrated information framework to manage INEL waste and environmental information as an asset. This will improve data quality, resolve data redundancy, and increase data accessibility; therefore, providing more effective utilization of the dollars spent on waste and environmental information

Remediating the INEL's buried mixed waste tanks

International Nuclear Information System (INIS)

Kuhns, D.J.; Matthern, G.E.; Reese, C.L.

1996-01-01

The Idaho National Engineering Laboratory (INEL), formerly the National Reactor Testing Station (NRTS), encompasses 890 square miles and is located in southeast Idaho. In 1949, the United States Atomic Energy Commission, now the Department of Energy (DOE), established the NRTS as a site for the building and testing of nuclear facilities. Wastes generated during the building and testing of these nuclear facilities were disposed within the boundaries of the site. These mixed wastes, containing radionuclides and hazardous materials, were often stored in underground tanks for future disposal. The INEL has 11 buried mixed waste storage tanks regulated under the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) ranging in size from 400 to 50,000 gallons. These tanks are constructed of either stainless or carbon steel and are located at 3 distinct geographic locations across the INEL. These tanks have been grouped based on their similarities in an effort to save money and decrease the time required to complete the necessary remediation. Environmental Restoration and Technology Development personnel are teaming in an effort to address the remediation problem systematically

The Stored Waste Examination Pilot Plant program at the INEL

International Nuclear Information System (INIS)

McKinley, K.B.; Anderson, B.C.; Clements, T.L.; Hinckley, J.P.; Mayberry, J.L.; Smith, T.H.

1983-01-01

Since 1970, defense transuranic waste has been placed into 20-year retrievable storage at the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory (INEL). A major objective of the U.S. Department of Energy (DOE) Nuclear Waste Management Program is to remove all retrievably stored transuranic waste from the INEL. The January 1981 DOE Record of Decision on the Waste Isolation Pilot Plant (WIPP) stated, ''The WIPP facility will dispose of defense transuranic waste stored retrievably at the Idaho National Engineering Laboratory.'' After retrieval and before shipment, processing may be necessary to prepare the waste for acceptance, handling, and enhanced long-term isolation in the WIPP. However, some of the waste is certifiable to the WIPP waste acceptance criteria without container opening or waste processing. To minimize costs, the Stored Waste Examination Pilot Plant (SWEPP) is being developed to certify INEL stored transuranic waste without container opening or waste processing. The SWEPP certification concept is based on records assessment, nondestructive examination techniques, assay techniques, health physics examinations, and limited opening of containers at another facility for quality control

INEL test plan for evaluating waste assay systems

International Nuclear Information System (INIS)

Mandler, J.W.; Becker, G.K.; Harker, Y.D.; Menkhaus, D.E.; Clements, T.L. Jr.

1996-09-01

A test bed is being established at the Idaho National Engineering Laboratory (INEL) Radioactive Waste Management Complex (RWMC). These tests are currently focused on mobile or portable radioassay systems. Prior to disposal of TRU waste at the Waste Isolation Pilot Plant (WIPP), radioassay measurements must meet the quality assurance objectives of the TRU Waste Characterization Quality Assurance Program Plan. This test plan provides technology holders with the opportunity to assess radioassay system performance through a three-tiered test program that consists of: (a) evaluations using non-interfering matrices, (b) surrogate drums with contents that resemble the attributes of INEL-specific waste forms, and (c) real waste tests. Qualified sources containing a known mixture and range of radionuclides will be used for the non-interfering and surrogate waste tests. The results of these tests will provide technology holders with information concerning radioassay system performance and provide the INEL with data useful for making decisions concerning alternative or improved radioassay systems that could support disposal of waste at WIPP

INEL test plan for evaluating waste assay systems

Energy Technology Data Exchange (ETDEWEB)

Mandler, J.W.; Becker, G.K.; Harker, Y.D.; Menkhaus, D.E.; Clements, T.L. Jr.

1996-09-01

A test bed is being established at the Idaho National Engineering Laboratory (INEL) Radioactive Waste Management Complex (RWMC). These tests are currently focused on mobile or portable radioassay systems. Prior to disposal of TRU waste at the Waste Isolation Pilot Plant (WIPP), radioassay measurements must meet the quality assurance objectives of the TRU Waste Characterization Quality Assurance Program Plan. This test plan provides technology holders with the opportunity to assess radioassay system performance through a three-tiered test program that consists of: (a) evaluations using non-interfering matrices, (b) surrogate drums with contents that resemble the attributes of INEL-specific waste forms, and (c) real waste tests. Qualified sources containing a known mixture and range of radionuclides will be used for the non-interfering and surrogate waste tests. The results of these tests will provide technology holders with information concerning radioassay system performance and provide the INEL with data useful for making decisions concerning alternative or improved radioassay systems that could support disposal of waste at WIPP.

User's and reference guide to the INEL RML/analytical radiochemistry sample tracking database version 1.00

International Nuclear Information System (INIS)

Femec, D.A.

1995-09-01

This report discusses the sample tracking database in use at the Idaho National Engineering Laboratory (INEL) by the Radiation Measurements Laboratory (RML) and Analytical Radiochemistry. The database was designed in-house to meet the specific needs of the RML and Analytical Radiochemistry. The report consists of two parts, a user's guide and a reference guide. The user's guide presents some of the fundamentals needed by anyone who will be using the database via its user interface. The reference guide describes the design of both the database and the user interface. Briefly mentioned in the reference guide are the code-generating tools, CREATE-SCHEMA and BUILD-SCREEN, written to automatically generate code for the database and its user interface. The appendices contain the input files used by the these tools to create code for the sample tracking database. The output files generated by these tools are also included in the appendices

A User's Guide to the SNF ampersand INEL EIS

International Nuclear Information System (INIS)

1995-01-01

This User's Guide is intended to help you find information in the SNF and INEL EIS (that's short for US Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Final Environmental Impact Statement). The first section of this Guide gives you a brief overview of the SNF ampersand INEL EIS., The second section is organized to help you find specific information in the Environmental Impact Statement -- whether you're interested in a management alternative, a particular site (such as Hanford), or a discipline (such as land use or water quality)

INEL BNCT Program: Volume 5, No. 9

Energy Technology Data Exchange (ETDEWEB)

Ackermann, A.L. (ed.)

1991-01-01

This Bulletin presents a summary of accomplishments and highlights of the Idaho National Engineering Laboratory's (INEL) Boron Neutron Capture Therapy (BNCT) Program for September 1991. This bulletin includes information on the brain tumor and melanoma research programs, Power Burst Facility (PBF) technical support and modifications, PBF operations, and updates to the animal data charts.

In situ vitrification engineering-scale test ES-INEL-5 test plan

International Nuclear Information System (INIS)

Stoots, P.R.

1990-06-01

In 1952, the Radioactive Waste Management Complex (RWMC) was established at the Idaho National Engineering Laboratory (INEL). RWMC is located on approximately 144 acres in the southwestern corner of the INEL site and was established as a controlled area for the burial of solid low-level wastes generated by INEL operations. In 1954, the 88-acre Subsurface Disposal Area (SDA) of RWMC began accepting solid transuranic-contaminated waste. From 1954 to 1970, transuranic-contaminated waste was accepted from the Rocky Flats Plant (RFP) near Golden, CO, as well as from other US Department of Energy (DOE) locations. In 1987, the Buried Waste Program (BWP) was established by EG ampersand G Idaho, Inc., the prime contractor at INEL. Following the Environmental Restoration guidelines of the Buried Waste Program, the In Situ Vitrification Program is participating in a Remedial Investigation/Feasibility Study (RI/FS) for permanent disposal of INEL waste, in compliance with the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA). This study was requested and is being funded by the Office of Technology Development of the Idaho Operations Office of DOE (DOE-ID). As part of the RI/FS, an in situ vitrification (ISV) scoping study on the treatability of mixed low-level and mixed transuranic-contaminated waste is being performed to determine applicability of ISV to remediation of waste at SDA. This In Situ Vitrification Engineering-Scale Test ES-INEL-5 Test Plan considers the data needs of engineering, regulatory, health, and safety activities for all sampling and analysis activities in support of engineering scale test ES-INEL-5. 5 refs., 3 figs., 4 tabs

ISDMS, Inel Scientific Data Management System

International Nuclear Information System (INIS)

Bruestle, H.R.; Russell, K.D.; Snider, D.M.; Stewart, H.D.

1993-01-01

Description of program or function: The Idaho National Engineering Laboratory (INEL) Scientific Data Management System, ISDMS, is a generalized scientific data processing system designed to meet the needs of the various organizations at the INEL. It consists of a set of general and specific processors running under the control of an executive processor which serves as the interface between the system and the user. The data requirements at the INEL are primarily for times series analyses. Data acquired at various site facilities are processed on the central CDC CYBER computers. This processing includes: data conversion, data calibration, computed parameter calculations, time series plots, and sundry other applications. The data structure used in ISDMS is CWAF, a common word addressable format. A table driven command language serves as the ISDMS control language. Execution in both batch and interactive mode is possible. All commands and their input arguments are specified in free form. ISDMS is a modular system both at the top executive or MASTER level and in the independent lower or sub-level modules. ISDMS processors were designed and isolated according to their function. This release of ISDMS, identified as 1.3A by the developers, includes processors for data conversion and reformatting for applications programs (e.g. RELAP4), interactive and batch graphics, data analysis, data storage, and archival and development aids

INEL BNCT Program: Volume 5, No. 9. Bulletin, September 1991

Energy Technology Data Exchange (ETDEWEB)

Ackermann, A.L. [ed.

1991-12-31

This Bulletin presents a summary of accomplishments and highlights of the Idaho National Engineering Laboratory`s (INEL) Boron Neutron Capture Therapy (BNCT) Program for September 1991. This bulletin includes information on the brain tumor and melanoma research programs, Power Burst Facility (PBF) technical support and modifications, PBF operations, and updates to the animal data charts.

Processing and certification of defense transuranic waste at the INEL

International Nuclear Information System (INIS)

Clements, T.L. Jr.; Cargo, C.H.; McKinley, K.B.; Smith, T.H.; Anderson, B.C.

1984-01-01

Since 1970, defense-generated transuranic waste has been placed into 20-year retrievable storage at the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory (INEL). A major objective of the US Department of Energy (DOE) Nuclear Waste Management Program is to remove all retrievably stored transuranic waste form the INEL. To support this objective, the Stored Waste Examination Pilot Plant (SWEPP) and the Process Experimental Pilot Plant (PREPP) are currently being constructed. SWEPP will certify waste, using nondestructive examination techniques, for shipment to the Waste Isolation Pilot Plant (WIPP). PREPP will process uncertifiable waste into a certifiable waste form. 3 references

Simplified risk assessment for transporting ATR spent fuel within the INEL

International Nuclear Information System (INIS)

Franklin, E.M.; Courtney, J.C.

1994-01-01

Interest in characterizing the condition of stored spent fuels has generated the need to move spent fuels to hot cell facilities within the Idaho National Engineering Laboratory (INEL). A simplified probabilistic risk assessment (SPRA) and an evaluation of the radiological consequences in the event of an accident are discussed and applied to on-site Advanced Test Reactor (AYR) spent fuel shipments. Reported accident probabilities between 10 -4 and 10 -6 and low radiological consequences, affords this, and other spent fuel characterization efforts, an additional option to move spent fuels within the INEL

1990 INEL national emission standards for hazardous air pollutants

International Nuclear Information System (INIS)

1990-05-01

The Environmental Protection Agency issued on December 15, 1989 final rules governing air emissions of radionuclides. Requirements concerning radionuclide emissions from Department of Energy Facilities are addressed under Title 40, Code Federal Regulations (CFR) 61, Subpart H, ''National Emission Standards for Emissions of Radionuclides other Than Radon From Department of Energy Facilities.'' Section 61.94 of the regulations require that each DOE facility submit on an annual basis a report documenting compliance with the Subpart H requirements. This report addresses the section 61.94 reporting requirements for operations at the Idaho National Engineering Laboratory (INEL) for calendar year 1990. The Idaho Operations Office of the Department of Energy is the primary contact concerning NESHAPs compliance at the INEL

TMI-2 core-examination program: INEL facilities-readiness study

International Nuclear Information System (INIS)

McLaughlin, T.B.

1982-09-01

This document is a review of the Idaho National Engineering Laboratory's (INEL) remote handling facilities. Their availability and readiness to conduct examination and analyses of TMI-2 core samples was determined. Examination of these samples require that the facilities be capable of receiving commercial casks, unloading canisters from the casks, opening the canisters, handling the fuel debris and assemblies, and performing various examinations. The documentation that was necessary for the INEL to have before the receipt of the core material was identified. The core information was also required for input to these documents. The costs, schedules, and a preliminary-project plan are presented for the tasks which are identified as prerequisites to the receipt of the first core sample

Using the INEL site-specific plan as a community relations tool

International Nuclear Information System (INIS)

Hart, Michael; Macdonald, Don; Couch, Brad; Reuel Smith, M.

1992-01-01

Idaho National Engineering Laboratory (INEL) activities have affected, or have the potential to affect the environment. For this reason) the issues surrounding INEL activities are of interest to a broad range of people. The preparation of the INEL Site-Specific Plan (SSP) reflects the U.S. Department of Energy Idaho Field Office's (DOE-ID'S) initiative for open and clear communications with the public. The INEL SSP describes for the public DOE-ID'S plan to clean up inactive facilities and locations that were contaminated due to past waste management practices. It also discusses waste management strategies for avoiding future contamination by active operations. The SSP is an over-arching document and supplies 'the big picture' of environmental restoration and waste management activities to the public, including budget information and long-range plans. DOE-ID has been using the INEL Site-Specific Plan and its associated public comment period as a primary tool for public involvement and as way to get meaningful citizen input into DOE-ID planning. Public involvement in the INBL Site-Specific Plan has four main objectives: To inform public officials, Indian Tribes, interest groups, businesses, and individuals about current plans for environmental restoration and waste management activities at INEL; To ensure that public concerns and interests relating to environmental restoration and waste management are reflected in the SSP and DOE-ID planning; To provide flexibility so modifications can be made to DOE-ID plans and the SSP in response to changing concerns within the community, and; To ensure that DOE-ID and INEL contractors are given feedback regarding public interest in, and concerns about, the DOE-ID'S plans. To carry out these objectives, DOE-ID has implemented an aggressive public outreach effort that provides multiple opportunities for public participation in cleanup and waste management decisions. (author)

Transporting fuel debris from TMI-2 to INEL

International Nuclear Information System (INIS)

Quinn, G.J.; Burton, H.M.; Bixby, W.W.; McIntosh, T.W.; McGoff, O.J.; Barkonic, R.J.; Henrie, J.O.

1986-06-01

Transportation of the damaged fuel from Unit 2 of Three Mile Island (TMI-2) presented noteworthy technical challenges involving complex institutional issues. The program resulted from both a need to package and remove the accident debris and also the opportunity to receive and study damaged core components. These combined to establish the safe transport of the TMI-2 fuel debris as a high priority for many diverse organizations. The capability of the sending and receiving facilities to handle spent fuel transport casks in the most cost-effective manner was assessed and resulted in the development by Nuclear Packaging Inc. (NuPac) of the NuPac 125-B rail cask. This paper reviews the technical challenges in preparation of the TMI-2 core debris for transport from TMI-2 to the Idaho National Engineering Laboratory (INEL) and receipt and storage of that material at INEL. Challenges discussed include design and testing of fuel debris canisters; design, fabrication and licensing of a new rail cask for spent fuel transport; cask loading operations, equipment and facilities at TMI-2; transportation logistics; and, receipt, storage and core examination operations at INEL. 10 refs

The status of soil mapping for the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Olson, G.L.; Lee, R.D.; Jeppesen, D.J.

1995-01-01

This report discusses the production of a revised version of the general soil map of the 2304-km 2 (890-mi 2 ) Idaho National Engineering Laboratory (INEL) site in southeastern Idaho and the production of a geographic information system (GIS) soil map and supporting database. The revised general soil map replaces an INEL soil map produced in 1978 and incorporates the most current information on INEL soils. The general soil map delineates large soil associations based on National Resources Conservation Services [formerly the Soil Conservation Service (SCS)] principles of soil mapping. The GIS map incorporates detailed information that could not be presented on the general soil map and is linked to a database that contains the soil map unit descriptions, surficial geology codes, and other pertinent information

Heat transfer correlation development and assessment: a summary and assessment of return to nucleate boiling phenomena during blowdown tests conducted at the Idaho National Engineering Laboratory (INEL)

International Nuclear Information System (INIS)

Eaton, A.M.; Tolman, E.L.

1979-04-01

The data are presented which were obtained in Loss-of-Coolant Experiments (LOCE) at Idaho National Engineering Laboratory (INEL) which demonstrate the presence of cladding rewetting after the critical heat flux has been exceeded as a viable cooling mechanism during the blowdown phase of a LOCE. A brief review of the mechanisms associated with the boiling crisis and rewetting is also provided. The relevance of INEL LOCE rewetting data to nuclear reactor licensing Evaluation Model Requirements is considered, and the conclusion is made that the elimination of rewetting and return to nucleate boiling (RNB) in Evaluation Models represents a definite conservatism

INEL oversight program. Quarterly technical progress report, January 1993--December 1993

International Nuclear Information System (INIS)

1994-01-01

Idaho's successful lawsuit over shipments of spent nuclear fuel is a major milestone for 1993. The challenge forced the U.S. Department of Energy to cease all shipments of spent nuclear fuel to the Idaho National Engineering Laboratory until a site-wide environmental impact statement is completed. This agreement is a significant victory in Idaho's battle to hold the federal government responsible for its actions and force compliance with applicable laws. Much of the State's INEL-related activity in 1993 focused on ensuring that INEL operations are conducted in a manner that protects public health and the environment

Fifth in situ vitrification engineering-scale test of simulated INEL buried waste sites

International Nuclear Information System (INIS)

Bergsman, T.M.; Shade, J.W.; Farnsworth, R.K.

1992-06-01

In September 1990, an engineering-scale in situ vitrification (ISV) test was conducted on sealed canisters containing a combined mixture of buried waste materials expected to be present at the Idaho National Engineering Laboratory (INEL) Subsurface Disposal Area (SDA). The test was part of a Pacific Northwest Laboratory (PNL) program to assist INEL in treatability studies of the potential application of ISV to mixed transuranic wastes at the INEL SDA. The purpose of this test was to determine the effect of a close-packed layer of sealed containers on ISV processing performance. Specific objectives included determining (1) the effect of releases from sealed containers on hood plenum pressure and temperature, (2) the release pressure ad temperatures of the sealed canisters, (3) the relationships between canister depressurization and melt encapsulation, (4) the resulting glass and soil quality, (5) the potential effects of thermal transport due to a canister layer, (6) the effects on particle entrainment of differing angles of approach for the ISV melt front, and (7) the effects of these canisters on the volatilization of voltatile and semivolatile contaminants into the hood plenum

Idaho National Engineering Laboratory (INEL) Environmental Restoration (ER) Program Baseline Safety Analysis File (BSAF)

International Nuclear Information System (INIS)

1995-09-01

The Baseline Safety Analysis File (BSAF) is a facility safety reference document for the Idaho National Engineering Laboratory (INEL) environmental restoration activities. The BSAF contains information and guidance for safety analysis documentation required by the U.S. Department of Energy (DOE) for environmental restoration (ER) activities, including: Characterization of potentially contaminated sites. Remedial investigations to identify and remedial actions to clean up existing and potential releases from inactive waste sites Decontamination and dismantlement of surplus facilities. The information is INEL-specific and is in the format required by DOE-EM-STD-3009-94, Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports. An author of safety analysis documentation need only write information concerning that activity and refer to BSAF for further information or copy applicable chapters and sections. The information and guidance provided are suitable for: sm-bullet Nuclear facilities (DOE Order 5480-23, Nuclear Safety Analysis Reports) with hazards that meet the Category 3 threshold (DOE-STD-1027-92, Hazard Categorization and Accident Analysis Techniques for Compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports) sm-bullet Radiological facilities (DOE-EM-STD-5502-94, Hazard Baseline Documentation) Nonnuclear facilities (DOE-EM-STD-5502-94) that are classified as open-quotes lowclose quotes hazard facilities (DOE Order 5481.1B, Safety Analysis and Review System). Additionally, the BSAF could be used as an information source for Health and Safety Plans and for Safety Analysis Reports (SARs) for nuclear facilities with hazards equal to or greater than the Category 2 thresholds, or for nonnuclear facilities with open-quotes moderateclose quotes or open-quotes highclose quotes hazard classifications

Idaho National Engineering Laboratory (INEL) Environmental Restoration (ER) Program Baseline Safety Analysis File (BSAF)

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-09-01

The Baseline Safety Analysis File (BSAF) is a facility safety reference document for the Idaho National Engineering Laboratory (INEL) environmental restoration activities. The BSAF contains information and guidance for safety analysis documentation required by the U.S. Department of Energy (DOE) for environmental restoration (ER) activities, including: Characterization of potentially contaminated sites. Remedial investigations to identify and remedial actions to clean up existing and potential releases from inactive waste sites Decontamination and dismantlement of surplus facilities. The information is INEL-specific and is in the format required by DOE-EM-STD-3009-94, Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports. An author of safety analysis documentation need only write information concerning that activity and refer to BSAF for further information or copy applicable chapters and sections. The information and guidance provided are suitable for: {sm_bullet} Nuclear facilities (DOE Order 5480-23, Nuclear Safety Analysis Reports) with hazards that meet the Category 3 threshold (DOE-STD-1027-92, Hazard Categorization and Accident Analysis Techniques for Compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports) {sm_bullet} Radiological facilities (DOE-EM-STD-5502-94, Hazard Baseline Documentation) Nonnuclear facilities (DOE-EM-STD-5502-94) that are classified as {open_quotes}low{close_quotes} hazard facilities (DOE Order 5481.1B, Safety Analysis and Review System). Additionally, the BSAF could be used as an information source for Health and Safety Plans and for Safety Analysis Reports (SARs) for nuclear facilities with hazards equal to or greater than the Category 2 thresholds, or for nonnuclear facilities with {open_quotes}moderate{close_quotes} or {open_quotes}high{close_quotes} hazard classifications.

INEL environmental characterization report. Volume II. Appendices A-D

International Nuclear Information System (INIS)

1984-09-01

This volume contains appendices: (1) a socioeconomic data base for southeastern Idaho; (2) an ecological characterization of the INEL; (3) site-specific climatology summary, NPR primary and alternate sites; (4) NPR site borehole completion; (5) an investigation of the principal lineament at the INEL; (6) an investigation of Clay Butte, Idaho; (7) Arco and Howe fault study; (8) seismology of the INEL; (9) geologic map of the INEL; and (1) geologic ages of the INEL

The INEL Tritium Research Facility

International Nuclear Information System (INIS)

Longhurst, G.R.

1990-01-01

The Tritium Research Facility (TRF) at the Idaho National Engineering Laboratory (INEL) is a small, multi-user facility dedicated to research into processes and phenomena associated with interaction of hydrogen isotopes with other materials. Focusing on bench-scale experiments, the main objectives include resolution of issues related to tritium safety in fusion reactors and the science and technology pertinent to some of those issues. In this report the TRF and many of its capabilities will be described. Work presently or recently underway there will be discussed, and the implications of that work to the development of fusion energy systems will be considered. (orig.)

The INEL Tritium Research Facility

Energy Technology Data Exchange (ETDEWEB)

Longhurst, G.R. (Idaho National Engineering Lab., Idaho Falls (USA))

1990-06-01

The Tritium Research Facility (TRF) at the Idaho National Engineering Laboratory (INEL) is a small, multi-user facility dedicated to research into processes and phenomena associated with interaction of hydrogen isotopes with other materials. Focusing on bench-scale experiments, the main objectives include resolution of issues related to tritium safety in fusion reactors and the science and technology pertinent to some of those issues. In this report the TRF and many of its capabilities will be described. Work presently or recently underway there will be discussed, and the implications of that work to the development of fusion energy systems will be considered. (orig.).

1983 Borah Peak earthquake and INEL structural performance

International Nuclear Information System (INIS)

Gorman, V.W.; Guenzler, R.C.

1983-12-01

At 8:06 a.m. Mountain Daylight Time on October 28, 1983 an earthquake registering 7.3 on the Richter Magnitude scale occurred about 30 km northwest of the town of Mackay, in central Idaho. This report describes the event and associated effects and the responses of facilities at Idaho National Engineering Laboratory (INEL), located approximately 100 km. from the epicenter, to ground motion. 21 references, 36 figures, 5 tables

INEL environmental characterization report. Volume III. Appendices E-H

International Nuclear Information System (INIS)

1984-09-01

This volume contains the following appendices: (1) INEL subsurface hydrology; (2) cultural resources assessment of two study areas on the INEL; (3) description of INEL facilities; and (4) effluent measurements and environmental monitoring programs

Evaluation of seismic criteria used in design of INEL facilities

International Nuclear Information System (INIS)

Young, G.A.

1977-01-01

This report provides the results of an independent evaluation of seismic studies that were made to establish the seismic acceleration levels and the response spectra used in the design of vital facilities at Idaho National Engineering Laboratory. A comparison of the procedures used to define the seismic acceleration values and response spectra at INEL with the requirements of the Nuclear Regulatory Commission showed that additional geologic studies would probably be required in order to fulfill NRC regulations. Recommendations are made on justifiable changes in the acceleration values and response spectra used at INEL. The geologic, geophysical, and seismological studies needed to provide a better understanding of the tectonic processes in the Snake River plains and the surrounding region are identified. Both potential and historical acceleration values are evaluated on a probability basis to permit a risk assessment approach to the design of new facilities and facility modifications. Studies conducted to develop seismic criteria for the design of the Loss of Fluid Test reactor and the New Waste Calcining Facility were selected as typical examples of criteria development previously used in the design of INEL facilities

INEL metal recycle annual report, FY-94

International Nuclear Information System (INIS)

Bechtold, T.E.

1994-09-01

In 1992, the mission of the Idaho Chemical Processing Plant was changed from reprocessing of spent nuclear fuels to development of technologies for conditioning of spent nuclear fuels and other high-level wastes for disposal in a geologic repository. In addition, the Department of Energy (DOE) directed Idaho National Engineering Laboratory (INEL) to develop a program plan addressing the management of radioactive contaminated scrap metal (RSM) within the DOE complex. Based on discussions with the EM-30 organization, the INEL Metal Recycle program plan was developed to address all issues of RSM management. Major options considered for RSM management were engineered interim storage, land disposal as low-level waste, and beneficial reuse/recycle. From its inception, the Metal Recycle program has emphasized avoidance of storage and disposal costs through beneficial reuse of RSM. The Metal Recycle program plan includes three major activities: Site-by-site inventory of RSM resources; validation of technologies for conversion of RSM to usable products; and identification of parties prepared to participate in development of a RSM recycle business

INEL environmental characterization report. Volume I. Summary

International Nuclear Information System (INIS)

1984-09-01

This environmental characterization report contains general information on environmental aspects of the INEL, and specific information on two areas within the INEL which have been tentatively selected for NPR siting. The objective is to present environmental information but not assess environmental impacts. Impacts will be addressed specifically at a later date when an EIS is prepared. The information in this report will be used to evaluate the siting of various reactor types at each of the three reservation alternatives. The report covers geography, physiography, and demography of the INEL, ecology, climatology overview, geology and seismology, hydrology, cultural resources assessment, baseline socioeconomic data, description of INEL facilities and capabilities, effluent and environmental measurements and monitoring programs, exposure pathways, and environmental laws and regulations

INEL/USNRC pipe damping experiments and studies

International Nuclear Information System (INIS)

Ware, A.G.

1987-08-01

Since the previous paper on this subject presented at the 8th SMiRT Conference, the Idaho National Engineering Laboratory (INEL) has conducted further research on piping system damping for the United States Nuclear Regulatory Commission (USNRC). These efforts have included vibration tests on two laboratory piping systems at response frequencies up to 100 Hz, and damping data calculations from both of these two systems and from a third laboratory piping system test series. In addition, a statistical analysis was performed on piping system damping data from tests representative of seismic and hydrodynamic events of greater than minimal excitation. The results of this program will be used to assist regulators in establishing suitable damping values for use in dynamic analyses of nuclear piping systems, and in revising USNRC Regulatory Guide (RG) 1.61

Philosophy and overview of the INEL waste management program

International Nuclear Information System (INIS)

Gertz, C.P.; Whitsett, J.B.; Hamric, J.P.

1986-01-01

The INEL philosophy of ''get the job done; do it right--the first time'' is described as it applies to all phases of waste management activities. In addition, an overview of INEL's waste management programs and projects--low-level waste management operations and technology development; transuranic waste management operations and technology development; high-level waste management operations and technology development; spent fuel storage operations and equipment/technology development; transportation operations, technology development, and prototype cask procurements--are discussed. Emphasis is placed on the application of the INEL philosophy to the successful initiation and continuation of INEL waste management activities

1995 Idaho National Engineering Laboratory (INEL) National Emission Standards for Hazardous Air Pollutants (NESHAPs): Radionuclides. Annual report

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-06-01

Under Section 61.94 of 40 CFR 61, Subpart H (National Emission Standards for Emissions of Radionuclides Other Than Radon From Department of Energy Facilities), each DOE facility must submit an annual report documenting compliance. This report addresses the Section 61.94 reporting requirements for operations at INEL for CY 1995. For that year, airborne radionuclide emissions from INEL operations were calculated to result in a maximum individual dose to a member of the public of 1.80E-02 mrem (1.80E-07 Sievert), well below the 40 CFR 61, Subpart H, regulatory standard of 10 mrem per year (1.0E-04 Sievert per year).

1995 Idaho National Engineering Laboratory (INEL) National Emission Standards for Hazardous Air Pollutants (NESHAPs): Radionuclides. Annual report

International Nuclear Information System (INIS)

1996-06-01

Under Section 61.94 of 40 CFR 61, Subpart H (National Emission Standards for Emissions of Radionuclides Other Than Radon From Department of Energy Facilities), each DOE facility must submit an annual report documenting compliance. This report addresses the Section 61.94 reporting requirements for operations at INEL for CY 1995. For that year, airborne radionuclide emissions from INEL operations were calculated to result in a maximum individual dose to a member of the public of 1.80E-02 mrem (1.80E-07 Sievert), well below the 40 CFR 61, Subpart H, regulatory standard of 10 mrem per year (1.0E-04 Sievert per year)

A document review to characterize Atomic International SNAP fuels shipped to INEL 1966--1973

International Nuclear Information System (INIS)

Wahnschaffe, S.D.; Lords, R.E.; Kneff, D.W.; Nagel, W.E.; Pearlman, H.; Schaubert, V.J.

1995-09-01

This report provides the results of a document search and review study to obtain information on the spent fuels for the following six Nuclear Auxiliary Power (SNAP) reactor cores now stored at the Idaho National Engineering Laboratory (INEL): SNAP-2 Experimental Reactor, SNAP-2 Development Reactor, SNAP-10A Ground Test Reactor, SNAP-8 Experimental Reactor, SNAP-8 Development Reactor, and Shield Test Reactor. The report also covers documentation on SNAP fuel materials from four in-pile materials tests: NAA-82-1, NAA-115-2, NAA-117-1, and NAA-121. Pieces of these fuel materials are also stored at INEL as part of the SNAP fuel shipments

Occupational radiation exposure history of Idaho Field Office Operations at the INEL

International Nuclear Information System (INIS)

Horan, J.R.; Braun, J.B.

1993-10-01

An extensive review has been made of the occupational radiation exposure records of workers at the Idaho National Engineering Laboratory (INEL) over the period of 1951 through 1990. The focus has been on workers employed by contractors and employees of the Idaho Field Operations Office (ID) of the United States Department of Energy (USDOE) and does not include the Naval Reactors Facility (NRF), the Argonne National Laboratory (ANL), or other operations field offices at the INEL. The radiation protection guides have decreased from 15 rem/year to 5 rem/year in 1990 for whole body penetrating radiation exposure. During these 40 years of nuclear operations (in excess of 200,000 man-years of work), a total of twelve individuals involved in four accidents exceeded the annual guidelines for exposure; nine of these exposures were received during life saving efforts on January 3, 1961 following the SL-1 reactor accident which killed three military personnel. These exposures ranged from 8 to 27 rem. Only one individual has exceeded the annual whole body penetrating radiation protection guidelines in the last 29 years

Occupational radiation exposure history of Idaho Field Office Operations at the INEL

Energy Technology Data Exchange (ETDEWEB)

Horan, J.R.; Braun, J.B.

1993-10-01

An extensive review has been made of the occupational radiation exposure records of workers at the Idaho National Engineering Laboratory (INEL) over the period of 1951 through 1990. The focus has been on workers employed by contractors and employees of the Idaho Field Operations Office (ID) of the United States Department of Energy (USDOE) and does not include the Naval Reactors Facility (NRF), the Argonne National Laboratory (ANL), or other operations field offices at the INEL. The radiation protection guides have decreased from 15 rem/year to 5 rem/year in 1990 for whole body penetrating radiation exposure. During these 40 years of nuclear operations (in excess of 200,000 man-years of work), a total of twelve individuals involved in four accidents exceeded the annual guidelines for exposure; nine of these exposures were received during life saving efforts on January 3, 1961 following the SL-1 reactor accident which killed three military personnel. These exposures ranged from 8 to 27 rem. Only one individual has exceeded the annual whole body penetrating radiation protection guidelines in the last 29 years.

INEL studies concerning solidification of low-level waste in cement

International Nuclear Information System (INIS)

Mandler, J.W.

1989-01-01

The Idaho National Engineering Laboratory (INEL) has performed numerous studies addressing issues concerning the solidification of low-level radioactive waste in cement. These studies have been performed for both the Nuclear Regulatory Commission (NRC) and the Department of Energy (DOE). This short presentation will only outline the major topics addressed in some of these studies, present a few conclusions, and identify some of the technical concerns we have. More details of the work and pertinent results will be given in the Working Group sessions. The topics that have been addressed at the INEL which are relevant to this Workshop include (1) solidification of ion-exchange resins and evaporator waste in cement at commercial nuclear power plants, (2) leachability and compressive strength of power plant waste solidified in cement, (3) suggested guidelines for preparation of a solid waste process control program (PCP), (4) cement solidification of EPICOR-II resin wastes, and (5) performance testing of cement-solidified EPICOR-II resin wastes

TMI-2 fuel canister interface requirements for INEL. Revision 1

International Nuclear Information System (INIS)

Wilkins, D.E.; Martz, D.E.; Reno, H.W.

1984-06-01

This report focuses on fuel canister interface requirements at INEL which should be incorporated into the canister design criteria. The requirements will ensure compatibility with existing INEL structures and equipment to be used for receipt, unloading, and storage of fuel canisters. INEL can and does receive and store radioactive materials in many different forms, including reactor fuel. INEL requires detailed descriptions of canisters and casks. Therefore, requirements listed represent engineering design features which will simplify the handling and storage operations; consequently, they are not to be viewed as absolute or non-negotiable. However, the core acquisition contract was negotiated with certain storage assumptions which effect costs of storage. Deviations from those assumptions which significantly effect costs would require approval by DOE-Idaho. If some stated requirements are too restrictive, modifications based on sound engineering principles may be negotiated with INEL. 11 figures

Treatability studies for polyethylene encapsulation of INEL low-level mixed wastes. Final report

International Nuclear Information System (INIS)

Lageraaen, P.R.; Patel, B.R.; Kalb, P.D.; Adams, J.W.

1995-10-01

Treatability studies for polyethylene encapsulation of Idaho National Engineering Laboratory (INEL) low-level mixed wastes were conducted at Brookhaven National Laboratory. The treatability work, which included thermal screening and/or processibility testing, was performed on priority candidate wastes identified by INEL to determine the applicability of polyethylene encapsulation for the solidification and stabilization of these mixed wastes. The candidate wastes selected for this preliminary study were Eutectic Salts, Ion Exchange Resins, Activated Carbons, Freon Contaminated Rags, TAN TURCO Decon 4502, ICPP Sodium Bearing Liquid Waste, and HTRE-3 Acid Spill Clean-up. Thermal screening was conducted for some of these wastes to determine the thermal stability of the wastes under expected pretreatment and processing conditions. Processibility testing to determine whether the wastes were amenable to extrusion processing included monitoring feed consistency, extruder output consistency, waste production homogeneity, and waste form performance. Processing parameters were not optimized within the scope of this study. However, based on the treatability results, polyethylene encapsulation does appear applicable as a primary or secondary treatment for most of these wastes

Technical issues associated with in situ vitrification of the INEL Subsurface Disposal Area

International Nuclear Information System (INIS)

Stoots, C.M.; Bates, S.O.; Callow, R.A.; Campbell, K.A.; Farnsworth, R.K.; Gratson, G.K.; McKellar, M.G.; Nickelson, D.F.; Slater, C.E.

1991-12-01

In situ vitrification (ISV) has been identified as an alternative technology for remediation of the Acid Pit and Transuranic Pits and Trenches (TRU-PTs) that are present at the Idaho National Engineering Laboratory (INEL) Subsurface Disposal Area (SDA). However, a number of technical issues exist that must be resolved before ISV can be considered applicable to these waste sites. To assist in the ISV technology evaluation, an ISV Steering Committee was formed to identify, prioritize, and develop closure roadmaps for technical issues associated with ISV application at the INEL SDA. The activities of the ISV Steering Committee are summarized in three volumes of this report. This document, Volume 1, identifies the systematic approach used to identify and prioritize the ISV technical issues, and briefly discusses the methodology that will be employed to resolve these issues

Mixed debris treatment at the Idaho National Engineering Laboratory (INEL)

International Nuclear Information System (INIS)

Garcia, E.C.; Porter, C.L.; Wallace, M.T.

1993-01-01

August 18, 1992 the Environmental Protection Agency (EPA) published the final revised treatment standards for hazardous debris, including mixed debris. (1) Whereas previous standards had been concentration based, the revised standards are performance based. Debris must be treated prior to land disposal, using specific technologies from one or more of the following families of debris treatment technologies: Extraction, destruction, or immobilization. Seventeen specific technologies with generic application are discussed in the final rule. The existing capabilities and types of debris at the INEL were scrubbed against the debris rule to determine an overall treatment strategy. Seven types of debris were identified: combustible, porous, non-porous, inherently hazardous, HEPA filters, asbestos contaminated, and reactive metals contaminated debris. With the exception of debris contaminated with reactive metals treatment can be achieved utilizing existing facilities coupled with minor modifications

Criticality safety for TMI-2 canister storage at INEL

International Nuclear Information System (INIS)

Jones, R.R.; Briggs, J.B.; Ayers, A.L. Jr.

1986-01-01

Canisters containing Three Mile Island Unit 2 (TMI-2) core debris will be researched, stored, and prepared for final disposition at the Idaho National Engineering Laboratory (INEL). The canisters will be placed into storage modules and assembled into a storage rack, which will be located in the Test Area North (TAN) storage pool. Criticality safety calculations were made (a) to ensure that the storage rack is safe for both normal and accident conditions and (b) to determine the effects of degradation of construction materials (Boraflex and polyethylene) on criticality safety

INEL integrated spent nuclear fuel consolidation task team report

International Nuclear Information System (INIS)

Henry, R.N.; Clark, J.H.; Chipman, N.A.

1994-01-01

This document describes a draft plan and schedule to consolidate spent nuclear fuel (SNF) and special nuclear material (SNW) from aging storage facilities throughout the Idaho National Engineering Laboratory (INEL) to the Idaho Chemical Processing Plant (ICPP) in a safe, cost-effective, and expedient manner. A fully integrated and resource-loaded schedule was developed to achieve consolidation as soon as possible. All of the INEL SNF and SNM management task, projects, and related activities from fiscal year 1994 to the end of the consolidation period are logic-tied and integrated with each other. The schedule and plan are presented to initiate discussion of their implementation, which is expected to generate alternate concepts that can be evaluated using the methodology described in this report. Three perturbations to consolidating SNF as soon as possible are also explored. If the schedule is executed as proposed, the new and on-going consolidation activities will require about 6 years to complete and about $25.3M of additional funding. Reduced annual operating costs are expected to recover the additional investment in about 6.4 years. The total consolidation program as proposed will cost about $66.8M and require about 6 years to recover via reduced operating costs from retired SNF/SNM storage facilities. Detailed schedules and cost estimates for the Test Reactor Area Materials Test Reactor canal transfers are included as an example of the level of detail that is typical of the entire schedule (see Appendix D). The remaining work packages for each of the INEL SNF consolidation transfers are summarized in this document. Detailed cost and resource information is available upon request for any of the SNF consolidation transfers

Idaho National Engineering Laboratory site development plan

International Nuclear Information System (INIS)

1994-09-01

This plan briefly describes the 20-year outlook for the Idaho National Engineering Laboratory (INEL). Missions, workloads, worker populations, facilities, land, and other resources necessary to fulfill the 20-year site development vision for the INEL are addressed. In addition, the plan examines factors that could enhance or deter new or expanded missions at the INEL. And finally, the plan discusses specific site development issues facing the INEL, possible solutions, resources required to resolve these issues, and the anticipated impacts if these issues remain unresolved

A preliminary evaluation of alternatives for disposal of INEL low-level waste and low-level mixed waste

International Nuclear Information System (INIS)

Smith, T.H.; Roesener, W.S.; Jorgenson-Waters, M.J.

1993-07-01

The Mixed and Low-Level Waste Disposal Facility (MLLWDF) project was established in 1992 by the US Department of Energy Idaho Operations Office to provide enhanced disposal capabilities for Idaho National Engineering Laboratory (INEL) low-level mixed waste and low-level waste. This Preliminary Evaluation of Alternatives for Disposal of INEL Low-Level Waste and Low-Level Mixed Waste identifies and evaluates-on a preliminary, overview basis-the alternatives for disposal of that waste. Five disposal alternatives, ranging from of no-action'' to constructing and operating the MLLWDF, are identified and evaluated. Several subalternatives are formulated within the MLLWDF alternative. The subalternatives involve various disposal technologies as well as various scenarios related to the waste volumes and waste forms to be received for disposal. The evaluations include qualitative comparisons of the projected isolation performance for each alternative, and facility, health and safety, environmental, institutional, schedule, and rough order-of-magnitude life-cycle cost comparisons. The performance of each alternative is evaluated against lists of ''musts'' and ''wants.'' Also included is a discussion of other key considerations for decisionmaking. The analysis of results indicated further study is necessary to obtain the best estimate of long-term future waste volume and characteristics from the INEL Environmental Restoration activities and the expanded INEL Decontamination and Decommissioning Program

INEL BNCT Research Program annual report 1994

International Nuclear Information System (INIS)

Venhuizen, J.R.

1995-11-01

This report is a summary of the progress and research produced for the Idaho National Engineering Laboratory (INEL) Boron Neutron Capture Therapy (BNCT) Research Program for calendar year 1994. Contributions from the principal investigators about their individual projects are included, specifically, chemistry (pituitary tumor studies, boron drug development including liposomes, lipoproteins, and carboranylalanine derivatives), pharmacology (murine screenings, toxicity testing, ICP-AES analysis of biological samples), physics (treatment planning software, neutron beam and filter design, neutron beam measurement dosimetry), and radiation biology (small and large animal models tissue studies and efficacy studies). Information on the potential toxicity of BSH and BPA is presented and results of 21 spontaneous tumor bearing dogs that have been treated with BNCT at Brookhaven National Laboratory (BNL) are discussed. Several boron carrying drugs exhibiting good tumor uptake are described. Significant progress in the potential of treating pituitary tumors is presented. Highlights from the First International Workshop on Accelerator-Based Neutron Sources for BNCT are included

Sampling and instrumentation requirements for long-range D and D activities at INEL

International Nuclear Information System (INIS)

Ahlquist, A.J.

1985-01-01

Assistance was requested to help determine sampling and instrumentation requirements for the long-range decontamination and decommissioning activities at the Idaho National Engineering Laboratory. Through a combination of literature review, visits to other DOE contractors, and a determination of the needs for the INEL program, a draft report has been prepared that is now under review. The final report should be completed in FY 84

Conversion tool for the LWR transient analysis code RELAP5 from the CDC version to the FACOM version

International Nuclear Information System (INIS)

Shinozawa, Naohisa; Fujisaki, Masahide; Makino, Mitsuhiro; Kondou, Kazuya; Ishiguro, Misako

1987-01-01

The LWR transient analysis code RELAP5 has been developed on the CDC-CYBER 176 at Idaho National Engineering Laboratory (INEL), the RELAP5 code has been often updated in order to extend the analyzing model and correct the errors. At Japan Atomic Energy Research Institute the code has been converted from the CDC version to the FACOM version and the converted code has been used. The conversion is the task which consumes a lot of time, because the code is large and there is the difference between CDC's machines and FACOM's ones. In order to convert the RELAP5 code automatically, the software tool has been developed. By using this tools the efficiency for converting the RELAP5 code has been improved. Productivity of the conversion is increased about 2.0 to 2.6 times by the tools in comparison with in manual. The procedure of conversion by using the tools and the option parameters of each tool are described. (author)

Air emission inventory for the Idaho National Engineering Laboratory: 1994 emissions report

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-07-01

This report Presents the 1994 update of the Air Emission inventory for the Idaho National Engineering Laboratory (INEL). The INEL Air Emission Inventory documents sources and emissions of non-radionuclide pollutants from operations at the INEL. The report describes the emission inventory process and all of the sources at the INEL, and provides non-radionuclide emissions estimates for stationary sources.

Air emission inventory for the Idaho National Engineering Laboratory: 1994 emissions report

International Nuclear Information System (INIS)

1995-07-01

This report Presents the 1994 update of the Air Emission inventory for the Idaho National Engineering Laboratory (INEL). The INEL Air Emission Inventory documents sources and emissions of non-radionuclide pollutants from operations at the INEL. The report describes the emission inventory process and all of the sources at the INEL, and provides non-radionuclide emissions estimates for stationary sources

Overview of environmental surveillance of waste management activities at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Smith, T.H.; Hedahl, T.G.; Wiersma, G.B.; Chew, E.W.; Mann, L.J.; Pointer, T.F.

1986-02-01

The Idaho National Engineering Laboratory (INEL), in southeastern Idaho, is a principal center for nuclear energy development for the Department of Energy (DOE) and the US Nuclear Navy. Fifty-two reactors have been built at the INEL, with 15 still operable. Extensive environmental surveillance is conducted at the INEL by DOE's Radiological and Environmental Sciences Laboratory (RESL), the US Geological Survey (USGS), the National Oceanic and Atmospheric Administration (NOAA), EG and G Idaho, Inc., and Westinghouse Idaho Nuclear Company (WINCO). Surveillance of waste management facilities is integrated with the overall INEL Site surveillance program. Air, water, soil, biota, and environmental radiation are monitored or sampled routinely at the INEL. Results to date indicate very small or no impacts from the INEL on the surrounding environment. Environmental surveillance activities are currently underway to address key environmental issues at the INEL. 7 refs., 6 figs., 2 tabs

An overview of environmental surveillance of waste management activities at the Idaho National Engineering Laboratory

Science.gov (United States)

Smith, T.H.; Chew, E.W.; Hedahl, T.G.; Mann, L.J.; Pointer, T.F.; Wiersma, G.B.

1986-01-01

The Idaho National Engineering Laboratory (INEL), in southeastern Idaho, is a principal center for nuclear energy development for the Department of Energy (DOE) and the U.S. Nuclear Navy. Fifty-two reactors have been built at the INEL, with 15 still operable. Extensive environmental surveillance is conducted at the INEL by DOE's Radiological Environmental Sciences Laboratory (RESL), and the U.S. Geological Survey (USGS), the National Oceanic and Atmospheric Administration (NOAA), EG&G Idaho, Inc., and Westinghouse Idaho Nuclear Company (WINCO). Surveillance of waste management facilities radiation is integrated with the overall INEL Site surveillance program. Air, warer, soil, biota, and environmental radiation are monitored or sampled routinely at INEL. Results to date indicate very small or no impacts from INEL on the surrounding environment. Environmental surveillance activities are currently underway to address key environmental issues at the INEL.

Math and science education programs from the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

1991-01-01

This booklet reviews math and science education programs at the Idaho National Engineering Laboratory (INEL). The programs can be categorized into six groups: teacher programs; science laboratories for students; student programs; education outreach programs; INEL Public Affairs Office; and programs for college faculty and students

INEL BNCT Research Program, May/June 1992

Energy Technology Data Exchange (ETDEWEB)

Venhuizen, J.R.

1992-09-01

This report presents summaries for two months of current research of the Idaho National Engineering Laboratory (INEL) Boron Neutron Capture Therapy (BNCT) Program. Information is presented on development and murine screening experiments of low-density lipoprotein, carboranyl alanine, and liposome boron containing compounds. Pituitary tumor cell culture studies are described. Drug stability, pharmacology and toxicity evaluation of borocaptate sodium (BSH) and boronophenylaianine (IBPA) are described. Treatment protocol development via the large animal (canine) model studies and physiological response evaluation in rats are discussed. Supporting technology development and technical support activities for boron drug biochemistry and purity, analytical and measurement dosimetry, and noninvasive boron quantification activities are included for the current time period. Current publications for the two months are listed.

INEL BNCT Research Program, September--October 1992

Energy Technology Data Exchange (ETDEWEB)

Venhuizen, J.R.

1992-12-01

This report presents summaries for two months of current research of the Idaho National Engineering Laboratory (INEL) Boron Neutron Capture Therapy (BNCT) Program. Information is presented on development and murine screening experiments of low-density lipoprotain. carboranyl alanine, and liposome boron containing compounds. Pituitary tumor call culture studies are described. Drug stability, pharmacology and toxicity evaluation of borocaptate sodium (BSH) and boronophonylalanine (BPA) are described. Treatment protocol development via the large animal (canine) model studies and physiological response evaluation in rats are discussed. Supporting technology development and technical support activities for boron drug biochemistry and purity, analytical and measurement dosimetry, and noninvasive boron quantification activities are included for the current time period. Current publications for the two months are listed.

INEL BNCT research program, July--August 1992

Energy Technology Data Exchange (ETDEWEB)

Venhuizen, J.R.

1992-10-01

This report presents summaries for two months of current research of the Idaho National Engineering Laboratory (INEL) Boron Neutron Capture Therapy (BNCT) Program. Information is presented on development and murine screening experiments of low-density lipoprotein, carboranyl alanine, and liposome boron containing compounds. Pituitary tumor cell culture studies are described. Drug stability, pharmacology and toxicity evaluation of borocaptate sodium (BSH) and boronophenylalanine (BPA) are described. Treatment protocol development via the large animal (canine) model studies and physiological response evaluation in rats are discussed. Supporting technology development and technical support activities for boron drug biochemistry and purity, analytical and measurement dosimetry, and noninvasive boron quantification activities are included for the current time period. Current publications for the two months are listed.

INEL BNCT Research Program, March/April 1992

Energy Technology Data Exchange (ETDEWEB)

Venhuizen, J.R.

1992-09-01

This report presents summaries for two months of current research for the Idaho National Engineering Laboratory (INEL) Boron Neutron Capture Therapy (BNCT) Program. Information is presented on development and murino screening experiments of low-density lipoprotein, carboranyl alanine, and liposome boron containing compounds. Pituitary tumor call culture studies are described. Drug stability, pharmacology and toxicity evaluation of borocaptate sodium (BSH) and boronopheoylalanine (BPA) are described. Treatment protocol development via the large animal (canine) model studies and physiological response evaluation in rats are discussed. Supporting technology development and technical support activities for boron drug biochemistry and purity, analytical and measurement dosimetry, and noninvasive boron quantification activities are included for the current time period. Current publications for the two months are listed.

INEL BNCT Research Program, September--October 1992

International Nuclear Information System (INIS)

Venhuizen, J.R.

1992-12-01

This report presents summaries for two months of current research of the Idaho National Engineering Laboratory (INEL) Boron Neutron Capture Therapy (BNCT) Program. Information is presented on development and murine screening experiments of low-density lipoprotain. carboranyl alanine, and liposome boron containing compounds. Pituitary tumor call culture studies are described. Drug stability, pharmacology and toxicity evaluation of borocaptate sodium (BSH) and boronophonylalanine (BPA) are described. Treatment protocol development via the large animal (canine) model studies and physiological response evaluation in rats are discussed. Supporting technology development and technical support activities for boron drug biochemistry and purity, analytical and measurement dosimetry, and noninvasive boron quantification activities are included for the current time period. Current publications for the two months are listed

INEL BNCT Research Program, January/February 1993

Energy Technology Data Exchange (ETDEWEB)

Venhuizen, J.R. [ed.

1993-04-01

This report presents summaries for two months of current research of the Idaho National Engineering Laboratory (INEL) Boron Neutron Capture Therapy (BNCT) Program. Information is presented on development and murine screening experiments of low-density lipoprotein, carboranyl alanine, and liposome boron containing compounds. Pituitary tumor cell culture studies are described. Drug stability, pharmacology and toxicity evaluation of borocaptate sodium (BSH) and boronophenylaianine (BPA) are described. Treatment protocol development via the large animal (canine) model studies and physiological response evaluation in rats are discussed. Supporting technology development and technical support activities for boron drug biochemistry and purity, analytical and measurement dosimetry, and noninvasive boron quantification activities are included for the current time period. Current publications for the two months are listed.

INEL BNCT Research Program, January/February 1993

International Nuclear Information System (INIS)

Venhuizen, J.R.

1993-04-01

This report presents summaries for two months of current research of the Idaho National Engineering Laboratory (INEL) Boron Neutron Capture Therapy (BNCT) Program. Information is presented on development and murine screening experiments of low-density lipoprotein, carboranyl alanine, and liposome boron containing compounds. Pituitary tumor cell culture studies are described. Drug stability, pharmacology and toxicity evaluation of borocaptate sodium (BSH) and boronophenylaianine (BPA) are described. Treatment protocol development via the large animal (canine) model studies and physiological response evaluation in rats are discussed. Supporting technology development and technical support activities for boron drug biochemistry and purity, analytical and measurement dosimetry, and noninvasive boron quantification activities are included for the current time period. Current publications for the two months are listed

INEL BNCT Research Program, May/June 1992

International Nuclear Information System (INIS)

Venhuizen, J.R.

1992-09-01

This report presents summaries for two months of current research of the Idaho National Engineering Laboratory (INEL) Boron Neutron Capture Therapy (BNCT) Program. Information is presented on development and murine screening experiments of low-density lipoprotein, carboranyl alanine, and liposome boron containing compounds. Pituitary tumor cell culture studies are described. Drug stability, pharmacology and toxicity evaluation of borocaptate sodium (BSH) and boronophenylaianine (IBPA) are described. Treatment protocol development via the large animal (canine) model studies and physiological response evaluation in rats are discussed. Supporting technology development and technical support activities for boron drug biochemistry and purity, analytical and measurement dosimetry, and noninvasive boron quantification activities are included for the current time period. Current publications for the two months are listed

The proposed INEL intense slow positron source, beam line, and positron microscope facility

International Nuclear Information System (INIS)

Makowitz, H.; Denison, A.B.; Brown, B.

1993-01-01

A program is currently underway at the Idaho National Engineering Laboratory (INEL) to design and construct an Intense Slow Positron Beam Facility with an associated Positron Microscope. Positron beams have been shown to be valuable research tools and have potential application in industrial processing and nondestructive evaluation (microelectronics, etc.). The limit of resolution or overall usefulness of the technique has been limited because of lack of sufficient intensity. The goal of the INEL positron beam is ≥ 10 12 slow e+/s over a 0.03 cm diameter which represents a 10 3 to 10 4 advancement in beam current over existing beam facilities. The INEL is an ideal site for such a facility because of the nuclear reactors capable of producing intense positron sources and the personnel and facilities capable of handling high levels of radioactivity. A design using 58 Co with moderators and remoderators in conjunction with electrostatic positron beam optics has been reached after numerous computer code studies. Proof-of-principle electron tests have demonstrated the feasibility of the large area source focusing optics. The positron microscope development is occurring in conjunction with the University of Michigan positron microscope group. Such a Beam Facility and associated Intense Slow Positron Source (ISPS) can also be utilized for the generation and study of positron, and positron electron plasmas at ≤ 10 14 particles/cm 3 with plasma temperatures ranging from an eV to many keV, as well as an intense x-ray source via positron channeling radiation. The possibility of a tunable x-ray laser based on channeling positron radiation also exists. In this discussion the authors will present a progress report on various activities associated with the INEL ISPS

Environmental surveillance for the INEL Radioactive-Waste-Management complex. Annual report 1981

International Nuclear Information System (INIS)

Janke, D.H.; Zahn, T.P.

1982-09-01

The 1981 environmental surveillance report for the Radioactive Waste Management Complex of the Idaho National Engineering Laboratory contains data and discussions about routine radiological monitoring of the atmospheric, hydrologic, and geologic environments of the RWMC. Additional discussions include results of routine monitoring of two surplus facilities, the Stationary Low-Power Reactor No. 1 Surplus Area and the Organic Moderated Reactor Experiment. Each area has produced localized effects on the environment, but containment is well within the INEL site boundary

Idaho National Engineering Laboratory installation roadmap assumptions document

International Nuclear Information System (INIS)

1993-05-01

This document is a composite of roadmap assumptions developed for the Idaho National Engineering Laboratory (INEL) by the US Department of Energy Idaho Field Office and subcontractor personnel as a key element in the implementation of the Roadmap Methodology for the INEL Site. The development and identification of these assumptions in an important factor in planning basis development and establishes the planning baseline for all subsequent roadmap analysis at the INEL

INEL RCRA [Resource Conservation and Recovery Act] permit for incineration of hazardous waste: Status report

International Nuclear Information System (INIS)

McFee, J.N.; Dalton, J.D.; Bohrer, H.A.

1987-01-01

The Waste Experimental Reduction Facility (WERF) was constructed to reduce the volume of low-level radioactive waste at the Idaho National Engineering Laboratory (INEL). To address the problem of radioactively contaminated ignitable hazardous waste resulting from INEL activities, a development program was carried out to evaluate WERF's ability to meet the regulated criteria for incinerating liquid and solid ignitable waste. Concurrently, INEL submitted its hazardous waste Part B application under the Resource Conservation and Recovery Act (RCRA). As required, and as a major step in the permitting process, the WERF incinerator portion of the permit application included a proposed trial burn, which is a demonstration test of the incinerator's ability to destroy hazardous materials. The trial burn plan was designed to demonstrate the system performance for liquid and solid ignitable wastes at three operating conditions, using a prepared mix of materials representative of waste to be processed. EPA Region X reviewed and commented on the plan prior to the trial burn. Results of the liquid feed trial burn showed a greater than 97% probability of meeting the RCRA-dictated DRE value for chlorinated solvents and a greater than 99% probability for nonchlorinated solvents. Nonchlorinated solid waste results were calculated at a 93% probability of meeting the required DRE, with a 75% probability for chlorinated solid wastes. In addition, the incinerator DRE continued to improve long after the assumed pre-test equilibrium period had ended. The trial burn demonstrates that the WERF incinerator can safely and adequately destroy ignitable hazardous and mixed waste and provides a significant enhancement of the INEL's waste management system

INEL experience and capabilities in design, operation, and maintenance of nuclear systems

International Nuclear Information System (INIS)

Leatham, J.; Masson, L.S.

1982-07-01

This study provides an overview of the experience, hardware, and managerial expertise available at the INEL for design, fabrication, and operation of tools and facilities for remote maintenance. The survey demonstrates that the INEL's fission reactor experience is directly applicable to the design of remote handling hardware which must be developed for fusion reactors, and that the experience and facilities are available at INEL to begin that work

1995 Laboratory-Directed Research and Development Annual report

International Nuclear Information System (INIS)

Cauffman, D.P.; Shoaf, D.L.; Hill, D.A.; Denison, A.B.

1995-01-01

The Laboratory-Directed Research and Development Program (LDRD) is a key component of the discretionary research conducted by Lockheed Idaho Technologies Company (Lockheed Idaho) at the Idaho National Engineering Laboratory (INEL). The threefold purpose and goal of the LDRD program is to maintain the scientific and technical vitality of the INEL, respond to and support new technical opportunities, and enhance the agility and flexibility of the national laboratory and Lockheed Idaho to address the current and future missions of the Department of Energy

1995 Laboratory-Directed Research and Development Annual report

Energy Technology Data Exchange (ETDEWEB)

Cauffman, D.P.; Shoaf, D.L.; Hill, D.A.; Denison, A.B.

1995-12-31

The Laboratory-Directed Research and Development Program (LDRD) is a key component of the discretionary research conducted by Lockheed Idaho Technologies Company (Lockheed Idaho) at the Idaho National Engineering Laboratory (INEL). The threefold purpose and goal of the LDRD program is to maintain the scientific and technical vitality of the INEL, respond to and support new technical opportunities, and enhance the agility and flexibility of the national laboratory and Lockheed Idaho to address the current and future missions of the Department of Energy.

INEL BNCT research program: Annual report, 1995

Energy Technology Data Exchange (ETDEWEB)

Venhuizen, J.R. [ed.

1996-04-01

This report is a summary of the progress and research produced for the Idaho National Engineering Laboratory (INEL) Boron Neutron Capture Therapy (BNCT) Research Program for calendar year 1995. Contributions from the principal investigators about their individual projects are included, specifically, physics (treatment planning software, real-time neutron beam measurement dosimetry), and radiation biology (large animal models efficacy studies). Design of a reactor based epithermal neutron extraction facility is discussed in detail. Final results of boron magnetic resonance imagining is included for both borocaptate sodium (BSH) and boronophenylalanine (BPA) in rats, and BSH in humans. Design of an epithermal neutron facility using electron linear accelerators is presented, including a treatise on energy removal from the beam target. Information on the multiple fraction injection of BSH in rats is presented.

INEL BNCT research program: Annual report, 1995

International Nuclear Information System (INIS)

Venhuizen, J.R.

1996-04-01

This report is a summary of the progress and research produced for the Idaho National Engineering Laboratory (INEL) Boron Neutron Capture Therapy (BNCT) Research Program for calendar year 1995. Contributions from the principal investigators about their individual projects are included, specifically, physics (treatment planning software, real-time neutron beam measurement dosimetry), and radiation biology (large animal models efficacy studies). Design of a reactor based epithermal neutron extraction facility is discussed in detail. Final results of boron magnetic resonance imagining is included for both borocaptate sodium (BSH) and boronophenylalanine (BPA) in rats, and BSH in humans. Design of an epithermal neutron facility using electron linear accelerators is presented, including a treatise on energy removal from the beam target. Information on the multiple fraction injection of BSH in rats is presented

INEL BNCT Research Program annual report 1994

Energy Technology Data Exchange (ETDEWEB)

Venhuizen, J.R. [ed.

1995-11-01

This report is a summary of the progress and research produced for the Idaho National Engineering Laboratory (INEL) Boron Neutron Capture Therapy (BNCT) Research Program for calendar year 1994. Contributions from the principal investigators about their individual projects are included, specifically, chemistry (pituitary tumor studies, boron drug development including liposomes, lipoproteins, and carboranylalanine derivatives), pharmacology (murine screenings, toxicity testing, ICP-AES analysis of biological samples), physics (treatment planning software, neutron beam and filter design, neutron beam measurement dosimetry), and radiation biology (small and large animal models tissue studies and efficacy studies). Information on the potential toxicity of BSH and BPA is presented and results of 21 spontaneous tumor bearing dogs that have been treated with BNCT at Brookhaven National Laboratory (BNL) are discussed. Several boron carrying drugs exhibiting good tumor uptake are described. Significant progress in the potential of treating pituitary tumors is presented. Highlights from the First International Workshop on Accelerator-Based Neutron Sources for BNCT are included. Selected papers have been indexed separately for inclusion in the Energy Science and Technology Database.

The 1988 INEL [Idaho National Engineering Laboratory] microearthquake survey near the western edge of the eastern Snake River Plain

International Nuclear Information System (INIS)

Jackson, S.M.; Anderson, D.M.; Carpenter, G.S.; Gilbert, H.K.; Martin, S.M.; Permann, P.J.

1989-08-01

A network of seventeen analog recording seismograph, spaced approximately 2 km apart, were operated from May to November, 1988 near the western edge of the eastern Snake River Plain (ESRP) to record small magnitude microearthquakes. Two three-component digital seismographs were also installed to record the microearthquake activity for analysis of earthquake source parameters and any regional earthquakes for possible analysis of the localized site and crustal effects of the ESRP on earthquake ground motions. We determined near-surface crustal velocities for this area that were slightly lower than the near-surface crustal velocities presently used in routine locations of events recorded by the INEL Seismic Network from five 100 lb surface blasts. During the survey period, only two earthquakes were located near the network area. One of the events occurred in May and was recorded by four of the portable seismic stations and two of the permanent INEL Seismic Network stations. It had a coda magnitude (M c ) of approximately 0.3. The other event was recorded by seventeen portable analog stations and three of the permanent INEL Seismic Network stations. We located this microearthquake, M c =0.5, about 2 km west of Howe, Idaho, off of the ESRP. We determined an unconstrained focal mechanism for this event, which could be interpreted as normal faulting striking N 44 degree W or strike-slip faulting on a plane striking either N 44 degree W or N 47 degree E. 26 refs., 10 figs., 3 tabs

Summary of INEL research on the iron-enriched basalt waste form

International Nuclear Information System (INIS)

Reimann, G.A.; Grandy, J.D.; Eddy, T.L.; Anderson, G.L.

1992-01-01

This report summarizes the knowledge base on the iron-enriched basalt (IEB) waste form developed at the Idaho National Engineering Laboratory (INEL) during 1979--1982. The results presented discuss the applicability of IEB in converting retrieved transuranic (TRU) waste from INEL's Radioactive Waste Management Complex (RWMC) into a vitreous/ceramic (glassy/rock) stable waste form suitable for permanent disposal in an appropriate repository, such as the Waste Isolation Pilot Plant (WIPP) in New Mexico. Borosilicate glass (BSG), the approved high-level waste form, appears unsuited for this application. Melting the average waste-soil mix from the RWMC produces the IEB composition and attempting to convert IEB to the BSG composition would require additions of substantial B 2 0 3 , Na, and SiO 2 (glass frit). IEB requires processing temperatures of 1400 to 1600 degrees C, depending upon the waste composition. Production of the IEB waste form, using Joule heated melters, has proved difficult in the past because of electrode and refractory corrosion problems associated with the high temperature melts. Higher temperature electric melters (arc and plasma) are available to produce this final waste form. Past research focused on extensive slag property measurements, waste form leachability tests, mechanical, composition, and microstructure evaluations, as well as a host of experiments to improve production of the waste form. Past INEL studies indicated that the IEB glass-ceramic is a material that will accommodate and stabilize a wide range of heterogeneous waste materials, including long lived radionuclides and scrap metals, while maintaining a superior level of chemical and physical performance characteristics. Controlled cooling of the molten IEB and subsequent heat treatment will produce a glass-ceramic waste form with superior leach resistance

Compliance agreements at the INEL: A success story

International Nuclear Information System (INIS)

McBath, W.H.

1995-01-01

The Radioactive Waste Management Complex (RWMC), located at the Idaho National Engineering Laboratory (INEL), is the storage facility for approximately 135,000 containers of radioactive mixed waste that must be stored in accordance with Resource Conservation and Recovery Act (RCRA) requirements. Collectively, the compliance and safety basis documents governing the operation of the storage facility contain approximately 2,500 specific, identifiable requirements. Critical to the compliance with these 2,500 requirements was the development of a process which converted these requirements to a form and format that allowed implementation at the operator level. Additionally, to ensure continued compliance, a method of identifying and controlling implementing documents is imperative. This paper discusses the methods employed to identify, implement, and control these requirements

Evaluation of the graphite electrode DC arc furnace for the treatment of INEL buried wastes

International Nuclear Information System (INIS)

Surma, J.E.; Freeman, C.J.; Powell, T.D.; Cohn, D.R.; Smatlak, D.L.; Thomas, P.; Woskov, P.P.

1993-06-01

The past practices of DOE and its predecessor agencies in burying radioactive and hazardous wastes have left DOE with the responsibility of remediating large volumes of buried wastes and contaminated soils. The Buried Waste Integrated Demonstration (BWID), has chosen to evaluate treatment of buried wastes at the Idaho National Engineering Laboratory (INEL). Because of the characteristics of the buried wastes, the potential for using high-temperature thermal treatment technologies is being evaluated. The soil-waste mixture at INEL, when melted or vitrified, produces a glass/ceramic referred to as iron-enriched basalt (IEB). One potential problem with producing the IEB material is the high melting temperature of the waste and soil (1,400-1,600 degrees C). One technology that has demonstrated capabilities to process high melting point materials is the plasma arc heated furnace. A three-party program was initiated and the program involved testing an engineering-scale DC arc furnace to gain preliminary operational and waste processibility information. It also included the design, fabrication, and evaluation of a second-generation, pilot-scale graphite electrode DC arc furnace. Widely ranging simulants of INEL buried waste were prepared and processed in the Mark I furnace. The tests included melting of soils with metals, sludges, combustibles, and simulated drums. Very promising results in terms of waste product quality, volume reduction, heating efficiency, and operational reliability and versatility were obtained. The results indicate that the graphite electrode DC arc technology would be very well suited for treating high melting point wastes such as those found at INEL. The graphite electrode DC arc furnace has been demonstrated to be very simple, yet effective, with excellent prospects for remote or semi-remote operation

Robotic systems for the high level waste tank farm replacement project at INEL

International Nuclear Information System (INIS)

Berger, A.; White, D.; Thompson, B.; Christensen, M.

1993-01-01

Westinghouse Idaho Nuclear Company (WINCO) is specifying and designing a new high level waste tank farm at the Idaho National Engineering Laboratory (INEL). The farm consists of four underground storage tanks, which replace the existing tanks. The new facility includes provisions for remote operations. One of the planned remote operations is robotic inspection of the tank from the interior and exterior. This paper describes the process used to design the robotic system for the inspection tasks

Air emissions inventory for the Idaho National Engineering Laboratory -- 1995 emissions report

International Nuclear Information System (INIS)

1996-06-01

This report presents the 1995 update of the Air Emission Inventory for the Idaho National Engineering Laboratory (INEL). The INEL Air Emission Inventory documents sources and emissions of non-radionuclide pollutants from operations at the INEL. The report describes the emission inventory process and all of the sources at the INEL, and provides non-radionuclide emissions estimates for stationary sources. The air contaminants reported include nitrogen oxides, sulfur oxides, carbon monoxide, volatile organic compounds, particulates, and hazardous air pollutants (HAPs)

Air emissions inventory for the Idaho National Engineering Laboratory -- 1995 emissions report

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-06-01

This report presents the 1995 update of the Air Emission Inventory for the Idaho National Engineering Laboratory (INEL). The INEL Air Emission Inventory documents sources and emissions of non-radionuclide pollutants from operations at the INEL. The report describes the emission inventory process and all of the sources at the INEL, and provides non-radionuclide emissions estimates for stationary sources. The air contaminants reported include nitrogen oxides, sulfur oxides, carbon monoxide, volatile organic compounds, particulates, and hazardous air pollutants (HAPs).

Nuclear plant analyzer development at INEL

International Nuclear Information System (INIS)

Laats, E.T.; Russell, K.D.; Stewart, H.D.

1983-01-01

The Office of Nuclear Regulatory Research of the US Nuclear Regulatory Commission (NRC) has sponsored development of a software-hardware system called the Nuclear Plant Analyzer (NPA). This paper describes the status of the NPA project at the INEL after one year of development. When completed, the NPA will be an integrated network of analytical tools for performing reactor plant analyses. Development of the NPA in FY-1983 progressed along two parallel pathways; namely, conceptual planning and software development. Regarding NPA planning, and extensive effort was conducted to define the function requirements of the NPA, conceptual design, and hardware needs. Regarding software development conducted in FY-1983, all development was aimed toward demonstrating the basic concept and feasibility of the NPA. Nearly all software was developed and resides on the INEL twin Control Data Corporation 176 mainframe computers

Technical issues associated with in situ vitrification of the INEL Subsurface Disposal Area

International Nuclear Information System (INIS)

Stoots, C.M.; Bates, S.O.; Callow, R.A.; Campbell, K.A.; Farnsworth, R.K.; Gratson, G.K.; McKellar, M.G.; Nickelson, D.F.; Slater, C.E.

1992-01-01

In situ vitrification (ISV) has been identified as an alternative technology for remediation of the Acid Pit and Transuranic Pits and Trenches (TRU-PTs) that are present at the Idaho National Engineering Laboratory (INEL) Subsurface Disposal Area (SDA). However, a number of technical issues exist that must be resolved before ISV can be considered applicable to these waste sites. To assist in the ISV technology evaluation, an ISV Steering Committee was formed to identify, prioritize, and develop closure roadmaps for technical issues associated with ISV application at the INEL SDA. The activities of the ISV Steering Committee are summarized in three volumes of this report. Volume 1 identifies the systematic approach used to identify and prioritize the ISV technical issues, and briefly discusses the methodology that will be employed to resolve these issues. This document Volume 2 and Volume 3 discusses each technical issue in greater detail and suggest specific closure roadmaps to be used in resolving technical issues associated with ISV at the SDA Acid Pit and TRU-PTs, respectively

1986 environmental monitoring program report for the Idaho National Engineering Laboratory Site

International Nuclear Information System (INIS)

Hoff, D.L.; Chew, E.W.; Rope, S.K.

1987-05-01

This report presents onsite and offsite data collected in 1986 for the routine environmental monitoring program conducted by the Radiological and Environmental Sciences Laboratory (RESL) of the Department of Energy (DOE) at the Idaho National Engineering Laboratory (INEL) Site. The purpose of this routine program is to monitor radioactive and nonradioactive materials resulting from INEL Site operations which may reach the surrounding offsite environment and population. This report is prepared in accordance with the DOE requirements in draft DOE Order 5484.1 and is not intended to cover the numerous special environmental research programs being conducted at the INEL by RESL and others

Enhancements to the Idaho National Engineering Laboratory motor-operated valve assessment software

International Nuclear Information System (INIS)

Holbrook, M.R.; Watkins, J.C.

1994-01-01

In January 1991, the U.S. Nuclear Regulatory Commission (USNRC) commenced Part 1 inspections to review licensee's motor-operated valve (MOV) programs that were developed to address Generic Letter 89-10, open-quotes Safety-Related Motor-Operated Valve Testing and Surveillanceclose quotes. In support, of this effort, the Isolation Valve Assessment (IVA) software, Version 3.10, was developed by the Idaho National Engineering Laboratory (INEL) to enable rapid in-depth review of MOV sizing and torque switch setting calculations. In 1994, the USNRC commenced Part 2 inspections, which involve a more in-depth review of MOV in situ testing relative to design-basis assumptions. The purpose of this paper is to describe the latest INEL and industry research that has been incorporated into Version 4.00 of the IVA software to support the latest round of inspections. Major improvements include (a) using dynamic and static test results to determine MOV performance parameters and validate design-basis engineering assumptions, (b) determining the stem/stem-nut coefficient of friction using new research-based techniques, (c) adding the ability to evaluate globe valves, and (d) incorporating new methods to account for the effects of high ambient temperature on the output torque of alternating current (ac) motors

Addition of liquid waste incineration capability to the INEL's low-level waste incinerator

International Nuclear Information System (INIS)

Steverson, E.M.; Clark, D.P.; McFee, J.N.

1986-01-01

A liquid waste system has recently been installed in the Waste Experimental Reduction Facility (WERF) incinerator at the Idaho National Engineering Laboratory (INEL). In this paper, aspects of the incineration system such as the components, operations, capabilities, capital cost, EPA permit requirements, and future plans are discussed. The principal objective of the liquid incineration system is to provide the capability to process hazardous, radioactively contaminated, non-halogenated liquid wastes. The system consists primarily of a waste feed system, instrumentation and controls, and a liquid burner, which were procured at a capital cost of $115,000

TMI-2 [Three Mile Island Nuclear Power Station] fuel canister and core sample handling equipment used in INEL hot cells

International Nuclear Information System (INIS)

McConnell, J.W. Jr.; Shurtliff, W.T.; Lynch, R.J.; Croft, K.M.; Whitmill, L.J.; Allen, S.M.

1987-01-01

This paper describes the specialized remote handling equipment developed and used at the Idaho National Engineering Laboratory (INEL) to handle samples obtained from the core of the damaged Unit 2 reactor at Three Mile Island Nuclear Power Station (TM-2). Samples of the core were removed, placed in TMI-2 fuel canisters, and transported to the INEL. Those samples will be examined as part of the analysis of the TMI-2 accident. The equipment described herein was designed for removing sample materials from the fuel canisters, assisting with initial examination, and processing samples in preparation for detailed examinations. The more complex equipment used microprocessor remote controls with electric motor drives providing the required force and motion capabilities. The remaining components were unpowered and manipulator assisted

Raptors of the Idaho National Engineering Laboratory Site

International Nuclear Information System (INIS)

Craig, T.H.

1979-04-01

From 1974 through 1976 base line data were gathered on the raptors which occur on the Idaho National Engineering Laboratory (INEL) Site. Thirteen species were observed on the INEL Site during the non-breeding seasons. American Rough-legged Hawks, American Kestrels, Golden Eagles, and Prairie Falcons were the most numerous. Marsh Hawks, Ferruginous Hawks, Redtailed Hawks, Swainson's Hawks, Great Horned Owls, Short-eared Owls, Merlins, Cooper's Hawks, the endangered Bald Eagle, and the endangered Peregrine Falcon were all observed on the INEL Site during the nonbreeding seasons although less frequently. American Rough-legged Hawks and American Kestrels were commonly observed in agricultural lands while Prairie Falcons and Golden Eagles were usually seen in areas of native vegetation. Nesting species of raptors on the INEL Site include American Kestrels, and Long-eared Owls. Ferruginous Hawks, Merlins, Prairie Falcons, Red-tailed Hawks, Swainson's Hawks, Golden Eagles, Great Horned Owls, and Burrowing Owls also nest on or near the INEL Site. The nesting ecology of American Kestrels, Long-eared Owls, Prairie Falcons, Red-tailed Hawks, Swainson's Hawks, Golden Eagles, and Great Horned Owls on the INEL Site are summarized in this report. The decline of nesting Ferruginous Hawks, Golden Eagles, and Red-tailed Hawks on and near the INEL Site is discussed

Idaho National Engineering Laboratory: Annual report, 1986

International Nuclear Information System (INIS)

1986-01-01

The INEL underwent a year of transition in 1986. Success with new business initiatives, the prospects of even better things to come, and increased national recognition provided the INEL with a glimpse of its promising and exciting future. Among the highlights were: selection of the INEL as the preferred site for the Special Isotope Separation Facility (SIS); the first shipments of core debris from the Three Mile Island Unit 2 reactor to the INEL; dedication of three new facilities - the Fluorinel Dissolution Process, the Remote Analytical Laboratory, and the Stored Waste Experimental Pilot Plant; groundbreaking for the Fuel Processing Restoration Facility; and the first IR-100 award won by the INEL, given for an innovative machine vision system. The INEL has been assigned project management responsibility for the SDI Office-sponsored Multimegawatt Space Reactor and the Air Force-sponsored Multimegawatt Terrestrial Power Plant Project. New Department of Defense initiatives have been realized in projects involving development of prototype defense electronics systems, materials research, and hazardous waste technology. While some of our major reactor safety research programs have been completed, the INEL continues as a leader in advanced reactor technologies development. In April, successful tests were conducted for the development of the Integral Fast Reactor. Other 1986 highlights included the INEL's increased support to the Office of Civilian Radioactive Waste Management for complying with the Nuclear Waste Policy Act of 1982. Major INEL activities included managing a cask procurement program, demonstrating fuel assembly consolidation, and testing spent fuel storage casks. In addition, the INEL supplied the Tennessee Valley Authority with management and personnel experienced in reactor technology, increased basic research programs at the Idaho Research Center, and made numerous outreach efforts to assist the economies of Idaho communities

Replacement of the Idaho National Engineering Laboratory Health Physics Instrumentation Laboratory

International Nuclear Information System (INIS)

1995-05-01

The DOE-Idaho Operations Office (DOE-ID) has prepared an environmental assessment (EA) on the replacement of the Idaho National Engineering Laboratory Health Physics Instrumentation Laboratory at the Idaho National Engineering Laboratory (INEL). The purpose of this project is to replace the existing Health Physics Instrumentation Laboratory (HPIL) with a new facility to provide a safe environment for maintaining and calibrating radiation detection instruments used at the Idaho National Engineering Laboratory. The existing HPIL facility provides portable health physics monitoring instrumentation and direct reading dosimetry procurement, maintenance and calibration of radiation detection instruments, and research and development support-services to the INEL and others. However, the existing facility was not originally designed for laboratory activities and does not provide an adequate, safe environment for calibration activities. The EA examined the potential environmental impacts of the proposed action and evaluated reasonable alternatives, including the no action alternative in accordance with the Council on Environmental Quality (CEQ) Regulations (40 CFR Parts 1500-1508). Based on the environmental analysis in the attached EA, the proposed action will not have a significant effect on the human environment within the meaning of the National Environmental Policy Act (NEPA) and 40 CFR Parts 1508.18 and 1508.27. The selected action (the proposed alternative) is composed of the following elements, each described or evaluated in the attached EA on the pages referenced. The proposed action is expected to begin in 1997 and will be completed within three years: design and construction of a new facility at the Central Facility Area of the INEL; operation of the facility, including instrument receipt, inspections and repairs, precision testing and calibration, and storage and issuance. The selected action will result in no significant environmental impacts

Development of the environmental management integrated baseline at the Idaho National Engineering Laboratory using systems engineering

International Nuclear Information System (INIS)

Murphy, J.A.; Caliva, R.M.; Wixson, J.R.

1997-01-01

The Idaho National Engineering Laboratory (INEL) is one of many Department of Energy (DOE) national laboratories that has been performing environmental cleanup and stabilization, which was accelerated upon the end of the cold war. In fact, the INEL currently receives two-thirds of its scope to perform these functions. However, the cleanup is a highly interactive system that creates an opportunity for systems engineering methodology to be employed. At the INEL, a group called EM (Environmental Management) Integration has been given this charter along with a small core of systems engineers. This paper discusses the progress to date of converting the INEL legacy system into one that uses the systems engineering discipline as the method to ensure that external requirements are met

Project Management Plan for the INEL technology logic diagrams

International Nuclear Information System (INIS)

Rudin, M.J.

1992-10-01

This Project Management Plan (PjMP) describes the elements of project planning and control that apply to activities outlined in Technical Task Plan (TTP) ID-121117, ''Technology Logic Diagrams For The INEL.'' The work on this project will be conducted by personnel in EG ampersand G Idaho, Inc.'s Waste Technology Development Program. Technology logic diagrams represent a formal methodology to identify technology gaps or needs within Environmental Restoration/Waste Management Operations, which will focus on Office of Environmental Restoration and Waste Management (EM-50) research and development, demonstration, test, and evaluation efforts throughout the US Department of Energy complex. This PjMP describes the objectives, organization, roles and responsibilities, workscope and processes for implementing and managing the technology logic diagram for the Idaho National Engineering Laboratory project

Air Emission Inventory for the Idaho National Engineering Laboratory, 1993 emissions report

International Nuclear Information System (INIS)

1994-06-01

This report presents the 1993 update of the Air Emission Inventory for the Idaho National Engineering Laboratory (INEL). The purpose of the Air Emission Inventory is to commence the preparation of the permit to operate application for the INEL, as required by the recently promulgated Title V regulations of the Clean Air Act. The report describes the emission inventory process and all of the sources at the INEL and provides emissions estimates for both mobile and stationary sources

Air Emission Inventory for the Idaho National Engineering Laboratory, 1993 emissions report

Energy Technology Data Exchange (ETDEWEB)

1994-06-01

This report presents the 1993 update of the Air Emission Inventory for the Idaho National Engineering Laboratory (INEL). The purpose of the Air Emission Inventory is to commence the preparation of the permit to operate application for the INEL, as required by the recently promulgated Title V regulations of the Clean Air Act. The report describes the emission inventory process and all of the sources at the INEL and provides emissions estimates for both mobile and stationary sources.

Vitrifiable concrete for disposal of spent nuclear fuel reprocessing waste at I.N.E.L

International Nuclear Information System (INIS)

Gougar, M.L.D.; Scheetz, B.E.; Siemer, D.D.

1996-01-01

A cement capable of being Hot Isostatically Pressed (HIP'ed) into a glass-ceramic has been proposed for use as the waste form for SNF reprocessing wastes at the Idaho National Engineering Laboratories. Such an ''intermediate'' cement, with a composition based on that of common glasses, has been designed and tested. The cement formulations included mixed I.N.E.L. wastes, blast furnace flag, reactive silica, alumina, and I.N.E.L. soil or vermiculite, which was activated with potassium or sodium hydroxide. Modified FUETAP processing was performed and the cement was subsequently characterized. Results of compressive strength testing ranged from 1,452 psi to 4,163 psi, exceeding the NRC-suggested standard of >500 psi. Total dissolved solids concentrations in waste form leachates were calculated from a static leach test in which leachate conductivity was measured. Effective diffusivities for radioisotopes Cs and Sr were calculated from leachate analysis data. Diffusivity values were on the order of 10 -15 to 10 -10 cm 2 /sec, which compare favorably with diffusivities in other materials

IP and resistivity survey at the INEL cold test pit

International Nuclear Information System (INIS)

Frangos, W.

1997-01-01

Induced polarization (IP) is a technique for detection of diffuse occurrences of metallic material. The Idaho National Laboratory (INEL) Cold Test Pit (CTP) has been carefully constructed to simulate stored hazardous waste occurrences. IP and resistivity surveys of the CTP show a very strong IP response and a modest resistivity response associated with the simulated waste. Several false positive resistivity anomalies are noted. 2-D inversion of the data accurately determine the lateral limits of the waste zone. The depth of burial indicated is deeper than reported by the construction engineers. Limited depth extent is recognized, in distinction to results from other, resistivity-based, methods, but it also appears too deep. IP holds promise as a method for locating buried waste

Long-term land use future scenarios for the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

1995-08-01

In order to facilitate decision regarding environmental restoration activities at the Idaho National Engineering Laboratory (INEL), the United States Department of Energy, Idaho Operations Office (DOE-ID) conducted analyses to project reasonable future land use scenarios at the INEL for the next 100 years. The methodology for generating these scenarios included: review of existing DOE plans, policy statements, and mission statements pertaining to the INEL; review of surrounding land use characteristics and county developments policies; solicitation of input from local, county, state and federal planners, policy specialists, environmental professionals, and elected officials; and review of environmental and development constraints at the INEL site that could influence future land use

Evaluation of potential for MSRE spent fuel and flush salt storage and treatment at the INEL

International Nuclear Information System (INIS)

Ougouag, A.M.; Ostby, P.A.; Nebeker, R.L.

1996-09-01

The potential for interim storage as well as for treatment of the Molten Salt Reactor Experiment spent fuel at INEL has been evaluated. Provided that some minimal packaging and chemical stabilization prerequisites are satisfied, safe interim storage of the spent fuel at the INEL can be achieved in a number of existing or planned facilities. Treatment by calcination in the New Waste Calcining Facility at the INEL can also be a safe, effective, and economical alternative to treatment that would require the construction of a dedicated facility. If storage at the INEL is chosen for the Molten Salt Reactor Experiment (MSRE) spent fuel salts, their transformation to the more stable calcine solid would still be desirable as it would result in a lowering of risks. Treatment in the proposed INEL Remote-Handled Immobilization Facility (RHIF) would result in a waste form that would probably be acceptable for disposal at one of the proposed national repositories. The cost increment imputable to the treatment of the MSRE salts would be a small fraction of the overall capital and operating costs of the facility or the cost of building and operating a dedicated facility. Institutional and legal issues regarding shipments of fuel and waste to the INEL are summarized. The transfer of MSRE spent fuel for interim storage or treatment at the INEL is allowed under existing agreements between the State of idaho and the Department of energy and other agencies of the Federal Government. In contrast, current agreements preclude the transfer into Idaho of any radioactive wastes for storage or disposal within the State of Idaho. This implies that wastes and residues produced from treating the MSRE spent fuel at locations outside Idaho would not be acceptable for storage in Idaho. Present agreements require that all fuel and high-level wastes stored at the INEL, including MSRE spent fuel if received at the INEL, must be moved to a location outside Idaho by the year 2035

Tiger Team assessment of the Idaho National Engineering Laboratory

Energy Technology Data Exchange (ETDEWEB)

McKenzie, Barbara J.; West, Stephanie G.; Jones, Olga G.; Kerr, Dorothy A.; Bieri, Rita A.; Sanderson, Nancy L.

1991-08-01

The purpose of the Safety and Health (S H) Subteam assessment was to determine the effectiveness of representative safety and health programs at the Idaho National Engineering Laboratory (INEL) site. Four Technical Safety Appraisal (TSA) Teams were assembled for this purpose by the US Department of Energy (DOE), Deputy Assistant Secretary for Safety and Quality Assurance, Office of Safety Appraisals (OSA). Team No. 1 reviewed EG G Idaho, Inc. (EG G Idaho) and the Department of Energy Field Office, Idaho (ID) Fire Department. Team No. 2 reviewed Argonne National Laboratory-West (ANL-W). Team No. 3 reviewed selected contractors at the INEL; specifically, Morrison Knudsen-Ferguson of Idaho Company (MK-FIC), Protection Technology of Idaho, Inc. (PTI), Radiological and Environmental Sciences Laboratory (RESL), and Rockwell-INEL. Team No. 4 provided an Occupational Safety and Health Act (OSHA)-type compliance sitewide assessment of INEL. The S H Subteam assessment was performed concurrently with assessments conducted by Environmental and Management Subteams. Performance was appraised in the following technical areas: Organization and Administration, Quality Verification, Operations, Maintenance, Training and Certification, Auxiliary Systems, Emergency Preparedness, Technical Support, Packaging and Transportation, Nuclear Criticality Safety, Security/Safety Interface, Experimental Activities, Site/Facility Safety Review, Radiological Protection, Personnel Protection, Worker Safety and Health (OSHA) Compliance, Fire Protection, Aviation Safety, Medical Services, and Firearms Safety.

Tiger Team assessment of the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

1991-08-01

This report documents the Tiger Team Assessment of the Idaho National Engineering Laboratory (INEL) located in Idaho Falls, Idaho. INEL is a multiprogram, laboratory site of the US Department of Energy (DOE). Overall site management is provided by the DOE Field Office, Idaho; however, the DOE Field Office, Chicago has responsibility for the Argonne National Laboratory-West facilities and operations through the Argonne Area Office. In addition, the Idaho Branch Office of the Pittsburgh Naval Reactors Office has responsibility for the Naval Reactor Facility (NRF) at the INEL. The assessment included all DOE elements having ongoing program activities at the site except for the NRF. In addition, the Safety and Health Subteam did not review the Westinghouse Idaho Nuclear Company, Inc. facilities and operations. The Tiger Team Assessment was conducted from June 17 to August 2, 1991, under the auspices of the Office of Special Projects, Office of the Assistant Secretary for Environment, Safety and Health, Headquarters, DOE. The assessment was comprehensive, encompassing environmental, safety, and health (ES ampersand H) disciplines; management; and contractor and DOE self-assessments. Compliance with applicable federal, state, and local regulations; applicable DOE Orders; best management practices; and internal INEL site requirements was assessed. In addition, an evaluation of the adequacy and effectiveness of the DOE and the site contractors management of ES ampersand H/quality assurance programs was conducted

Tiger Team assessment of the Idaho National Engineering Laboratory

Energy Technology Data Exchange (ETDEWEB)

1991-08-01

This report documents the Tiger Team Assessment of the Idaho National Engineering Laboratory (INEL) located in Idaho Falls, Idaho. INEL is a multiprogram, laboratory site of the US Department of Energy (DOE). Overall site management is provided by the DOE Field Office, Idaho; however, the DOE Field Office, Chicago has responsibility for the Argonne National Laboratory-West facilities and operations through the Argonne Area Office. In addition, the Idaho Branch Office of the Pittsburgh Naval Reactors Office has responsibility for the Naval Reactor Facility (NRF) at the INEL. The assessment included all DOE elements having ongoing program activities at the site except for the NRF. In addition, the Safety and Health Subteam did not review the Westinghouse Idaho Nuclear Company, Inc. facilities and operations. The Tiger Team Assessment was conducted from June 17 to August 2, 1991, under the auspices of the Office of Special Projects, Office of the Assistant Secretary for Environment, Safety and Health, Headquarters, DOE. The assessment was comprehensive, encompassing environmental, safety, and health (ES H) disciplines; management; and contractor and DOE self-assessments. Compliance with applicable federal, state, and local regulations; applicable DOE Orders; best management practices; and internal INEL site requirements was assessed. In addition, an evaluation of the adequacy and effectiveness of the DOE and the site contractors management of ES H/quality assurance programs was conducted.

Tiger Team assessment of the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

1991-08-01

The purpose of the Safety and Health (S ampersand H) Subteam assessment was to determine the effectiveness of representative safety and health programs at the Idaho National Engineering Laboratory (INEL) site. Four Technical Safety Appraisal (TSA) Teams were assembled for this purpose by the US Department of Energy (DOE), Deputy Assistant Secretary for Safety and Quality Assurance, Office of Safety Appraisals (OSA). Team No. 1 reviewed EG ampersand G Idaho, Inc. (EG ampersand G Idaho) and the Department of Energy Field Office, Idaho (ID) Fire Department. Team No. 2 reviewed Argonne National Laboratory-West (ANL-W). Team No. 3 reviewed selected contractors at the INEL; specifically, Morrison Knudsen-Ferguson of Idaho Company (MK-FIC), Protection Technology of Idaho, Inc. (PTI), Radiological and Environmental Sciences Laboratory (RESL), and Rockwell-INEL. Team No. 4 provided an Occupational Safety and Health Act (OSHA)-type compliance sitewide assessment of INEL. The S ampersand H Subteam assessment was performed concurrently with assessments conducted by Environmental and Management Subteams. Performance was appraised in the following technical areas: Organization and Administration, Quality Verification, Operations, Maintenance, Training and Certification, Auxiliary Systems, Emergency Preparedness, Technical Support, Packaging and Transportation, Nuclear Criticality Safety, Security/Safety Interface, Experimental Activities, Site/Facility Safety Review, Radiological Protection, Personnel Protection, Worker Safety and Health (OSHA) Compliance, Fire Protection, Aviation Safety, Medical Services, and Firearms Safety

INEL metal recycle radioactive scrap metal survey report

International Nuclear Information System (INIS)

Funk, D.M.

1994-09-01

DOE requested that inventory and characterization of radioactive scrap metal (RSM) be conducted across the DOE complex. Past studies have estimated the metal available from unsubstantiated sources. In meetings held in FY-1993, with seven DOE sites represented and several DOE-HQ personnel present, INEL personnel discovered that these numbers were not reliable and that large stockpiles did not exist. INEL proposed doing in-field measurements to ascertain the amount of RSM actually available. This information was necessary to determine the economic viability of recycling and to identify feed stock that could be used to produce containers for radioactive waste. This inventory measured the amount of RSM available at the selected DOE sites. Information gathered included radionuclide content and chemical form, general radiation field, alloy type, and mass of metal

Idaho National Engineering Laboratory High-Level Waste Roadmap

International Nuclear Information System (INIS)

1993-08-01

The Idaho National Engineering Laboratory (INEL) High-Level Waste (HLW) Roadmap takes a strategic look at the entire HLW life-cycle starting with generation, through interim storage, treatment and processing, transportation, and on to final disposal. The roadmap is an issue-based planning approach that compares ''where we are now'' to ''where we want and need to be.'' The INEL has been effectively managing HLW for the last 30 years. Calcining operations are continuing to turn liquid HLW into a more manageable form. Although this document recognizes problems concerning HLW at the INEL, there is no imminent risk to the public or environment. By analyzing the INEL current business operations, pertinent laws and regulations, and committed milestones, the INEL HLW Roadmap has identified eight key issues existing at the INEL that must be resolved in order to reach long-term objectives. These issues are as follows: A. The US Department of Energy (DOE) needs a consistent policy for HLW generation, handling, treatment, storage, and disposal. B. The capability for final disposal of HLW does not exist. C. Adequate processes have not been developed or implemented for immobilization and disposal of INEL HLW. D. HLW storage at the INEL is not adequate in terms of capacity and regulatory requirements. E. Waste streams are generated with limited consideration for waste minimization. F. HLW is not adequately characterized for disposal nor, in some cases, for storage. G. Research and development of all process options for INEL HLW treatment and disposal are not being adequately pursued due to resource limitations. H. HLW transportation methods are not selected or implemented. A root-cause analysis uncovered the underlying causes of each of these issues

Human applications of the INEL patient treatment planning system

International Nuclear Information System (INIS)

Wheeler, F.; Wessol, D.; Atkinson, C.; Nigg, D.

1995-01-01

During the past few years, murine and large animal research, as well as human studies have provided data to the point where human clinical trials have been initiated at the BMRR using BPA-F for gliomas and at the Massachusetts Institute of Technology Reactor (MITR) using BPA for melanomas of the extremeties. It is expected that glioma trials using BSH will proceed soon at the Petten High Flux Reactor (HFR) in the Netherlands. The first human glioma epithermal boron neutron capture therapy application was performed at the BMRR in the fall of 1994. This was a collaborative effort by BNL, Beth Israel Manhattan hospital, and INEL. The INEL planning system was chosen to perform dose predictions for this application

Laboratory scale vitrification of low-level radioactive nitrate salts and soils from the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Shaw, P.; Anderson, B.

1993-07-01

INEL has radiologically contaminated nitrate salt and soil waste stored above and below ground in Pad A and the Acid Pit at the Radioactive Waste Management Complex. Pad A contain uranium and transuranic contaminated potassium and sodium nitrate salts generated from dewatered waste solutions at the Rocky Flats Plant. The Acid Pit was used to dispose of liquids containing waste mineral acids, uranium, nitrate, chlorinated solvents, and some mercury. Ex situ vitrification is a high temperature destruction of nitrates and organics and immobilizes hazardous and radioactive metals. Laboratory scale melting of actual radionuclides containing INEL Pad A nitrate salts and Acid Pit soils was performed. The salt/soil/additive ratios were varied to determine the range of glass compositions (resulted from melting different wastes); maximize mass and volume reduction, durability, and immobilization of hazardous and radioactive metals; and minimize viscosity and offgas generation for wastes prevalent at INEL and other DOE sites. Some mixtures were spiked with additional hazardous and radioactive metals. Representative glasses were leach tested and showed none. Samples spiked with transuranic showed low nuclide leaching. Wasteforms were two to three times bulk densities of the salt and soil. Thermally co-processing soils and salts is an effective remediation method for destroying nitrate salts while stabilizing the radiological and hazardous metals they contain. The measured durability of these low-level waste glasses approached those of high-level waste glasses. Lab scale vitrification of actual INEL contaminated salts and soils was performed at General Atomics Laboratory as part of the INEL Waste Technology Development and Environmental Restoration within the Buried Waste Integrated Demonstration Program

Quaternary volcanism, tectonics, and sedimentation in the Idaho National Engineering Laboratory area

Energy Technology Data Exchange (ETDEWEB)

Hackett, W.R.; Smith, R.P.

1992-09-01

In this article, we discuss the regional context and describe localities for a two-day field excursion in the vicinity of the Idaho National Engineering Laboratory (INEL). We address several geologic themes: (1) Late Cenozoic, bimodal volcanism of the Eastern Snake River Plain (ESRP), (2) the regional tectonics and structural geology of the Basin and Range province to the northwest of the ESRP, (3) fluvial, lacustrine, and aeolian sedimentation in the INEL area, and (4) the influence of Quaternary volcanism and tectonics on sedimentation near the INEL.

Quaternary volcanism, tectonics, and sedimentation in the Idaho National Engineering Laboratory area

Energy Technology Data Exchange (ETDEWEB)

Hackett, W.R.; Smith, R.P.

1992-01-01

In this article, we discuss the regional context and describe localities for a two-day field excursion in the vicinity of the Idaho National Engineering Laboratory (INEL). We address several geologic themes: (1) Late Cenozoic, bimodal volcanism of the Eastern Snake River Plain (ESRP), (2) the regional tectonics and structural geology of the Basin and Range province to the northwest of the ESRP, (3) fluvial, lacustrine, and aeolian sedimentation in the INEL area, and (4) the influence of Quaternary volcanism and tectonics on sedimentation near the INEL.

Volcanic hazards of the Idaho National Engineering Laboratory and adjacent areas

International Nuclear Information System (INIS)

Hackett, W.R.; Smith, R.P.

1994-12-01

Potential volcanic hazards are assessed, and hazard zone maps are developed for the Idaho National Engineering Laboratory (INEL) and adjacent areas. The basis of the hazards assessment and mapping is the past volcanic history of the INEL region, and the apparent similarity of INEL volcanism with equivalent, well-studied phenomena in other regions of active volcanism, particularly Hawaii and Iceland. The most significant hazards to INEL facilities are associated with basaltic volcanism, chiefly lava flows, which move slowly and mainly threaten property by inundation or burning. Related hazards are volcanic gases and tephra, and ground disturbance associated with the ascent of magma under the volcanic zones. Several volcanic zones are identified in the INEL area. These zones contain most of the volcanic vents and fissures of the region and are inferred to be the most probable sites of future INEL volcanism. Volcanic-recurrence estimates are given for each of the volcanic zones based on geochronology of the lavas, together with the results of field and petrographic investigations concerning the cogenetic relationships of INEL volcanic deposits and associated magma intrusion. Annual probabilities of basaltic volcanism within the INEL volcanic zones range from 6.2 x 10 -5 per year (average 16,000-year interval between eruptions) for the axial volcanic zone near the southern INEL boundary and the Arco volcanic-rift zone near the western INEL boundary, to 1 x 10 -5 per year (average 100,000-year interval between eruptions) for the Howe-East Butte volcanic rift zone, a geologically old and poorly defined feature of the central portion of INEL. Three volcanic hazard zone maps are developed for the INEL area: lava flow hazard zones, a tephra (volcanic ash) and gas hazard zone, and a ground-deformation hazard zone. The maps are useful in land-use planning, site selection, and safety analysis

Site-specific probabilistic seismic hazard analyses for the Idaho National Engineering Laboratory. Volume 1: Final report

International Nuclear Information System (INIS)

1996-05-01

This report describes and summarizes a probabilistic evaluation of ground motions for the Idaho National Engineering Laboratory (INEL). The purpose of this evaluation is to provide a basis for updating the seismic design criteria for the INEL. In this study, site-specific seismic hazard curves were developed for seven facility sites as prescribed by DOE Standards 1022-93 and 1023-96. These sites include the: Advanced Test Reactor (ATR); Argonne National Laboratory West (ANL); Idaho Chemical Processing Plant (ICPP or CPP); Power Burst Facility (PBF); Radioactive Waste Management Complex (RWMC); Naval Reactor Facility (NRF); and Test Area North (TAN). The results, probabilistic peak ground accelerations and uniform hazard spectra, contained in this report are not to be used for purposes of seismic design at INEL. A subsequent study will be performed to translate the results of this probabilistic seismic hazard analysis to site-specific seismic design values for the INEL as per the requirements of DOE Standard 1020-94. These site-specific seismic design values will be incorporated into the INEL Architectural and Engineering Standards

Performance-Based Technology Selection Filter description report. INEL Buried Waste Integrated Demonstration System Analysis project

Energy Technology Data Exchange (ETDEWEB)

O`Brien, M.C.; Morrison, J.L.; Morneau, R.A.; Rudin, M.J.; Richardson, J.G.

1992-05-01

A formal methodology has been developed for identifying technology gaps and assessing innovative or postulated technologies for inclusion in proposed Buried Waste Integrated Demonstration (BWID) remediation systems. Called the Performance-Based Technology Selection Filter, the methodology provides a formalized selection process where technologies and systems are rated and assessments made based on performance measures, and regulatory and technical requirements. The results are auditable, and can be validated with field data. This analysis methodology will be applied to the remedial action of transuranic contaminated waste pits and trenches buried at the Idaho National Engineering Laboratory (INEL).

The INEL approach: Environmental Restoration Program management and implementation methodology

International Nuclear Information System (INIS)

1996-01-01

The overall objectives of the INEL Environmental Restoration (ER) Program management approach are to facilitate meeting mission needs through the successful implementation of a sound, and effective project management philosophy. This paper outlines the steps taken to develop the ER program, and explains further the implementing tools and processes used to achieve what can be viewed as fundamental to a successful program. The various examples provided will demonstrate how the strategies for implementing these operating philosophies are actually present and at work throughout the program, in spite of budget drills and organizational changes within DOE and the implementing contractor. A few of the challenges and successes of the INEL Environmental Restoration Program have included: a) completion of all enforceable milestones to date, b) acceleration of enforceable milestones, c) managing funds to reduce uncosted obligations at year end by utilizing greater than 99% of FY-95 budget, d) an exemplary safety record, e) developing a strategy for partial Delisting of the INEL by the year 2000, f) actively dealing with Natural Resource Damages Assessment issues, g) the achievement of significant project cost reductions, h) and implementation of a partnering charter and application of front end quality principles

Annual technology assessment and progress report for the Buried Transuranic Waste Program at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Low, J.O.

1985-12-01

An improved-confinement technology as applied to the Idaho National Engineering Laboratory (INEL) shallow-land-buried transuranic (TRU) waste is being investigated. An improved-confinement technology, in situ grouting, is being demonstrated in a 2-year engineering feasibility test at the INEL. Grout formulation and development were completed by Oak Ridge National Laboratory in Tennessee to support the in situ grouting test. Three grout formulations have been adapted to the arid, unsaturated soil conditions at the INEL: ordinary particulate grout; microfine penetration grout; soil grout. Three test trenches were constructed north of the INEL's Subsurface Disposal Area (SDA). Nonradioactive waste forms closely resembling TRU waste buried at the INEL have been fabricated and are ready for emplacement into these test trenches. A literature search for a simulated (analog) TRU tracer was completed as well as a chemical characterization of the INEL soil. Data developed from the chemistry characterization and literature search have been inputed into the selection and laboratory testing of the TRU analog tracers. Simulated TRU tracers will be loaded into waste forms prior to emplacement into the test trenches. Test trench data acquisition instrumentation will be installed during waste form emplacement. Instrumentation will monitor for moisture movement and tracer detection. Plans for test completion in FY-1986 are also shown. Various buried waste improved-confinement technologies performed by other Department of Energy sites were assessed for applicability to the INEL buried TRU waste. Primary demonstrations were performed at the Hanford site in Washington and at ORNL. This report also includes information on accomplishments of related activities at the INEL such as the program for Environmental Surveillance of the Radioactive Waste Management complex as well as the Subsurface Migration Studies. 18 refs., 11 figs., 12 tabs

Buried Transuranic Waste Studies Program at the Idaho National Engineering Laboratory: Annual technology assessment and progress report

International Nuclear Information System (INIS)

Low, J.O.; Allman, D.W.; Shaw, P.G.; Sill, C.W.

1987-01-01

In-situ grouting, an improved-confinement technology that could be applied to the Idaho National Engineering Laboratory (INEL) shallow-land-buried transuranic (TRU) waste, is being investigated by EG and G Idaho, Inc. In situ grouting has been demonstrated as the culmination of a two-year engineering feasibility test at the INEL. In situ stabilization and hydrologic isolation of a simulated buried TRU waste trench at an arid site were performed using an experimental dynamic compaction in situ grouting process developed by Rockwell Hanford Operations (RHO). A series of laboratory evaluations relative to the grout permeation characteristics of microfine particulate cements with INEL-type soil was performed prior to the grouting operations. In addition, an extensive pre-grouting hydrologic assessment of the test trench was performed to support the performance assessment analysis. Laboratory testing of various chemical materials yielded a suitable hydrologic tracer for use in the hydrologic monitoring phase of the experiment. Various plutonium transport laboratory evaluations were performed to assess the plutonium retention capabilities of a microfine grout/INEL-soil waste product similar to that expected to result if the grout is injected in situ into the INEL test trench. The test trench will be hydrologically assessed in FY 1987 to determine if the RHO grouting system attained the performance acceptance criteria of the experiment. The report includes a technology assessment of buried waste technologies developed by other DOE sites. Field demonstrations at ORNL and Hanford are reported under this technology assessment. Also included is information on activities related to buried waste management at the INEL. These include environmental surveillance of the Radioactive Waste Management Complex and the Subsurface Migration Studies Program

Space nuclear thermal propulsion test facilities accommodation at INEL

International Nuclear Information System (INIS)

Hill, T.J.; Reed, W.C.; Welland, H.J.

1993-01-01

The U.S. Air Force (USAF) has proposed to develop the technology and demonstrate the feasibility of a particle bed reactor (PBR) propulsion system that could be used to power an advanced upper stage rocket engine. The U.S. Department of Energy (DOE) is cooperating with the USAF in that it would host the test facility if the USAF decides to proceed with the technology demonstration. Two DOE locations have been proposed for testing the PBR technology, a new test facility at the Nevada Test Site, or the modification and use of an existing facility at the Idaho National Engineering Laboratory. The preliminary evaluations performed at the INEL to support the PBR technology testing has been completed. Additional evaluations to scope the required changes or upgrade needed to make the proposed USAF PBR test facility meet the requirements for testing Space Exploration Initiative (SEI) nuclear thermal propulsion engines are underway

Space nuclear thermal propulsion test facilities accommodation at INEL

Science.gov (United States)

Hill, Thomas J.; Reed, William C.; Welland, Henry J.

1993-01-01

The U.S. Air Force (USAF) has proposed to develop the technology and demonstrate the feasibility of a particle bed reactor (PBR) propulsion system that could be used to power an advanced upper stage rocket engine. The U.S. Department of Energy (DOE) is cooperating with the USAF in that it would host the test facility if the USAF decides to proceed with the technology demonstration. Two DOE locations have been proposed for testing the PBR technology, a new test facility at the Nevada Test Site, or the modification and use of an existing facility at the Idaho National Engineering Laboratory. The preliminary evaluations performed at the INEL to support the PBR technology testing has been completed. Additional evaluations to scope the required changes or upgrade needed to make the proposed USAF PBR test facility meet the requirements for testing Space Exploration Initiative (SEI) nuclear thermal propulsion engines are underway.

1983 Environmental monitoring program report for Idaho National Engineering Laboratory Site

International Nuclear Information System (INIS)

Hoff, D.L.; Chew, E.W.; Dickson, R.L.

1984-05-01

The results of the various monitoring programs for 1983 indicated that radioactivity from the Idaho National Engineering Laboratory (INEL) Site operations could not be distinguished from worldwide fallout and natural radioactivity in the region surrounding the Site. Although some radioactive materials were discharged during Site operations, concentrations and doses to the surrounding population were of no health consequence and were far less than State of Idaho and Federal health protection guidelines. This report describes the air, water, and foodstuff samples routinely collected at the INEL boundary locations and at locations distant from the INEL Site. 11 figures, 14 tables

In summary: Idaho National Engineering Laboratory site environmental report for calendar year 1995

International Nuclear Information System (INIS)

Roush, D.; Mitchell, R.G.; Peterson, D.

1996-08-01

Every human is exposed to natural radiation. This exposure comes from many sources, including cosmic radiation from outer space, naturally-occurring radon, and radioactivity from substances in our bodies. In addition to natural sources of radiation, humans can also be exposed to man-made sources of radiation. Examples of man-made sources include nuclear medicine, X-rays, nuclear weapons testing, and accidents at nuclear power plants. The Idaho National Engineering Laboratory (INEL) is a U.S. Department of Energy (DOE) research facility that deals, in part, with studying nuclear reactors and storing radioactive materials. Careful handling and rigorous procedures do not completely eliminate the risk of releasing radioactivity. So, there is a remote possibility for a member of the public near the INEL to be exposed to radioactivity from the INEL. Extensive monitoring of the environment takes place on and around the INEL. These programs search for radionuclides and other contaminants. The results of these programs are presented each year in a site environmental report. This document summarizes the Idaho National Engineering Laboratory Site Environmental Report for Calendar Year 1995

Computer modeling of jet mixing in INEL waste tanks

International Nuclear Information System (INIS)

Meyer, P.A.

1994-01-01

The objective of this study is to examine the feasibility of using submerged jet mixing pumps to mobilize and suspend settled sludge materials in INEL High Level Radioactive Waste Tanks. Scenarios include removing the heel (a shallow liquid and sludge layer remaining after tank emptying processes) and mobilizing and suspending solids in full or partially full tanks. The approach used was to (1) briefly review jet mixing theory, (2) review erosion literature in order to identify and estimate important sludge characterization parameters (3) perform computer modeling of submerged liquid mixing jets in INEL tank geometries, (4) develop analytical models from which pump operating conditions and mixing times can be estimated, and (5) analyze model results to determine overall feasibility of using jet mixing pumps and make design recommendations

Idaho National Engineering Laboratory High-Level Waste Roadmap. Revision 2

Energy Technology Data Exchange (ETDEWEB)

1993-08-01

The Idaho National Engineering Laboratory (INEL) High-Level Waste (HLW) Roadmap takes a strategic look at the entire HLW life-cycle starting with generation, through interim storage, treatment and processing, transportation, and on to final disposal. The roadmap is an issue-based planning approach that compares ``where we are now`` to ``where we want and need to be.`` The INEL has been effectively managing HLW for the last 30 years. Calcining operations are continuing to turn liquid HLW into a more manageable form. Although this document recognizes problems concerning HLW at the INEL, there is no imminent risk to the public or environment. By analyzing the INEL current business operations, pertinent laws and regulations, and committed milestones, the INEL HLW Roadmap has identified eight key issues existing at the INEL that must be resolved in order to reach long-term objectives. These issues are as follows: A. The US Department of Energy (DOE) needs a consistent policy for HLW generation, handling, treatment, storage, and disposal. B. The capability for final disposal of HLW does not exist. C. Adequate processes have not been developed or implemented for immobilization and disposal of INEL HLW. D. HLW storage at the INEL is not adequate in terms of capacity and regulatory requirements. E. Waste streams are generated with limited consideration for waste minimization. F. HLW is not adequately characterized for disposal nor, in some cases, for storage. G. Research and development of all process options for INEL HLW treatment and disposal are not being adequately pursued due to resource limitations. H. HLW transportation methods are not selected or implemented. A root-cause analysis uncovered the underlying causes of each of these issues.

Plasma treatment of INEL soil contaminated with heavy metals

International Nuclear Information System (INIS)

Detering, B.A.; Batdorf, J.A.

1992-01-01

INEL soil spiked with inorganic salts of chromium, lead, mercury, silver, and zinc was melted in a 150 kW plasma furnace to produce a glassy slag product. This glassy slag is an environmentally safe waste form. In order to reduce the melting temperature of the soil, sodium carbonate was added to half of the test batches. Random sample from each batch of glassy slag product were analyzed by an independent laboratory for total metals concentration and leachability of metals via the Environmental Protection Agency (EPA) toxicity characterization leaching procedure (RCLP) tests. These tests showed the residual metals were very tightly bound to the slag matrix and were within EPA TCLP limits under these test conditions. Additionally, scanning electron microscopy (SEM) and emissions dispersive spectroscopy (EDS) analysis of the vitrified soil also confirmed that the added metals present in the vitrified soil were totally contained in the crystalline phase as distinct oxide crystallites

Idaho National Engineering Laboratory Conceptual Site Treatment Plan. Tables 8.1 and 8.2, Appendices A, B, C

International Nuclear Information System (INIS)

Eaton, D.

1993-10-01

The US Department of Energy (DOE) is required by Section 3021(b) of the Resource Conservation and Recovery Act (RCRA), as amended by the Federal Facility Compliance Act (FFCAct), to prepare plans describing the development of treatment capacities and technologies for treating mixed waste. The FFCAct requires site treatment plans (STPs or plans) to be developed for each site at which DOE generates or stores mixed waste and submitted to the host state or the US Environmental Protection Agency (EPA) for either approval, approval with modification, or disapproval. The Idaho National Engineering Laboratory (INEL) Conceptual Site Treatment Plan (CSTP) is the preliminary version of the plan required by the FFCAct and is being provided to the State of Idaho, the EPA, and others for review. A list of the other DOE sites preparing CSTPs is included in Appendix A of this document. In addition to aiding the INEL in formulating its Final Proposed STP, this CSTP will also provide information to other DOE sites for use in identifying common technology needs and potential options for treating their wastes. The INEL CSTP is also intended to be used in conjunction with CSTPs from other sites as a basis for nationwide discussions among state regulators, the EPA, and other interested parties on treatment strategies and options, and on technical and equity issues associated with DOE's mixed waste

Idaho National Engineering Laboratory Conceptual Site Treatment Plan. Tables 8.1 and 8.2, Appendices A, B, C

Energy Technology Data Exchange (ETDEWEB)

Eaton, D.

1993-10-01

The US Department of Energy (DOE) is required by Section 3021(b) of the Resource Conservation and Recovery Act (RCRA), as amended by the Federal Facility Compliance Act (FFCAct), to prepare plans describing the development of treatment capacities and technologies for treating mixed waste. The FFCAct requires site treatment plans (STPs or plans) to be developed for each site at which DOE generates or stores mixed waste and submitted to the host state or the US Environmental Protection Agency (EPA) for either approval, approval with modification, or disapproval. The Idaho National Engineering Laboratory (INEL) Conceptual Site Treatment Plan (CSTP) is the preliminary version of the plan required by the FFCAct and is being provided to the State of Idaho, the EPA, and others for review. A list of the other DOE sites preparing CSTPs is included in Appendix A of this document. In addition to aiding the INEL in formulating its Final Proposed STP, this CSTP will also provide information to other DOE sites for use in identifying common technology needs and potential options for treating their wastes. The INEL CSTP is also intended to be used in conjunction with CSTPs from other sites as a basis for nationwide discussions among state regulators, the EPA, and other interested parties on treatment strategies and options, and on technical and equity issues associated with DOE`s mixed waste.

Idaho National Engineering Laboratory nonradiological waste management information for 1994 and record to date

International Nuclear Information System (INIS)

French, D.L.; Lisee, D.J.; Taylor, K.A.

1995-08-01

This document provides detailed data and graphics on airborne and liquid effluent releases, fuel oil and coal consumption, water usage, and hazardous and mixed waste generated for calendar year 1994. This report summarizes industrial waste data records compiled since 1971 for the Idaho National Engineering Laboratory (INEL). The data presented are from the INEL Nonradiological Waste Management Information System

Idaho National Engineering Laboratory Nonradiological Waste Management Information for 1993 and record to date

International Nuclear Information System (INIS)

Sims, A.M.; Taylor, K.A.

1994-08-01

This document provides detailed data and graphics on airborne and liquid effluent releases, fuel oil and coal consumption, water usage, and hazardous and mixed waste generated for calendar year 1993. This report summarizes industrial waste data records compiled since 1971 for the Idaho National Engineering Laboratory (INEL). The data presented are from the INEL Nonradiological Waste Management Information System

Environmental resource document for the Idaho National Engineering Laboratory. Volume 1

Energy Technology Data Exchange (ETDEWEB)

Irving, J.S.

1993-07-01

This document contains information related to the environmental characterization of the Idaho National Engineering Laboratory (INEL). The INEL is a major US Department of Energy facility in southeastern Idaho dedicated to nuclear research, waste management, environmental restoration, and other activities related to the development of technology. Environmental information covered in this document includes land, air, water, and ecological resources; socioeconomic characteristics and land use; and cultural, aesthetic, and scenic resources.

Environmental resource document for the Idaho National Engineering Laboratory. Volume 2

Energy Technology Data Exchange (ETDEWEB)

Irving, J.S.

1993-07-01

This document contains information related to the environmental characterization of the Idaho National Engineering Laboratory (INEL). The INEL is a major US Department of Energy facility in southeastern Idaho dedicated to nuclear research, waste management, environmental restoration, and other activities related to the development of technology. Environmental information covered in this document includes land, air, water, and ecological resources; socioeconomic characteristics and land use; and cultural, aesthetic, and scenic resources.

Ecological risk assessment at the Idaho National Engineering Laboratory: Overview

International Nuclear Information System (INIS)

VanHorn, R.; Bensen, T.; Green, T.; Hampton, N.; Staley, C.; Morris, R.; Brewer, R.; Peterson, S.

1994-01-01

The paper will present an overview of the methods and results of the screening level ecological risk assessment (ERA) performed at the Idaho National Engineering Laboratory (INEL). The INEL is a site with some distinct characteristics. First it is a large Department of Energy (DOE) laboratory (2,300 km 2 ) having experienced 40 years of nuclear material production operations. Secondly, it is a relatively undisturbed cold desert ecosystem. Neither of these issues have been sufficiently addressed in previous ERAs. It was necessary in many instances to develop methods that differed from those used in other studies. This paper should provide useful methodologies for the ERAs performed at other similar sites

Idaho National Engineering Laboratory historical dose evaluation: Volume 1

International Nuclear Information System (INIS)

Francis, S.J.

1991-08-01

The methodology and results are presented for an evaluation of potential radiation doses to a hypothetical individual who may have resided at an offsite location with the highest concentration of airborne radionuclides near the Idaho National Engineering Laboratory (INEL). Volume 1 contains a summary of methods and results. The years of INEL operations from 1952 to 1989 were evaluated. Radiation doses to an adult, child, and infant were estimated for both operational (annual) and episodic (short-term) airborne releases from INEL facilities. Atmospheric dispersion of operational releases was modeled using annual average meteorological conditions. Dispersion of episodic releases was generally modeled using actual hourly wind speed and direction data at the time of release. 50 refs., 23 figs., 10 tabs

Idaho National Engineering Laboratory Waste Management Operations Roadmap Document

International Nuclear Information System (INIS)

Bullock, M.

1992-04-01

At the direction of the Department of Energy-Headquarters (DOE-HQ), the DOE Idaho Field Office (DOE-ID) is developing roadmaps for Environmental Restoration and Waste Management (ER ampersand WM) activities at Idaho National Engineering Laboratory (INEL). DOE-ID has convened a select group of contractor personnel from EG ampersand G Idaho, Inc. to assist DOE-ID personnel with the roadmapping project. This document is a report on the initial stages of the first phase of the INEL's roadmapping efforts

Idaho National Engineering Laboratory site environmental report for calendar year 1995

International Nuclear Information System (INIS)

Mitchell, R.G.; Peterson, D.; Hoff, D.L.

1996-08-01

This report presents a compilation of data collected in 1995 for the routine environmental surveillance programs conducted on and around the Idaho National Engineering Laboratory (INEL). During 1995, the offsite surveillance program was conducted by the Environmental Science and Research Foundation. Onsite surveillance was performed by Lockheed Idaho Technologies Company (LITCO). Ground-water monitoring, both on and offsite, was performed by the US Geological Survey (USGS). This report also presents summaries of facility effluent monitoring data collected by INEL contractors. This report, prepared in accordance with the requirements in DOE Order 5400.1, is not intended to cover the numerous special environmental research programs being conducted at the INEL by the Foundation, LITCO, USGS, and others

Low-level waste incineration: experience at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Bohrer, H.A.; Dalton, J.D.

1987-01-01

The Waste Experimental Reduction Facility (WERF) is a low level radioactive waste treatment facility being operated at the Idaho National Engineering Laboratory (INEL). A key component of the facility is a dual chambered controlled air incinerator with a dry off-gas treatment system. The incinerator began processing radioactive waste in September, 1984. Limited operations continued from that data until October, 1985, at which time all INEL generators began shipping combustible waste for incineration. The incinerator is presently processing all available INEL combustible Dry Active Waste (DAW) (approximately 1700 m 3 per year) operating about five days per month. Performance to date has demonstrated the effectiveness, viability and safety of incineration as a volume reduction method of DAW. 3 figures

Idaho National Engineering Laboratory site environmental report for calendar year 1995

Energy Technology Data Exchange (ETDEWEB)

Mitchell, R.G.; Peterson, D.; Hoff, D.L.

1996-08-01

This report presents a compilation of data collected in 1995 for the routine environmental surveillance programs conducted on and around the Idaho National Engineering Laboratory (INEL). During 1995, the offsite surveillance program was conducted by the Environmental Science and Research Foundation. Onsite surveillance was performed by Lockheed Idaho Technologies Company (LITCO). Ground-water monitoring, both on and offsite, was performed by the US Geological Survey (USGS). This report also presents summaries of facility effluent monitoring data collected by INEL contractors. This report, prepared in accordance with the requirements in DOE Order 5400.1, is not intended to cover the numerous special environmental research programs being conducted at the INEL by the Foundation, LITCO, USGS, and others.

Track 2 sites: Guidance for assessing low probability hazard sites at the INEL

International Nuclear Information System (INIS)

1994-01-01

This document presents guidance for assessment of Track 2 low probability hazard sites (LPHS) at the Idaho National Engineering Laboratory (INEL). The Track 2 classification was developed specifically for the INEL to streamline the implementation of Comprehensive Environmental Response, Compensation, and Liability Act. Track 2 LPHSs are described as sites where insufficient data are available to make a decision concerning the risk level or to select or design a remedy. As such, these types of sites are not described in the National Contingency Plan or existing regulatory guidance. The goal of the Track 2 process is to evaluate LPHSs using existing qualitative and quantitative data to minimize the collection of new environmental data. To this end, this document presents a structured format consisting of a series of questions and tables. A qualitative risk assessment is used. The process is iterative, and addresses an LPHS from multiple perspectives (i.e., historical, empirical, process) in an effort to generate a reproducible and defensible method. This rigorous approach follows the data quality objective process and establishes a well organized, logical approach to consolidate and assess existing data, and set decision criteria. If necessary, the process allows for the design of a sampling and analysis strategy to obtain new environmental data of appropriate quality to support decisions for each LPHS. Finally, the guidance expedites consensus between regulatory parties by emphasizing a team approach to Track 2 investigations

The DOE/NOAA meteorological program at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

George, D.H.

1996-01-01

The National Oceanic and Atmospheric Administration (NOAA) Air Resources Laboratory (ARL) has recently upgraded the U.S. Department of Energy's (DOE's) Idaho National Engineering Laboratory (INEL) Meteorological Measuring Network. This has allowed the entire service system to be modernized

In Situ Vitrification Engineering-Scale Test ES-INEL-4 Product Characterization Test Plan

International Nuclear Information System (INIS)

Weidner, J.R.; Stoots, P.R.

1990-06-01

In 1987, the Buried Waste Program (BWP) was established within EG ampersand G Idaho, Inc., the prime contractor at INEL. Following the Environmental Restoration guidelines of the Buried Waste Program, the In Situ Vitrification Program is participating in a Remedial Investigation/Feasibility Study (RI/FS) for permanent disposal of INEL waste, in compliance with the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA). This study was requested and is being funded by the Office of Technology Development of the Idaho Operations Office of DOE (DOE-ID). As part of the RI/FS, an in situ vitrification (ISV) scoping study on the treatability of mixed low-level and mixed transuranic-contaminated waste is being performed to determine the applicability of ISV to remediation of waste at SDA. In examination of the ISV process for applicability to SDA waste, this In Situ Vitrification Engineering-Scale Test ES-INEL-4 Product Characterization Test Plan identifies the following: sampling and analysis strategy; sampling procedures; methods to conduct analyses; equipment; and procedures to ensure data quality. 8 refs., 2 tabs

Idaho National Engineering Laboratory Conceptual Site Treatment Plan. Sections 1 through 8, Tables 2-1 through 6-1, Figures 1 and 2

International Nuclear Information System (INIS)

Eaton, D.

1993-10-01

The US Department of Energy (DOE) is required by Section 3021(b) of the Resource Conservation and Recovery Act (RCRA), as amended by the Federal Facility Compliance Act (FFCAct), to prepare plans describing the development of treatment capacities and technologies for treating mixed waste. The FFCAct requires site treatment plans (STPs or plans) to be developed for each site at which DOE generates or stores mixed waste and submitted to the host state or the US Environmental Protection Agency (EPA) for either approval, approval with modification, or disapproval. The Idaho National Engineering Laboratory (INEL) Conceptual Site Treatment Plan (CSTP) is the preliminary version of the plan required by the FFCAct and is being provided to the State of Idaho, the EPA, and others for review. A list of the other DOE sites preparing CSTPs is included in Appendix A of this document. In addition to aiding the INEL in formulating its Final Proposed STP, this CSTP will also provide information to other DOE sites for use in identifying common technology needs and potential options for treating their wastes. The INEL CSTP is also intended to be used in conjunction with CSTPs from other sites as a basis for nationwide discussions among state regulators, the EPA, and other interested parties on treatment strategies and options, and on technical and equity issues associated with DOE's mixed waste

Solute travel time in the vadose zone under RWMC at INEL

International Nuclear Information System (INIS)

Liou, J.C.P.; Tian, J.

1995-01-01

Solute transport in the vadose zone under the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering Laboratory (INEL) is considered. The objective is to assess the relative importance of variables involved in modeling the travel time of a conservative solute from ground surface to water table. The vadose zone under RWMC is composed of several layers of basalt flows interceded with sediment layers. The thickness of the layers varies with location. The hydraulic properties also vary. The extents of the variations are large, with standard deviations exceed mean in some instances. The vadose zone is idealized as composed of horizontal layers. Solute transport starts at the ground surface and moves vertically downwards to the water table. The perceived process is one-dimensional. This study used VS2DT, a computer code developed by the US Geological Survey, for simulating solute transport in variably saturated porous media

Robotic applications at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Griebenow, B.E.; Marts, D.J.

1990-01-01

The Idaho National Engineering Laboratory (INEL) has several programs and projected programs that involve work in hazardous environments. Robotics/remote handling technology is being considered for an active role in these programs. The most appealing aspect of using robotics is in the area of personnel safety. Any task requiring an individual to enter a hazardous or potentially hazardous environment can benefit substantially from robotics by removing the operator from the environment and having him conduct the work remotely. Several INEL programs were evaluated based on their applications for robotics and the results and some conclusions are discussed in this paper. 1 fig

1985 Environmental Monitoring Program report for the Idaho National Engineering Laboratory site

International Nuclear Information System (INIS)

Hoff, D.L.; Chew, E.W.; Rope, S.K.

1986-05-01

The results of the various monitoring programs for 1985 indicated that radioactivity from the Idaho National Engineering Laboratory (INEL) Site operations could not be distinguished from worldwide fallout and natural radioactivity in the region surrounding the Site. Although some radioactive materials were discharged during Site operations, concentrations and doses to the surrounding population were of no health consequence and were far less than State of Idaho and Federal health protection guidelines. This report describes the air, water, and foodstuff samples routinely collected at the INEL boundary locations and at locations distant from the INEL Site. It compares and evaluates the sample results, discussing implications, if any. Included for the first time this year are data from air and water samples routinely collected from onsite locations. The report also summarizes significant environmental activities at the INEL Site during 1985, nonradioactive and radioactive effluent monitoring at the Site, and the US Geological Survey (USGS) groundwater monitoring program

Annual report on monitoring of the unsaturated zone and recharge areas at INEL to the state of Idaho INEL Oversight Committee

International Nuclear Information System (INIS)

King, B.; Bloomsburg, G.; Horn, D.; Liou, J.; Finnie, J.

1992-01-01

During the early years of the INEL, the USGS conducted extensive studies (sitewide drilling program) of the geology and hydrology of the area collecting varied data over the years. The unsaturated zone has not received much attention until recently. The studies that have been done are a result of problems or concerns arising from liquid radioactive waste disposal. The TRA facility has the most information published about its waste disposal activities. The ICPP has less data about the unsaturated zone due to the fact that most waste water disposal has been to a well. Little is known about the effect of waste water disposal at the NRF on the unsaturated zone. Essentially no information was found about waste disposal activities at other facilities, primarily because there does not appear to be any reported problems associated with waste water disposal at these locations. The RWMC has received much attention in the last few years as the result of being priority No. 1 in the superfund clean up of the INEL. A considerable amount of data are available describing the unsaturated zone at the RWMC. These data have been collected to field calibrate a radionuclide migration model for the RWMC

The Idaho National Engineering Laboratory site environmental report for calendar year 1989

International Nuclear Information System (INIS)

Hoff, D.L.; Mitchell, R.G.; Bowman, G.C.; Moore, R.

1990-06-01

To verify that exposures resulting from operations at the Department of Energy (DOE) nuclear facilities have remained very small, each site at which nuclear activities are underway operates an environmental surveillance program to monitor the air, water and any other pathway where radionuclides from operations might conceivably reach workers or members of the public. This report presents data collected in 1989 for the routine environmental surveillance program conducted by the Radiological and Environmental Sciences Laboratory (RESL) of DOE and the US Geological Survey (USGS) at the Idaho National Engineering Laboratory (INEL) site. The environmental surveillance program for the INEL and vicinity for 1989 included the collection and analysis of samples from potential exposure pathways. Three basic groups of samples were collected. Those collected within the INEL boundaries will be referred to as onsite samples. Samples collected outside, but near, the Site boundaries will be referred to as boundary samples or part of a group of offsite samples. Samples collected from locations considerably beyond the Site boundaries will be referred to as distant samples or part of the offsite group. With the exception of Craters of the Moon National Monument, the distant locations are sufficiently remote from the Site to ensure that detectable radioactivity is primarily due to natural background sources or sources other than INEL operations. 35 refs., 14 figs., 13 tabs

The Idaho National Engineering Laboratory Site Environmental Report for Calendar Year 1993

International Nuclear Information System (INIS)

Mitchell, R.G.

1994-07-01

Results of the various environmental monitoring programs for 1993 are presented from the Idaho National Engineering Laboratory (INEL) operations. Although some radioactive materials were discharged during Site operations, concentrations and doses to the surrounding population were of no health consequence and were far less than State of Idaho and Federal health protection guidelines. Chapter 2 summarizes INEL activities related to compliance with environmental regulations and laws for Calendar Year 1993. The major portion of the report summarizes results of the environmental surveillance program conducted by the DOE Radiological and Environmental Sciences Laboratory, which includes the collection of foodstuffs at the INEL boundary and distant offsite locations, and the collection of air and water samples at onsite locations and offsite boundary and distant locations. The report also compares and evaluates the sample results to appropriate federal regulations and standards and discusses implications, if any. The US Geological Survey (USGS) ground-water monitoring program is briefly summarized and data are included in maps showing the spread of contaminants. Effluent monitoring and nonradiological drinking water monitoring are discussed briefly and data are summarized

Project Management Plan for the Idaho National Engineering Laboratory Waste Isolation Pilot Plant Experimental Test Program

International Nuclear Information System (INIS)

Connolly, M.J.; Sayer, D.L.

1993-11-01

EG ampersand G Idaho, Inc. and Argonne National Laboratory-West (ANL-W) are participating in the Idaho National Engineering Laboratory's (INEL's) Waste Isolation Pilot Plant (WIPP) Experimental Test Program (WETP). The purpose of the INEL WET is to provide chemical, physical, and radiochemical data on transuranic (TRU) waste to be stored at WIPP. The waste characterization data collected will be used to support the WIPP Performance Assessment (PA), development of the disposal No-Migration Variance Petition (NMVP), and to support the WIPP disposal decision. The PA is an analysis required by the Code of Federal Regulations (CFR), Title 40, Part 191 (40 CFR 191), which identifies the processes and events that may affect the disposal system (WIPP) and examines the effects of those processes and events on the performance of WIPP. A NMVP is required for the WIPP by 40 CFR 268 in order to dispose of land disposal restriction (LDR) mixed TRU waste in WIPP. It is anticipated that the detailed Resource Conservation and Recovery Act (RCRA) waste characterization data of all INEL retrievably-stored TRU waste to be stored in WIPP will be required for the NMVP. Waste characterization requirements for PA and RCRA may not necessarily be identical. Waste characterization requirements for the PA will be defined by Sandia National Laboratories. The requirements for RCRA are defined in 40 CFR 268, WIPP RCRA Part B Application Waste Analysis Plan (WAP), and WIPP Waste Characterization Program Plan (WWCP). This Project Management Plan (PMP) addresses only the characterization of the contact handled (CH) TRU waste at the INEL. This document will address all work in which EG ampersand G Idaho is responsible concerning the INEL WETP. Even though EG ampersand G Idaho has no responsibility for the work that ANL-W is performing, EG ampersand G Idaho will keep a current status and provide a project coordination effort with ANL-W to ensure that the INEL, as a whole, is effectively and

Integrated safeguards and security for the INEL Special Isotope Separation Plant

International Nuclear Information System (INIS)

Warner, G.F.; Zack, N.R.

1990-01-01

This paper describes the development of the safeguards and security system that was to be used for the Special Isotope Separation (SIS) Production Plant. The US Department of Energy has postponed the construction of the SIS Plant that was to be built at the Idaho National Engineering Laboratory (INEL) site near Idaho Falls, Idaho. The Plant was designed to produce weapons grade plutonium from DOE owned fuel grade plutonium by converting off-spec. plutonium dioxide into metal buttons that would meet required chemical and isotopic specifications. Because this was to be a completely new facility there was a unique opportunity to provide an in-depth, ''state-of-the- art'' safeguards and security system without attempting to overlay upon an existing, older system. This facility was being designed to be in complete compliance with the new DOE Orders by integrating safeguards and security into the plant operating system and by providing graded protection to the areas of varying sensitivity within the plant

Baseline tests for arc melter vitrification of INEL buried wastes. Volume 1: Facility description and summary data report

International Nuclear Information System (INIS)

Oden, L.L.; O'Connor, W.K.; Turner, P.C.; Soelberg, N.R.; Anderson, G.L.

1993-01-01

This report presents field results and raw data from the Buried Waste Integrated Demonstration (BWID) Arc Melter Vitrification Project Phase 1 baseline test series conducted by the Idaho National Engineering Laboratory (INEL) in cooperation with the U.S. Bureau of Mines (USBM). The baseline test series was conducted using the electric arc melter facility at the USBM Albany Research Center in Albany, Oregon. Five different surrogate waste feed mixtures were tested that simulated thermally-oxidized, buried, TRU-contaminated, mixed wastes and soils present at the INEL. The USBM Arc Furnace Integrated Waste Processing Test Facility includes a continuous feed system, the arc melting furnace, an offgas control system, and utilities. The melter is a sealed, 3-phase alternating current (ac) furnace approximately 2 m high and 1.3 m wide. The furnace has a capacity of 1 metric ton of steel and can process as much as 1,500 lb/h of soil-type waste materials. The surrogate feed materials included five mixtures designed to simulate incinerated TRU-contaminated buried waste materials mixed with INEL soil. Process samples, melter system operations data and offgas composition data were obtained during the baseline tests to evaluate the melter performance and meet test objectives. Samples and data gathered during this program included (a) automatically and manually logged melter systems operations data, (b) process samples of slag, metal and fume solids, and (c) offgas composition, temperature, velocity, flowrate, moisture content, particulate loading and metals content. This report consists of 2 volumes: Volume I summarizes the baseline test operations. It includes an executive summary, system and facility description, review of the surrogate waste mixtures, and a description of the baseline test activities, measurements, and sample collection. Volume II contains the raw test data and sample analyses from samples collected during the baseline tests

Track 2 sites: Guidance for assessing low probability hazard sites at the INEL. Revision 6

Energy Technology Data Exchange (ETDEWEB)

1994-01-01

This document presents guidance for assessment of Track 2 low probability hazard sites (LPHS) at the Idaho National Engineering Laboratory (INEL). The Track 2 classification was developed specifically for the INEL to streamline the implementation of Comprehensive Environmental Response, Compensation, and Liability Act. Track 2 LPHSs are described as sites where insufficient data are available to make a decision concerning the risk level or to select or design a remedy. As such, these types of sites are not described in the National Contingency Plan or existing regulatory guidance. The goal of the Track 2 process is to evaluate LPHSs using existing qualitative and quantitative data to minimize the collection of new environmental data. To this end, this document presents a structured format consisting of a series of questions and tables. A qualitative risk assessment is used. The process is iterative, and addresses an LPHS from multiple perspectives (i.e., historical, empirical, process) in an effort to generate a reproducible and defensible method. This rigorous approach follows the data quality objective process and establishes a well organized, logical approach to consolidate and assess existing data, and set decision criteria. If necessary, the process allows for the design of a sampling and analysis strategy to obtain new environmental data of appropriate quality to support decisions for each LPHS. Finally, the guidance expedites consensus between regulatory parties by emphasizing a team approach to Track 2 investigations.

The Idaho National Engineering Laboratory Site environmental report for calendar year 1991

International Nuclear Information System (INIS)

Hoff, D.L.; Mitchell, R.G.; Moore, R.; Bingham, L.

1992-09-01

The results of the various monitoring programs for 1991 indicate that most radioactivity from the Idaho National Engineering Laboratory (INEL) operations could not be distinguished from worldwide fallout and natural radioactivity in the region surrounding the INEL Site. Although some radioactive materials were discharged during Site operations, concentrations and doses to the surrounding population were of no health consequence and were far less than State of Idaho and Federal health protection guidelines. The first section of the report summarizes Calendar Year 1991 and January 1 through June 1, 1992, INEL activities related to compliance with environmental regulations and laws. The major portion of the report summarizes results of the RESL environmental surveillance program, which includes the collection of foodstuffs at the INEL boundary and distant offsite locations, and the collection of air and water samples at onsite locations and offsite boundary and distant locations. The report also compares and evaluates the sample results to appropriate federal regulations and standards and discusses implications, if any. The US Geological Survey (USGS) groundwater monitoring program is briefly summarized and data from USGS reports are included in tables and maps showing the spread of contaminants. Effluent monitoring and nonradiological drinking water monitoring performed by INEL contractors are discussed briefly and data are summarized in tables

Idaho National Engineering Laboratory installation roadmap document

International Nuclear Information System (INIS)

1993-01-01

The roadmapping process was initiated by the US Department of Energy's office of Environmental Restoration and Waste Management (EM) to improve its Five-Year Plan and budget allocation process. Roadmap documents will provide the technical baseline for this planning process and help EM develop more effective strategies and program plans for achieving its long-term goals. This document is a composite of roadmap assumptions and issues developed for the Idaho National Engineering Laboratory (INEL) by US Department of Energy Idaho Field Office and subcontractor personnel. The installation roadmap discusses activities, issues, and installation commitments that affect waste management and environmental restoration activities at the INEL. The High-Level Waste, Land Disposal Restriction, and Environmental Restoration Roadmaps are also included

Commercial disposal options for Idaho National Engineering Laboratory low-level radioactive waste

International Nuclear Information System (INIS)

Porter, C.L.; Widmayer, D.A.

1995-09-01

The Idaho National Engineering Laboratory (INEL) is a Department of Energy (DOE)-owned, contractor-operated site. Significant quantities of low-level radioactive waste (LLW) have been generated and disposed of onsite at the Radioactive Waste Management Complex (RWMC). The INEL expects to continue generating LLW while performing its mission and as aging facilities are decommissioned. An on-going Performance Assessment process for the RWMC underscores the potential for reduced or limited LLW disposal capacity at the existing onsite facility. In order to properly manage the anticipated amount of LLW, the INEL is investigating various disposal options. These options include building a new facility, disposing the LLW at other DOE sites, using commercial disposal facilities, or seeking a combination of options. This evaluation reports on the feasibility of using commercial disposal facilities

Storage and disposition of weapons usable fissile materials (FMD) PEIS: Blending of U-233 to <12% or <5% enrichment at the Idaho National Engineering Laboratory. Data report, Draft: Version 1

International Nuclear Information System (INIS)

Shaber, E.L.

1995-08-01

Uranium-233 (U-233), a uranium isotope, is a fissionable material capable of fueling nuclear reactors or being utilized in the manufacturing of nuclear weapons. As such, it is controlled as a special nuclear material. The Idaho National Engineering Laboratory (INEL) and Oak Ridge National Laboratory (ORNL) currently store the Department of Energy's (DOE's) supply of unirradiated U-233 fuel materials. Irradiated U-233 is covered by the national spent nuclear fuel (SNF) program and is not in the scope of this report. The U-233 stored at ORNL is relatively pure uranium oxide in the form of powder or monolithic solids. This material is currently stored in stainless steel canisters of variable lengths measuring about 3 inches in diameter. The ORNL material enrichment varies with some material containing considerable amounts of U-235. The INEL material is fuel from the Light Water Breeder Reactor (LWBR) Program and consists of enriched uranium and thorium oxides in zircaloy cladding. The DOE inventory of U-233 contains trace quantities of U-232, and daughter products from the decay of U-232 and U-233, resulting in increased radioactivity over time. These increased levels of radioactivity generally result in the need for special handling considerations

Nuclear decay data measurements at the INEL ISOL facility

International Nuclear Information System (INIS)

Greenwood, R.C.; Helmer, R.G.; Putnam, M.H.; Struttmann, D.A.; Watts, K.D.

1991-01-01

In recent years, the use of the mass separation technique coupled on-line to a source of fission product nuclides has provided a wealth of new information on the nuclear decay properties of such nuclides. In addition to their relevance in basic studies of nuclear properties of neutron-rich nuclei, the fission product nuclides as a group, because of their intimate link with energy production in fission reactors, occupy a unique position in the field of applied nuclear decay data. Further, in addition to their critical role in nuclear reactor technology (decay heat source term, environmental concerns, etc.), such data have important applications in astrophysical calculations involving the rapid neutron capture process (r-process) of elemental synthesis in stellar environments. The scope of the nuclear decay data measurements being undertaken using the Idaho National Engineering Laboratory's (INEL) isotope separation on-line (ISOL) facility is focused on a systematic study of the gross nuclear decay properties of short-lived fission product isotopes, i.e., ground-state half-lives, beta-decay energies and beta-decay feeding (or beta-strength) distributions. In this paper, the authors discuss the results of new measurements of beta-decay energies and feeding distributions

The Idaho National Engineering Laboratory Site environmental report for calendar Year 1990

International Nuclear Information System (INIS)

Hoff, D.L.; Mitchell, R.G.; Moore, R.; Shaw, R.M.

1991-06-01

The results of the various monitoring programs for 1990 indicate that most radioactivity from the Idaho National Engineering Laboratory (INEL) operations could not be distinguished from worldwide fallout and natural radioactivity in the region surrounding the INEL Site. Although some radioactive materials were discharged during Site operations, concentrations and doses to the surrounding population were of no health consequence and were far less than State of Idaho and Federal health protection guidelines. The first section of the report summarizes Calendar Year 1990 and January 1 through April 1, 1991, INEL activities related to compliance with environmental regulations and laws. The balance of the report describes the surveillance program, the collection of foodstuffs at the INEL boundary and distant offsite locations, and the collection of air and water samples at onsite locations and offsite boundary and distant locations. The report also compares and evaluates the sample results and discusses implications, if any. Nonradioactive and radioactive effluent monitoring at the Site, and the US Geological Survey (USGS) ground-water monitoring program are also summarized. 33 refs., 18 figs., 29 tabs

A PC [personal computer]-based version of KENO V.a

International Nuclear Information System (INIS)

Nigg, D.A.; Atkinson, C.A.; Briggs, J.B.; Taylor, J.T.

1990-01-01

The use of personal computers (PCs) and engineering workstations for complex scientific computations has expanded rapidly in the last few years. This trend is expected to continue in the future with the introduction of increasingly sophisticated microprocessors and microcomputer systems. For a number of reasons, including security, economy, user convenience, and productivity, an integrated system of neutronics and radiation transport software suitable for operation in an IBM PC-class environment has been under development at the Idaho National Engineering Laboratory (INEL) for the past 3 yr. Nuclear cross-section data and resonance parameters are preprocessed from the Evaluated Nuclear Data Files Version 5 (ENDF/B-V) and supplied in a form suitable for use in a PC-based spectrum calculation and multigroup cross-section generation module. This module produces application-specific data libraries that can then be used in various neutron transport and diffusion theory code modules. This paper discusses several details of the Monte Carlo criticality module, which is based on the well-known highly-sophisticated KENO V.a package developed at Oak Ridge National Laboratory and previously released in mainframe form by the Radiation Shielding Information Center (RSIC). The conversion process and a variety of benchmarking results are described

Thermal treatment technology at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Hillary, J.M.

1994-01-01

Recent surveys of mixed wastes in interim storage throughout the 30-site Department of Energy complex indicate that only 12 of those sites account for 98% of such wastes by volume. Current inventories at the Idaho National Engineering Laboratory (INEL) account for 38% of total DOE wastes in interim storage, the largest of any single site. For a large percentage of these waste volumes, as well as the substantial amounts of buried and currently generated wastes, thermal treatment processes have been designated as the technologies of choice. Current facilities and a number of proposed strategies exist for thermal treatment of wastes of this nature at the INEL. High-level radioactive waste is solidified in the Waste Calciner Facility at the Idaho Central Processing Plant. Low-level solid wastes until recently have been processed at the Waste Experimental Reduction Facility (WERF), a compaction, size reduction, and controlled air incineration facility. WERF is currently undergoing process upgrading and RCRA Part B permitting. Recent systems studies have defined effective strategies, in the form of thermal process sequences, for treatment of wastes of the complex and heterogeneous nature in the INEL inventory. This presentation reviews the current status of operating facilities, active studies in this area, and proposed strategies for thermal treatment of INEL wastes

The Idaho National Engineering Laboratory Site environmental report for calendar year 1988

International Nuclear Information System (INIS)

Hoff, D.L.; Mitchell, R.G.; Moore, R.

1989-06-01

This report describes the monitoring program, the collection of foodstuffs at the Idaho National Engineering Laboratory (INEL) boundary and distant offsite locations, and the collection of air and water samples at Site locations and offsite boundary and distant locations. The report also compares and evaluates the samples results, discussing implications, if any. Significant environmental activities at the INEL Site during 1988, nonradioactive and radioactive effluent monitoring at the Site, and the US Geological Survey (USGS) ground-water monitoring program are also summarized. 42 refs., 15 figs., 12 tabs

Solidification of hazardous and mixed radioactive waste at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Boehmer, A.M.; Larsen, M.M.

1986-01-01

EG and G Idaho has initiated a program to develop treatment options for the hazardous and mixed wastes generated at the Idaho National Engineering Laboratory (INEL). This program includes development of solidification methods for some of these wastes. Testing has shown that toxic wastes can be successfully solidified using cement, cement-silicate, or ENVIROSTONE binders to produce nontoxic stable waste forms for safe, long term disposal. This paper presents the results of the solidification development program conducted at the INEL by EG and G Idaho

Solidification of hazardous and mixed radioactive waste at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Boehmer, A.M.; Larsen, M.M.

1986-03-01

EG and G Idaho has initiated a program to develop treatment options for the hazardous and mixed wastes generated at the Idaho National Engineering Laboratory (INEL). This program includes development of solidification methods for some of these wastes. Testing has shown that toxic wastes can be successfully solidified using cement, cement-silicate, or ENVIROSTONE binders to produce nontoxic stable waste forms for safe, long term disposal. This paper presents the results of the solidification development program conducted at the INEL by EG and G Idaho

Management of national nuclear power programs for assured safety. Report of visit by international participants to INEL on August 24, 1985

International Nuclear Information System (INIS)

Rouhani, S.Z.

1985-10-01

Through a special arrangement with the US State Department and support from the Department of Energy a group of high ranking officials from six different countries visited the Idaho National Engineering Laboratory on August 24, 1985. They were briefed on the highlights of the US-NRC's nuclear safety research programs at the INEL. The purpose of this project was to broadcast the advancements of the US nuclear safety technology to other nations that are at the start of major programs for peaceful use of nuclear energy in their countries

Impact and structural analysis of the INEL 55 gallon recycled shielded storage container

International Nuclear Information System (INIS)

Richins, W.D.

1996-07-01

The INEL Recycled Shielded Storage Containers (RSSC) are designed primarily for the transportation and storage of mixed RH-TRU solid waste using recycled, potentially contaminated lead and stainless steel construction materials. Two versions of the RSSC have been developed accommodating either 30 or 55 gallon drums. This report addresses the structural qualification of the 55 gallon version of the RSSC to DOT 7A Type A requirements. The controlling qualification test is a 4 ft drop onto a rigid surface. During and after this test, the container contents must remain within the container and shielding must not be reduced. The container is also designed to withstand stacking, internal pressure, lifting loads, tiedown failure, penetration, and a range of temperatures. Nonlinear dynamic finite element analyses were performed using a range of material properties. Loads in the major connections and strains in the stainless steel and lead were monitored as a function of time during impact analyses for three simulated drop orientations. Initial results were used to develop the final design. For the final design, the stainless steel and lead have maximum strains well below ultimate levels except at an impact corner where additional deformation is acceptable. The predicted loads in the connections indicate that some yielding will occur but the containment and shielding will remain intact. The results presented here provide assurance that the container will pass the DOT 7A Type A drop tests as well as the other structural requirements

Aerial radiological survey of the Idaho National Engineering Laboratory, Idaho Falls, Idaho. Date of survey: June 1982

International Nuclear Information System (INIS)

1984-02-01

An aerial radiological survey of the Idaho National Engineering Laboratory (INEL) was conducted during June 1982 by EG and G Energy Measurements, Inc. for the United States Department of Energy (DOE). The survey consisted of airborne measurements of both natural and man-made gamma radiation from the terrain surface in and around the INEL site. These measurements allowed an estimate of the distribution of isotopic concentrations in the survey area. Results are reported as isopleths superimposed on maps and photographs of the area. Gamma ray energy spectra are also presented for the net man-made radionuclides. The survey was designed to cover all of the area within a 2 mile radius of any facility at the INEL. Several areas of man-made activity were detected. These areas are all known working or storage areas which are associated with normal operations at the INEL. 3 references, 48 figures, 5 tables

Tiger Team assessment of the Idaho National Engineering Laboratory

Energy Technology Data Exchange (ETDEWEB)

Goldberg, Edward S.; Keating, John J.

1991-08-01

The Management Subteam conducted a management assessment of Environment, Safety, and Health (ES H) programs and their implementation of Idaho National Engineering Laboratory (INEL). The objectives of the assessment were to: (1) evaluate the effectiveness of existing management functions and processes in terms of ensuring environmental compliance, and the health and safety of workers and the general public; and (2) identify probable root causes for ES H findings and concerns. Organizations reviewed were DOE-Headquarters: DOE Field Offices, Chicago (CH) and Idaho (ID); Argonne Area Offices, East (AAO-E) and West (AAO-W); Radiological and Environmental Sciences Laboratory (RESL); Argonne National Laboratory (ANL); EG G Idaho, Inc. (EG G); Westinghouse Idaho Nuclear Company, Inc. (WINCO); Rockwell-INEL; MK-Ferguson of Idaho Company (MK-FIC); and Protection Technology of Idaho, Inc. (PTI). The scope of the assessment covered the following ES H management issues: policies and procedures; roles, responsibilities, and authorities; management commitment; communication; staff development, training, and certification; recruitment; compliance management; conduct of operations; emergency planning and preparedness; quality assurance; self assessment; oversight activities; and cost plus award fee processes.

Preparation and leaching of radioactive INEL waste forms

International Nuclear Information System (INIS)

Schuman, R.P.; Welch, J.M.; Staples, B.A.

1982-01-01

The purpose of this study is to prepare and leach test ceramic and glass waste form specimens produced from actual transuranic waste sludges and high-level waste calcines, respectively. Description of wastes, specimen fabrication, leaching procedure, analysis of leachates and results are discussed. The conclusion is that radioactive waste stored at INEL can be readily incorporated in fused ceramic and glass forms. Initial leach testing results indicate that these forms show great promise for safe long-term containment of radioactive wastes

The Environmental Compliance Office at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Cooper, S.C.

1990-01-01

The Idaho Operations Office of the U.S. Department of Energy (DOE-ID) has established an Environmental Compliance Office (ECO) at the Idaho National Engineering Laboratory (INEL). This office has been formed to ensure that INEL operations and activities are in compliance with all applicable environmental state and federal regulations. The ECO is headed by a DOE-ID manager and consists of several teams, each of which is led by a DOE-ID employee with members from DOE-ID, from INEL government contractors, and from DOE-ID consultants. The teams are (a) the negotiated compliance team, (b) the compliance implementation team (CIT), (c) the permits team, (d) the interagency agreement (IAG) team, (e) the consent order and compliance agreement (COCA) oversight team, and (f) the National Environmental Policy Act (NEPA) team. The last two teams were short term and have already completed their respective assignments. The functions of the teams and the results obtained by each are discussed

Hazards assessment for the INEL Landfill Complex

International Nuclear Information System (INIS)

Knudsen, J.K.; Calley, M.B.

1994-02-01

This report documents the hazards assessment for the INEL Landfill Complex (LC) located at the Idaho National Engineering Laboratory, which is operated by EG ampersand G Idaho, Inc., for the US Department of Energy (DOE). The hazards assessment was performed to ensure that this facility complies with DOE and company requirements pertaining to emergency planning and preparedness for operational emergencies. DOE Order 5500.3A requires that a facility-specific hazards assessment be performed to provide the technical basis for facility emergency planning efforts. This hazards assessment was conducted in accordance with DOE Headquarters and the DOE Idaho Operations Office (DOE-ID) guidance to comply with DOE Order 5500.3A. The hazards assessment identifies and analyzes the hazards that are significant enough to warrant consideration in a facility's operational emergency management program. The area surrounding the LC, the buildings and structures at the LC, and the processes that are used at the LC are described in this report. All hazardous materials, both radiological and nonradiological, at the LC were identified and screened against threshold quantities according to DOE Order 5500.3A guidance. Asbestos at the Asbestos Pit was the only hazardous material that exceeded its specified threshold quantity. However, the type of asbestos received and the packaging practices used are believed to limit the potential for an airborne release of asbestos fibers. Therefore, in accordance with DOE Order 5500.3A guidance, no further hazardous material characterization or analysis was required for this hazards assessment

Hazards assessment for the INEL Landfill Complex

Energy Technology Data Exchange (ETDEWEB)

Knudsen, J.K.; Calley, M.B.

1994-02-01

This report documents the hazards assessment for the INEL Landfill Complex (LC) located at the Idaho National Engineering Laboratory, which is operated by EG&G Idaho, Inc., for the US Department of Energy (DOE). The hazards assessment was performed to ensure that this facility complies with DOE and company requirements pertaining to emergency planning and preparedness for operational emergencies. DOE Order 5500.3A requires that a facility-specific hazards assessment be performed to provide the technical basis for facility emergency planning efforts. This hazards assessment was conducted in accordance with DOE Headquarters and the DOE Idaho Operations Office (DOE-ID) guidance to comply with DOE Order 5500.3A. The hazards assessment identifies and analyzes the hazards that are significant enough to warrant consideration in a facility`s operational emergency management program. The area surrounding the LC, the buildings and structures at the LC, and the processes that are used at the LC are described in this report. All hazardous materials, both radiological and nonradiological, at the LC were identified and screened against threshold quantities according to DOE Order 5500.3A guidance. Asbestos at the Asbestos Pit was the only hazardous material that exceeded its specified threshold quantity. However, the type of asbestos received and the packaging practices used are believed to limit the potential for an airborne release of asbestos fibers. Therefore, in accordance with DOE Order 5500.3A guidance, no further hazardous material characterization or analysis was required for this hazards assessment.

Storage and disposition of weapons usable fissile materials (FMD) PEIS: Blending of U-233 to {lt}12% or {lt}5% enrichment at the Idaho National Engineering Laboratory. Data report, Draft: Version 1

Energy Technology Data Exchange (ETDEWEB)

Shaber, E.L.

1995-08-01

Uranium-233 (U-233), a uranium isotope, is a fissionable material capable of fueling nuclear reactors or being utilized in the manufacturing of nuclear weapons. As such, it is controlled as a special nuclear material. The Idaho National Engineering Laboratory (INEL) and Oak Ridge National Laboratory (ORNL) currently store the Department of Energy`s (DOE`s) supply of unirradiated U-233 fuel materials. Irradiated U-233 is covered by the national spent nuclear fuel (SNF) program and is not in the scope of this report. The U-233 stored at ORNL is relatively pure uranium oxide in the form of powder or monolithic solids. This material is currently stored in stainless steel canisters of variable lengths measuring about 3 inches in diameter. The ORNL material enrichment varies with some material containing considerable amounts of U-235. The INEL material is fuel from the Light Water Breeder Reactor (LWBR) Program and consists of enriched uranium and thorium oxides in zircaloy cladding. The DOE inventory of U-233 contains trace quantities of U-232, and daughter products from the decay of U-232 and U-233, resulting in increased radioactivity over time. These increased levels of radioactivity generally result in the need for special handling considerations.

Radioactive effluent monitoring at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Simpson, O.D.

1975-01-01

The Effluent and Radiation Measurements Laboratory at the Idaho National Engineering Laboratory (INEL) has recently upgraded capabilities in the field of monitoring and analysis of radioactive airborne and liquid effluents using the techniques of gamma-ray spectrometry. The techniques and equipment used include remotely-operated, computer-based Ge(Li) spectrometers which obtain data on a real-time basis. Permanent record files are maintained of both the effluent release values and the gamma-ray data from which the release values are calculated. Should values for release levels ever be challenged, the gamma-ray spectral information for any measurement can be recalled and analyzed as needed. Daily effluent release reports are provided to operating personnel which contributes to prompt correction of any operational problems. Monthly, quarterly, and annual reports are compiled which provide inventories of the radionuclides released. A description of the effluent monitoring, reporting and records system developed at INEL for this application will be presented

Use of an isotope separator at the INEL

International Nuclear Information System (INIS)

Anderl, R.A.

1977-01-01

An electromagnetic isotope separator with a retardation lens as a collector was used to prepare highly enriched samples of Nd-143, -144, -145, -146, -148, -150, Sm-147, -149; Eu-151, -152, -153, -154. The 50 μg to 75 μg samples, deposited on 1 mil nickel foil or 0.5 mil vanadium foil, are part of a sample set to be irradiated in EBR-II as part of an integral-capture cross-section measurement program at the INEL. The isotope separator and the apparatus used for the sample preparation are described

Addressing earthquakes strong ground motion issues at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Wong, I.G.; Silva, W.J.; Stark, C.L.; Jackson, S.; Smith, R.P.

1991-01-01

In the course of reassessing seismic hazards at the Idaho National Engineering Laboratory (INEL), several key issues have been raised concerning the effects of the earthquake source and site geology on potential strong ground motions that might be generated by a large earthquake. The design earthquake for the INEL is an approximate moment magnitude (M w ) 7 event that may occur on the southern portion of the Lemhi fault, a Basin and Range normal fault that is located on the northwestern boundary of the eastern Snake River Plain and the INEL, within 10 to 27 km of several major facilities. Because the locations of these facilities place them at close distances to a large earthquake and generally along strike of the causative fault, the effects of source rupture dynamics (e.g., directivity) could be critical in enhancing potential ground shaking at the INEL. An additional source issue that has been addressed is the value of stress drop to use in ground motion predictions. In terms of site geology, it has been questioned whether the interbedded volcanic stratigraphy beneath the ESRP and the INEL attenuates ground motions to a greater degree than a typical rock site in the western US. These three issues have been investigated employing a stochastic ground motion methodology which incorporates the Band-Limited-White-Noise source model for both a point source and finite fault, random vibration theory and an equivalent linear approach to model soil response

Idaho National Engineering Laboratory (INEL) Environmental Restoration Program (ERP), Baseline Safety Analysis File (BSAF). Revision 1

Energy Technology Data Exchange (ETDEWEB)

1994-06-20

This document was prepared to take the place of a Safety Evaluation Report since the Baseline Safety Analysis File (BSAF)and associated Baseline Technical Safety Requirements (TSR) File do not meet the requirements of a complete safety analysis documentation. Its purpose is to present in summary form the background of how the BSAF and Baseline TSR originated and a description of the process by which it was produced and approved for use in the Environmental Restoration Program.The BSAF is a facility safety reference document for INEL environmental restoration activities including environmental remediation of inactive waste sites and decontamination and decommissioning (D&D) of surplus facilities. The BSAF contains safety bases common to environmental restoration activities and guidelines for performing and documenting safety analysis. The common safety bases can be incorporated by reference into the safety analysis documentation prepared for individual environmental restoration activities with justification and any necessary revisions. The safety analysis guidelines in BSAF provide an accepted method for hazard analysis; analysis of normal, abnormal, and accident conditions; human factors analysis; and derivation of TSRS. The BSAF safety bases and guidelines are graded for environmental restoration activities.

Idaho National Engineering Laboratory (INEL) Environmental Restoration Program (ERP), Baseline Safety Analysis File (BSAF). Revision 1

International Nuclear Information System (INIS)

1994-01-01

This document was prepared to take the place of a Safety Evaluation Report since the Baseline Safety Analysis File (BSAF)and associated Baseline Technical Safety Requirements (TSR) File do not meet the requirements of a complete safety analysis documentation. Its purpose is to present in summary form the background of how the BSAF and Baseline TSR originated and a description of the process by which it was produced and approved for use in the Environmental Restoration Program.The BSAF is a facility safety reference document for INEL environmental restoration activities including environmental remediation of inactive waste sites and decontamination and decommissioning (D ampersand D) of surplus facilities. The BSAF contains safety bases common to environmental restoration activities and guidelines for performing and documenting safety analysis. The common safety bases can be incorporated by reference into the safety analysis documentation prepared for individual environmental restoration activities with justification and any necessary revisions. The safety analysis guidelines in BSAF provide an accepted method for hazard analysis; analysis of normal, abnormal, and accident conditions; human factors analysis; and derivation of TSRS. The BSAF safety bases and guidelines are graded for environmental restoration activities

INEL cold test pit demonstration of improvements in information derived from non-intrusive geophysical methods over buried waste sites

International Nuclear Information System (INIS)

1994-01-01

Under contract between US DOE Idaho National Engineering Laboratory (INEL) and the Blackhawk Geosciences Division of Coleman Research Corporation (BGD-CRC), geophysical investigations were conducted to improve the detection of buried wastes. Over the Cold Test Pit (CTP) at INEL, data were acquired with multiple sensors on a dense grid. Over the CTP the interpretations inferred from geophysical data are compared with the known placement of various waste forms in the pit. The geophysical sensors employed were magnetics, frequency and time domain electromagnetics, and ground penetrating radar. Also, because of the high data density acquired, filtering and other data processing and imaging techniques were tested. After completion and analysis of the survey and interpretation over the CTP, the second phase of investigation consisted of testing geophysical methods over the Idaho Chemical Processing Plant (ICPP). The sections of the ICPP surveyed are underlain by a complex network of buried utility lines of different dimensions and composition, and with placement at various depths up to 13 ft. Further complications included many metallic objects at the surface, such as buildings, reinforced concrete pads, and debris. Although the multiple geophysical sensor approach mapped many buried utilities, they mapped far from all utilities shown on the facility drawings. This report consists of data collected from these geophysical surveys over the ICPP

Structural performance of the DOE's Idaho National Engineering Laboratory during the 1983 Borah Peak Earthquake

International Nuclear Information System (INIS)

Guenzler, R.C.; Gorman, V.W.

1985-01-01

The 1983 Borah Peak Earthquake (7.3 Richter magnitude) was the largest earthquake ever experienced by the DOE's Idaho National Engineering Laboratory (INEL). Reactor and plant facilities are generally located about 90 to 110 km (60 miles) from the epicenter. Several reactors were operating normally at the time of the earthquake. Based on detailed inspections, comparisons of measured accelerations with design levels, and instrumental seismograph information, it was concluded that the 1983 Borah Peak Earthquake created no safety problems for INEL reactors or other facilities. 10 references, 16 figures, 2 tables

Tiger Team assessment of the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

1991-08-01

The Management Subteam conducted a management assessment of Environment, Safety, and Health (ES ampersand H) programs and their implementation of Idaho National Engineering Laboratory (INEL). The objectives of the assessment were to: (1) evaluate the effectiveness of existing management functions and processes in terms of ensuring environmental compliance, and the health and safety of workers and the general public; and (2) identify probable root causes for ES ampersand H findings and concerns. Organizations reviewed were DOE-Headquarters: DOE Field Offices, Chicago (CH) and Idaho (ID); Argonne Area Offices, East (AAO-E) and West (AAO-W); Radiological and Environmental Sciences Laboratory (RESL); Argonne National Laboratory (ANL); EG ampersand G Idaho, Inc. (EG ampersand G); Westinghouse Idaho Nuclear Company, Inc. (WINCO); Rockwell-INEL; MK-Ferguson of Idaho Company (MK-FIC); and Protection Technology of Idaho, Inc. (PTI). The scope of the assessment covered the following ES ampersand H management issues: policies and procedures; roles, responsibilities, and authorities; management commitment; communication; staff development, training, and certification; recruitment; compliance management; conduct of operations; emergency planning and preparedness; quality assurance; self assessment; oversight activities; and cost plus award fee processes

A preliminary survey of the National Wetlands Inventory as mapped for the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Hampton, N.L.; Rope, R.C.; Glennon, J.M.; Moor, K.S.

1995-02-01

Approximately 135 areas within the boundaries of the Idaho National Engineering Laboratory (INEL) have been mapped as wetland habitat as part of the United States Fish and Wildlife Service (FWS) National Wetlands Inventory (NWI). A preliminary survey of these wetlands was conducted to examine their general characteristics and status, to provide an estimation of relative ecological importance, to identify additional information needed to complete ecological characterization of important INEL wetlands, and to identify high priority wetland areas on the INEL. The purpose of the survey was to provide information to support the preparation of the Environmental Restoration and Waste Management (ER ampersand WM) Environmental Impact Statement (EIS). Information characterizing general vegetation, hydrology, wildlife use, and archaeology was collected at 105 sample sites on the INEL. Sites representing NWI palustrine, lacustrine, and riverine wetlands (including manmade), and areas unmapped or unclassified by the NWI were included in the sample. The field information was used to develop a preliminary ranking of relative ecological importance for each wetland visited during this survey. Survey limitations are identified

Straddle-packer determination of the vertical distribution of hydraulic properties in the Snake River Plain Aquifer at well USGS-44, Idaho Chemical Processing Plant, INEL

International Nuclear Information System (INIS)

Monks, J.I.

1994-01-01

Many of the monitor wells that penetrate the upper portion of the Snake River Plain aquifer at the Idaho National Engineering Laboratory (INEL) are open over large intervals that include multiple water-bearing zones. Most of these wells are equipped with dedicated submersible pumps. Water of varying quality from different water-bearing zones is mixed within the wells. The hydrologic properties of individual water bearing zones are difficult to determine. Water quality and water-level data on organic, heavy metal, and radioactive contaminants have been collected, reported, and interpreted from these monitor wells for more than forty years. The problems associated with well completions over large intervals through multiple water-bearing zones raise significant questions about the data. A straddle-packer system was developed and applied at the INEL site to investigate the monitor well network. The straddle-packer system, hydraulic testing methods, data analysis procedures, and testing results are described in this report. The straddle-packer system and the straddle-packer testing and data evaluation procedures can be improved for future testing at the INEL site. Recommended improvements to the straddle-packer system are: (1) improved transducer pressure sensing systems, (2) faster opening riser valve, and (3) an in-line flowmeter in the riser pipe. Testing and data evaluation recommended improvements are: (1) simultaneous valve opening during slug tests, (2) analysis of the ratio of the times for head change and recovery to occur, (3) constant-drawdown tests of high transmissivity intervals, (4) multiple-well aquifer tests, and (5) long term head monitoring

The Intense Slow Positron Source concept: A theoretical perspective on a proposed INEL Facility

International Nuclear Information System (INIS)

Makowitz, H.; Abrashoff, J.D.; Landman, W.H.; Albano, R.K.; Tajima, T.

1992-01-01

An analysis has been performed of the INEL Intense Slow Positron Source (ISPS) concept. The results of the theoretical study are encouraging. A full-scale device with a monoenergetic 5 KeV positron beam of ≥10 12 e + /s on a ≤0.03-cmdiameter target appears feasible and can be obtained within the existing infrastructure of INEL reactor facilities. A 30.0-cm-diameter, large area source dish, moderated at first with thin crystalline W films and later by solid Ne, is proposed as the initial device in order to explore problems with a facility scale system. A demonstration scale beam at ≥10 10 slow e + /s is proposed using a 58 Co source plated on a 6-cm-diameter source dish insert, placed in a 30- cm adapter

Idaho National Engineering Laboratory installation roadmap document. Revision 1

Energy Technology Data Exchange (ETDEWEB)

1993-05-30

The roadmapping process was initiated by the US Department of Energy`s office of Environmental Restoration and Waste Management (EM) to improve its Five-Year Plan and budget allocation process. Roadmap documents will provide the technical baseline for this planning process and help EM develop more effective strategies and program plans for achieving its long-term goals. This document is a composite of roadmap assumptions and issues developed for the Idaho National Engineering Laboratory (INEL) by US Department of Energy Idaho Field Office and subcontractor personnel. The installation roadmap discusses activities, issues, and installation commitments that affect waste management and environmental restoration activities at the INEL. The High-Level Waste, Land Disposal Restriction, and Environmental Restoration Roadmaps are also included.

Idaho National Engineering Laboratory radioecology and ecology programs. 1983 progress report

International Nuclear Information System (INIS)

Markham, O.D.

1983-06-01

Progress is reported in research on: the baseline ecology of the Idaho National Engineering Laboratory (INEL), the effects of disturbance on animal and plant communities, and the behavior of radionuclides in the environment surrounding radioactive waste sites. Separate abstracts have been prepared for individual reports

Successful neural network projects at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Cordes, G.A.

1991-01-01

This paper presents recent and current projects at the Idaho National Engineering Laboratory (INEL) that research and apply neural network technology. The projects are summarized in the paper and their direct application to space reactor power and propulsion systems activities is discussed. 9 refs., 10 figs., 3 tabs

Institutional Plan, FY 1993--1998, Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

1993-01-01

This document presents the plans and goals of the Idaho National Engineering Laboratory for FY 1993--1998. Areas discussed in this document include: INEL strategic view; initiatives; scientific and technical programs; environmental, safety, and health management, technology transfer, science and math education, and community affairs; human resources; site and facilities; and resource projections

Analysis of the impacts of the 1984 Resource Conservation and Recovery Act amendments on the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Falconer, K.L.; Davis, K.D.; Johnson, R.D.; Nishimoto, D.D.; Wallace, M.T.

1986-02-01

The November 1984 Amendments to the Resource Conservation and Recovery Act (RCRA) have had, and will continue to have, a significant impact on the management of hazardous and radioactive mixed waste at the Idaho National Engineering Laboratory (INEL). These Amendments include new requirements specific to federal facilities such as the INEL. In this paper, areas of direct impact and associated INEL plans for complying with the 1984 RCRA Amendments will be described. The specific areas to be covered are the following: (1) changes in RCRA Part B permitting, including requirements for addressing past hazardous waste TSD sites; (2) the effects of increased restrictions on land disposal; (3) new requirements for undergrond tanks; (4) requirements for federal facilities; and (5) mandatory minimization of waste generation

Environmental Survey preliminary report, Idaho National Engineering Laboratory, Idaho Falls, Idaho and Component Development and Integration Facility, Butte, Montana

International Nuclear Information System (INIS)

1988-09-01

This report presents the preliminary findings of the first phase of the Environmental Survey of the United States Department of Energy's (DOE) Idaho National Engineering Laboratory (INEL) and Component Development and Integration Facility (CDIF), conducted September 14 through October 2, 1987. The Survey is being conducted by an interdisciplinary team of environmental specialists, led and managed by the Office of Environment, Safety and Health's Office of Environmental Audit. The team includes outside experts supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with the INEL and CDIF. The Survey covers all environmental media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. The on-site phase of the Survey involves the review of existing site environmental data, observations of the operations' carried on at the INEL and the CDIF, and interviews with site personnel. The Survey team developed a Sampling and Analysis (S ampersand A) Plan to assist in further assessing certain of the environmental problems identified during its on-site activities. The S ampersand A Plan will be executed by the Oak Ridge National Laboratory. When completed, the S ampersand A results will be incorporated into the INEL/CDIF Survey findings for inclusion into the Environmental Survey Summary Report. 90 refs., 95 figs., 77 tabs

Environmental Survey preliminary report, Idaho National Engineering Laboratory, Idaho Falls, Idaho and Component Development and Integration Facility, Butte, Montana

Energy Technology Data Exchange (ETDEWEB)

1988-09-01

This report presents the preliminary findings of the first phase of the Environmental Survey of the United States Department of Energy's (DOE) Idaho National Engineering Laboratory (INEL) and Component Development and Integration Facility (CDIF), conducted September 14 through October 2, 1987. The Survey is being conducted by an interdisciplinary team of environmental specialists, led and managed by the Office of Environment, Safety and Health's Office of Environmental Audit. The team includes outside experts supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with the INEL and CDIF. The Survey covers all environmental media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. The on-site phase of the Survey involves the review of existing site environmental data, observations of the operations' carried on at the INEL and the CDIF, and interviews with site personnel. The Survey team developed a Sampling and Analysis (S A) Plan to assist in further assessing certain of the environmental problems identified during its on-site activities. The S A Plan will be executed by the Oak Ridge National Laboratory. When completed, the S A results will be incorporated into the INEL/CDIF Survey findings for inclusion into the Environmental Survey Summary Report. 90 refs., 95 figs., 77 tabs.

Test plan for preparing the Rapid Transuranic Monitoring Laboratory for field deployment

International Nuclear Information System (INIS)

McIsaac, C.V.; Sill, C.W.; Gehrke, R.J.; Killian, E.W.; Watts, K.D.

1994-04-01

This plan describes experimental work that will be performed during fiscal year 1994 to prepare the Rapid Transuranic Monitoring Laboratory (RTML) for routine field use by US Department of Energy (DOE) Environmental Restoration and Waste Management programs. The RTML is a mobile, field-deployable laboratory developed at the Idaho National Engineering Laboratory (INEL) that provides a rapid, cost-effective means of characterizing and monitoring radioactive waste remediation sites for low-level radioactive contaminants. Analytical instruments currently installed in the RTML include an extended-range, germanium photon analysis spectrometer with an automatic sample changer; two, large-area, ionization chamber alpha spectrometers; and four alpha continuous air monitors. The RTML was field tested at the INEL during June 1993 in conjunction with the Buried Waste Integrated Demonstration's remote retrieval demonstration. The major tasks described in this test plan are to (a) evaluate the beta detectors for use in screening soil samples for 90 Sr, (b) upgrade the alpha spectral analysis software programs, and (c) upgrade the photon spectral analysis software programs

Idaho National Engineering Laboratory radioecology and ecology programs. 1983 progress report

Energy Technology Data Exchange (ETDEWEB)

Markham, O. D. [ed.

1983-06-01

Progress is reported in research on: the baseline ecology of the Idaho National Engineering Laboratory (INEL), the effects of disturbance on animal and plant communities, and the behavior of radionuclides in the environment surrounding radioactive waste sites. Separate abstracts have been prepared for individual reports. (ACR)

Low-level waste incineration at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Gillins, R.L.; Davis, J.N.; Maughan, R.Y.; Logan, J.A.

1985-01-01

A facility for the incineration of low-level beta/gamma contaminated combustible waste has been constructed at the Waste Experimental Reduction Facility (WERF) at the Idaho National Engineering Laboratory (INEL). The incineration facility was established to: (1) reduce the volume of currently generated contaminated combustible waste being disposed at the INEL's radioactive waste disposal site and thereby prolong the site's useful life; and (2) develop waste processing technology by providing a facility where full-size processes and equipment can be demonstrated and proven during production-scale operations. Cold systems testing has been completed, and contaminated operations began in September of 1984. Currently the facility is processing waste packaged in 2 x 2 x 2 ft cardboard boxes and measuring <10mR/h at contact. 3 figs

Idaho National Engineering Laboratory decontamination and decommissioning summary

International Nuclear Information System (INIS)

Chapin, J.A.

1981-01-01

Topics covered concern the decontamination and decommissioning (D and D) work performed at the Idaho National Engineering Laboratory (INEL) during FY 1979 and include both operations and development projects. Briefly presented are the different types of D and D projects planned and the D and D projects completed. The problems encountered on these projects and the development program recommended are discussed

The European Register of Specialists in Clinical Chemistry and Laboratory Medicine: Code of Conduct, Version 2--2008.

LENUS (Irish Health Repository)

McMurray, Janet

2009-01-01

In 1997, the European Communities Confederation of Clinical Chemistry and Laboratory Medicine (EC4) set up a Register for European Specialists in Clinical Chemistry and Laboratory Medicine. The operation of the Register is undertaken by a Register Commission (EC4RC). During the last 10 years, more than 2000 specialists in Clinical Chemistry and Laboratory Medicine have joined the Register. In 2007, EC4 merged with the Federation of European Societies of Clinical Chemistry and Laboratory Medicine (FESCC) to form the European Federation of Clinical Chemistry and Laboratory Medicine (EFCC). A Code of Conduct was adopted in 2003 and a revised and updated version, taking account particularly of the guidelines of the Conseil Européen des Professions Libérales (CEPLIS) of which EFCC is a member, is presented in this article. The revised version was approved by the EC4 Register Commission and by the EFCC Executive Board in Paris on 6 November, 2008.

Idaho National Engineering Laboratory materials in inventory natural and enriched uranium management and storage costs

International Nuclear Information System (INIS)

Nebeker, R.L.

1995-11-01

On July 13, 1994, the Office of Environmental Management (EM) was requested to develop a planning process that would result in management policies for dealing with nuclear materials in inventory. In response to this request, EM launched the Materials In Inventory (MIN) Initiative. A Headquarters Working Group was established to develop the broad policy framework for developing MIN management policies. MIN activities cover essentially all nuclear materials within the DOE complex, including such items as spent nuclear fuel, depleted uranium, plutonium, natural and enriched uranium, and other materials. In August 1995, a report discussing the natural and enriched uranium portion of the Initiative for the Idaho National Engineering Laboratory (INEL) was published. That report, 'Idaho National Engineering Laboratory Materials-in-Inventory, Natural and Enriched Uranium'.' identified MIN under the control of Lockheed Idaho Technologies Company at the INEL. Later, additional information related to the costs associated with the storage of MIN materials was requested to supplement this report. This report provides the cost information for storing, disposing, or consolidating the natural and enriched uranium portion of the MIN materials at the INEL. The information consists of eight specific tables which detail present management costs and estimated costs of future activities

Pipe damping: experimental results from laboratory tests in the seismic frequency range

International Nuclear Information System (INIS)

Ware, A.G.; Arendts, J.G.

1986-06-01

The Idaho National Engineering Laboratory (INEL) has been conducting a research program to assist the United States Nuclear Regulatory Commission (USNRC) in determining best-estimate damping values for the seismic analysis of nuclear piping systems. As part of this program, a 5-in. piping system was tested by the INEL, and data from USNRC/EPRI piping vibration tests at the ANCO Engineers facility were evaluated. These systems were subjected to various types of excitation methods and magnitudes, the support configurations were varied, and the effects of pipe insulation and internal pressure were investigated on the INEL system. The INEL has used several different methods to reduce the data to determine the damping in both these piping systems under the various test conditions. It was concluded that at representative seismic excitation levels, pressure was not a contributing factor, but the supports, insulation, and magnitude of response all were major influences contributing to damping. These tests are part of the ongoing program to determine how various parameters and data reduction methods affect piping system damping. The evaluation of all relevant test results, including these two series, will potentially lead to revised damping guidelines for the seismic analysis of nuclear plants, making them safer, less costly, and easier to inspect and maintain. The test results as well as accompanying evaluations and recommendations are presented in this report. 27 refs., 72 figs., 13 tabs

Partnerships in cleanup at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Hula, G.A.

1995-01-01

Environmental Restoration activities at the Idaho National Engineering Laboratory (INEL) are currently being conducted under a Federal Facility Agreement and Consent Order (FFA/CO). The FFA/CO was signed by the US Department of Energy-Idaho Operations Office (DOE-ID), the Environmental Protection Agency-Region 10 (EPA), and the state of Idaho Department of Health and Welfare (IDHW) in December 1991. The INEL FFA/CO has been successfully implemented due to the coordination, integration and communication among the DOE-ID, IDHW and EPA Project and WAG Managers. Successful implementation of this Tri-party Agreement hinges on one key concept: ownership of the agreement, including the routine and unexpected problems and conflicting schedules typically associated with three separate agencies. Other factors, such as (1) open and frequent communication, (2) trust among all players, (3) ''giving'' in order to ''get,'' (4) clear, concise documentation surrounding key decisions during implementation and (5) little turnover among the implementers of the Agreement, i.e., good institutional knowledge, will enhance implementation of the Agreement, but without ownership, successful implementation of the agreement may be jeopardized. This sense of ownership, as well as a sound professional working relationship between the Project and WAG Managers from each agency, has resulted in avoidance of the need for invoking the formal ''dispute resolution'' process outlined in the INEL Agreement. This facilitates timely decision-making (10 Record of Decisions have been signed to date at the INEL) which has quickly progressed the program from an ''assessment'' phase to a ''cleanup'' phase

Risk-based decision-making: A reality at the INEL

International Nuclear Information System (INIS)

Halford, V.E.; Nitschke, R.L.; Hula, G.A.

1994-01-01

Risk Analysis and Risk Management are major components of the Idaho National Engineering Laboratory's (INEL's) environmental restoration and waste management program. These tools help define responsible and cost-effective approaches to address potential human health and environmental risks from past operational practices. These techniques along with stake holder involvement, play a key role in the decision-making process which involves the US Department of Energy Idaho Operations Office (DOE), the US Environmental Protection Agency Region 10 (EPA), and the State of Idaho Department of Health and Welfare (IDHW), hereafter referred to as the agencies. An example of how this process works is Pad A, an above-ground mixed waste disposal site composed mainly of transuranic-contaminated evaporation pond salts. The site was constructed in 1972 for the disposal of solid radioactive wastes. A Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) baseline risk assessment was conducted to determine the incremental cancer risk and potential for adverse health effects to the public and the impacts to the environment if no action was performed. The risk characterization indicated that the carcinogenic risk for current and future hypothetical scenarios was below or within the NCP acceptable risk range. There was a potential 10 year window for an adverse health effect to an infant from nitrate contamination of the groundwater in about 250 years. Based on these results, a responsible and sound decision was reached to maintain and recontour the existing soil cover and to perform monitoring to confirm modeling assumptions

Incinerator development program for processing transuranic waste at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Hedahl, T.G.

1982-01-01

In the fall of 1981, two short-term tests were conducted on a controlled air and a rotary kiln incinerator to assess their potential for processing transuranic (TRU) contaminated waste at the Idaho National Engineering Laboratory (INEL). The primary purpose of the test program was a proof-of-principle verification that the incinerators could achieve near-complete combustion of the combustible portion of the waste, while mixed with high percentages of noncombustible and metal waste materials. Other important test objectives were to obtain system design information including off-gas and end-product characteristics and incinerator operating parameters. Approximately 7200 kg of simulated (non-TRU) waste from the INEL were processed during the two tests

Age dating ground water by use of chlorofluorocarbons (CCl3F and CCl2F2), and distribution of chlorofluorocarbons in the unsaturated zone, Snake River Plain aquifer, Idaho National Engineering Laboratory, Idaho

International Nuclear Information System (INIS)

Busenberg, E.; Weeks, E.P.; Plummer, L.N.; Bartholomay, R.C.

1993-04-01

Detectable concentrations of chlorofluorocarbons (CFC's) were observed in ground water and unsaturated-zone air at the Idaho National Engineering Laboratory (INEL) and vicinity. The recharge ages of waters were determined to be from 4 to more than 50 years on the basis of CFC concentrations and other environmental data; most ground waters have ages of 14 to 30 years. These results indicate that young ground water was added at various locations to the older regional ground water (greater than 50 years) within and outside the INEL boundaries. The wells drilled into the Snake River Plain aquifer at INEL sampled mainly this local recharge. The Big Lost River, Birch Creek, the Little Lost River, and the Mud Lake-Terreton area appear to be major sources of recharge of the Snake River Plain aquifer at INEL. An average recharge temperature of 9.7±1.3 degrees C (degrees Celsius) was calculated from dissolved nitrogen and argon concentrations in the ground waters, a temperature that is similar to the mean annual soil temperature of 9 degrees C measured at INEL. This similarity indicates that the aquifer was recharged at INEL and not at higher elevations that would have cooler soil temperatures than INEL. Soil-gas concentrations at Test Area North (TAN) are explained by diffusion theory

Interim status report of the TMI personnel-dosimetry project

International Nuclear Information System (INIS)

Rich, B.L.; Alvarez, J.L.; Adams, S.R.

1981-06-01

The current 2-chip TLD personnel dosimeter in use at Three Mile Island (TMI) has been shown inadequate for the anticipated high beta/gamma fields during TMI recovery operations in some areas. This project surveyed the available dosimeter systems, set up an Idaho National Engineering Laboratory (INEL) prototype system, and compared this system with those commercial systems that could be made immediately available for comparison. Of the systems tested, the new INEL personnel dosimeter was found to produce the most accurate results for use in recovery operations at TMI-2. The other multiple-chip or multiple-filter systems were found less desirable at present. The most prominent deficiencies in the INEL dosimeter stem from the fact that it lacks a completely automated reader and its x-ray and thermal neutron responses require additional development. A automated prototype reader system may be in operation by the end of CY-1981. Three alternatives for operational dosimetry are discussed. A combination of a modified version of the presently used Harshaw 2-chip dosimeter and the INEL dosimeter is recommended

A summary of the environmental restoration program Retrieval Demonstration Project at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

McQuary, J.

1991-01-01

This document summarizes the of retrieval techniques developed to excavate buried transuranic (TRU) mixed waste from the Subsurface Disposal Area (SDA). The SDA is located at the Idaho National Engineering Laboratory (INEL) in the Radioactive Waste Management Complex (RWMC). 31 refs., 1 fig

Technical issues associated with in situ vitrification of the INEL Subsurface Disposal Area

International Nuclear Information System (INIS)

Stoots, C.M.; Bates, S.O.; Callow, R.A.; Campbell, K.A.; Farnsworth, R.K.; Krisman, G.K.; McKellar, M.G.; Nickelson, D.F.; Slater, C.E.

1992-07-01

In situ vitrification (ISV) has been identified as an alternative technology for remediation of the acid pit and transuranic pits and trenches (TRU-PTs) at the Idaho National Engineering Laboratory (INEL) Subsurface Disposal Area (SDA). However, a number of technical issues must be resolved before ISV can be considered applicable to these waste sites. To assist in the ISV technology evaluation, an ISV Steering Committee was formed to identify, prioritize, and develop closure roadmaps for technical issues lated with ISV application at the SDA. The activities of the ISV Steering Committee are summarized in a three-volume report. Volume I identifies the systematic approach used to identify and prioritize the ISV technical issues and briefly discusses the methodology that will be employed to resolve these issues. Volumes 2 and 3 discuss each technical issue in greater detail and suggest specific closure roadmaps to be used in resolving technical issues associated with ISV at the SDA Acid Pit and TRU-PTS, respectively. The three-volume report is a working document that will be updated as necessary to reflect current evaluation strategy for the ISV technology. This is Volume 3

Geophysical surveys for buried waste detection at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Sandness, G.A.; Rising, J.L.; Kimbrough, J.R.

1979-12-01

This report describes a series of geophysical surveys performed at the Idaho National Engineering Laboratory (INEL). The main purpose of the surveys was to evaluate techniques, principally ground-penetrating radar, for detecting and mapping radioactive wastes buried in shallow trenches and pits. A second purpose was to determine the feasibility of using ground-penetrating radar to measure the depth of basalt bedrock. A prototype geophyscal survey system developed by the US Department of Energy's Pacific Northwest Laboratory was used for this study. Radar, magnetometer, and metal detector measurements were made at three sites in the Radioactive Waste Management Complex (RWMC) at INEL. Radar measurements were made at fourth site adjacent to the RWMC. The combination of three geophysical methods was shown to provide considerable information about the distribution of buried waste materials. The tests confirmed the potential effectiveness of the radar method, but they also pointed out the need for continued research and development in ground-penetrating radar technology. The radar system tested in this study appears to be capable of measuring the depth to basalt in the vicinity of the RWMC

Survey and analysis of materials research and development at selected federal laboratories

Energy Technology Data Exchange (ETDEWEB)

Reed, J.E.; Fink, C.R.

1984-04-01

This document presents the results of an effort to transfer existing, but relatively unknown, materials R and D from selected federal laboratories to industry. More specifically, recent materials-related work at seven federal laboratories potentially applicable to improving process energy efficiency and overall productiviy in six energy-intensive manufacturing industries was evaluated, catalogued, and distributed to industry representatives to gauge their reaction. Laboratories surveyed include: Air Force Wright Aeronautical Laboratories Material Laboratory (AFWAL). Pacific Northwest Laboratory (PNL), National Aeronautics and Space Administration Marshall Flight Center (NASA Marshall), Oak Ridge National Laboratory (ORNL), Brookhaven National Laboratory (BNL), Idaho National Engineering Laboratory (INEL), and Jet Propulsion Laboratory (JPL). Industries included in the effort are: aluminum, cement, paper and allied products, petroleum, steel and textiles.

Chlorine-36 in the Snake River Plain aquifer at the Idaho National Engineering Laboratory: Origin and implications

International Nuclear Information System (INIS)

Beasley, T.M.; Cecil, L.D.; Mann, L.J.; Sharma, P.; Fehn, U.; Gove, H.E.; Kubik, P.W.

1993-01-01

Between 1952 and 1984, low-level radioactive waste was introduced directly into the Snake River Plain aquifer at the Idaho National Engineering Laboratory (INEL), Idaho Falls, Idaho. These wastes were generated, principally, at the nuclear fuel reprocessing facility on the site. The measurements of 36 Cl in monitoring and production well waters, downgradient from disposal wells and seepage ponds, found easily detectable, nonhazardous concentrations of this radionuclide from the point of injection to the INEL southern site boundary. Comparisons are made between 3 H and 36 Cl concentrations in aquifer water and the advantages of 36 Cl as a tracer of subsurface-water dynamics at the site are discussed

Chlorine-36 in the Snake River Plain Aquifer at the Idaho National Engineering Laboratory; origin and implications

Science.gov (United States)

Beasley, T.M.; Cecil, L.D.; Sharma, P.; Kubik, P.W.; Fehn, U.; Mann, L.J.; Gove, H.E.

1993-01-01

Between 1952 and 1984, low-level radioactive waste was introduced directly into the Snake River Plain aquifer at the Idaho National Engineering Laboratory (INEL), Idaho Falls, Idaho. These wastes were generated, principally, at the nuclear fuel reprocessing facility on the site. Our measurements of 36C1 in monitoring and production well waters, downgradient from disposal wells and seepage ponds, found easily detectable, nonhazardous concentrations of this radionuclide from the point of injection to the INEL southern site boundary. Comparisons are made between 3H and 36Cl concentrations in aquifer water and the advantages of 36C1 as a tracer of subsurface-water dynamics at the site are discussed.

INEL cold test pit demonstration of improvements in information derived from non-intrusive geophysical methods over buried waste sites

International Nuclear Information System (INIS)

1994-01-01

Under Contract between US DOE Idaho National Engineering Laboratory (INEL) and the Blackhawk Geosciences Division of Coleman Research Corporation (BGD-CRC), geophysical investigations were conducted to improve the detection of buried wastes. Site characterization is a costly and time consuming process with the most costly components being drilling, sampling, and chemical analysis of samples. There is a focused effort at US DOE and other agencies to investigate methodologies that reduce costs and shorten the time between characterization and clean-up. These methodologies take the form of employing non-invasive (geophysical) and minimal invasive (e.g., cone penetrometer driving) techniques of characterization, and implementing a near real-time, rational decision-making process (Expedited Site Characterization). Over the Cold Test Pit (CTP) at INEL, data were acquired with multiple sensors on a dense grid. Over the CTP the interpretations inferred from geophysical data are compared with the known placement of various waste forms in the pit. The geophysical sensors employed were magnetics, frequency and time domain electromagnetics, and ground penetrating radar. Also, because of the high data density acquired, filtering and other data processing and imaging techniques were tested. The conclusions derived from the geophysical surveys were that pit boundaries, berms between cells within the pit, and individual objects placed in the pit were best mapped by the new Geonics EM61 time domain EM metal detector. Part of the reason for the effectiveness of the time domain metal detector is that objects buried in the pit are dominantly metallic. Also, the utility of geophysical data is significantly enhanced by dimensional and 3-dimensional imaging formats. These images will particularly assist remediation engineers in visualizing buried wastes

Hydrologic conditions and distribution of selected radiochemical and chemical constituents in water, Snake River Plain aquifer, Idaho National Engineering Laboratory, Idaho, 1992 through 1995

International Nuclear Information System (INIS)

Bartholomay, R.C.; Tucker, B.J.; Ackerman, D.J.; Liszewski, M.J.

1997-04-01

Radiochemical and chemical wastewater discharged since 1952 to infiltration ponds and disposal wells at the Idaho National Engineering Laboratory (INEL) has affected water quality in the Snake River Plain aquifer. The US Geological Survey, in cooperation with the US Department of Energy, maintains a monitoring network at the INEL to determine hydrologic trends and to delineate the movement of radiochemical and chemical wastes in the aquifer. This report presents an analysis of water-level and water-quality data collected from the Snake River Plain aquifer during 1992--95

Idaho National Engineering Laboratory Waste Area Groups 1-7 and 10 Technology Logic Diagram

International Nuclear Information System (INIS)

O'Brien, M.C.; Meservey, R.H.; Little, M.; Ferguson, J.S.; Gilmore, M.C.

1993-09-01

The Idaho National Engineering Laboratory (INEL) Technology Logic Diagram (TLD) was developed to provide a decision support tool that relates Environmental Restoration (ER) and Waste Management (WM) problems at the INEL to potential technologies that can remediate these problems. The TLD identifies the research, development, demonstration, testing, and evaluation needed to develop these technologies to a state that allows technology transfer and application to an environmental restoration need. It is essential that follow-on engineering and system studies be conducted to build on the output of this project. These studies will begin by selecting the most promising technologies identified in this TLD and finding an optimum mix of technologies that will provide a socially acceptable balance between cost and risk to meet the site windows of opportunity. The TLD consists of three separate volumes: Volume I includes the purpose and scope of the TLD, a brief history of the INEL Waste Area Groups, and environmental problems they represent. A description of the TLD, definitions of terms, a description of the technology evaluation process, and a summary of each subelement, is presented. Volume II (this volume) describes the overall layout and development of the TLD in logic diagram format. This section addresses the environmental restoration of contaminated INEL sites. Specific INEL problem areas/contaminants are identified along with technology solutions, the status of the technologies, precise science and technology needs, and implementation requirements. Volume III provides the Technology Evaluation Data Sheets (TEDS) for Environmental Restoration and Waste Management (EM) activities that are referenced by a TEDS codenumber in Volume II. Each of these sheets represents a single logic trace across the TLD. These sheets contain more detail than provided for technologies in Volume II

Long-range plan for buried transuranic waste studies at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Low, J.O.

1985-12-01

This document presents a plan to perform detailed studies of alternatives considered for the long-term management of buried transuranic waste at the Idaho National Engineering Laboratory (INEL). The studies will provide the technical basis for DOE to make a decision on the future management of that waste. Although the waste is currently being handled in an acceptable manner, new solutions are continually being researched to improve management techniques. Three alternatives are being considered: (a) leave the waste as is; (b) improve in situ confinement of the waste; and (c) retrieve, process, and certify the waste for disposal at a federal repository. Fourteen studies are described in this plan for Alternatives 2 and 3. The leave-as-is alternative involves continuing present procedures for managing the buried waste. An ongoing environmental surveillance program, a low-level-waste stabilization program, and enhanced subsurface migration studies begun in FY-1984 at the INEL will provide data for the decision-making process for the INEL buried TRU waste. These ongoing studies for the leave-as-is alternative are summarized in this plan in limited detail. The improved-confinement alternative involves leaving the waste in place, but providing additional protection against wind, water penetration, erosion, and plant and animal intrusion. Several studies proposed under this alternative will examine special techniques to immobilize or encapsulate the buried waste. An in situ grouting study was implemented at the INEL starting in FY-1985 and will be completed at the end of FY-1986 with the grouting of a simulated INEL buried TRU waste trench. Studies of the third alternative will investigate improved retrieval, processing, and certification techniques. New equipment, such as industrial manipulators and excavating machinery, will be tested in the retrieval studies. Processing and certification studies will examine rapidly changing or new technologies

Immobilization of INEL low-level radioactive wastes in ceramic containment materials

International Nuclear Information System (INIS)

Seymour, W.C.; Kelsey, P.V.

1978-11-01

INEL low-level radioactive wastes have an overall chemical composition that lends itself to self-containment in a ceramic-based material. Fewer chemical additives would be needed to process the wastes than to process high-level wastes or use a mixture containment method. The resulting forms of waste material could include a basalt-type glass or glass ceramic and a ceramic-type brick. Expected leach resistance is discussed in relationshp to data found in the literature for these materials and appears encouraging. An overview of possible processing steps for the ceramic materials is presented

Magnetotelluric soundings on the Idaho National Engineering Laboratory facility, Idaho

International Nuclear Information System (INIS)

Stanley, W.D.

1982-01-01

The magnetotelluric (MT) method was used as one of several geophysical tools to study part of the Idaho Engineering Laboratory (INEL) facility. The purpose of the geophysical study on INEL was to investigate the facility for a possible site to drill a geothermal exploration well. The initial interpretation of the MT sounding data was done with one-dimensional models consisting of four or five layers, the minimum number required to fit the data. After the test well (INEL-1) was completed, the electric log was used to guide an improved one-dimensional ID interpretation of the MT sounding data. Profile models derived from the well log provided good agreement with velocity models derived from refraction seismic data. A resolution study using generalized inverse techniques shows that the resolution of resistive layers in the lower part of the MT models is poor, as is the definition of a shallow, altered basalt unit. The only major structure observed on the MT data was the faulted contact between the SNRP and basin and range structures on the west. Modeling of the data near this structure with a two-dimensional computer program showed that the MT data near the fault require a model similar to the seismic refraction models and that structure on a deep crustal conductor is also required

Idaho National Engineering Laboratory release criteria for decontamination and decommissioning

International Nuclear Information System (INIS)

Dolenc, M.R.; Case, M.J.

1986-01-01

Criteria have been developed for release of Idaho National Engineering Laboratory (INEL) facilities and land areas following decontamination and decommissioning (D and D). Decommissioning release criteria in the form of dose guidelines were proposed by the US Nuclear Regulatory Commission as early as 1980. These criteria were used on an interim basis for INEL D and D projects. However, dose guidelines alone do not adequately cover the criteria necessary to release sites for unrestricted use. In actual practice, other parameters such as pathways analyses, sampling and instrumentation techniques, and implementation procedures are required to develop the basis for unrestricted release of a site. Thus, a rigorous approach for evaluating these other parameters is needed to develop acceptable D and D release criteria. Because of the complex and sensitive nature of the dose and pathways analyses work, a thorough review by experts in those respective fields was desired. Input and support in preparing or reviewing each part of the criteria development task was solicited from several DOE field offices. Experts were identified and contracted to assist in preparing portions of the release criteria, or to serve on a peer-review committee. Thus, the entire release criteria development task was thoroughly reviewed by recognized experts from each DOE field office, to validate technical content of the INEL site-specific document

Annual report on monitoring of the unsaturated zone and recharge areas at INEL to the state of Idaho INLEL Oversight COmmittee

International Nuclear Information System (INIS)

Horn, D.; Liou, J.; Finnie, J.

1993-03-01

This project, begun in March 1991, was originally structured as two separate research efforts: An investigation of the recharge phenomenon and surface water-ground water interactions at the INEL; and a study of water and contaminant movement through the unsaturated zone, including a review of computer models used to described this process. During the initial months of work, it became obvious to those involved in these studies that the two topic areas were intimately related, and work since that time has proceeded with no firm boundaries between the two efforts. Much of the Phase I work (March 1991--March 1992) consisted of a detailed review of available literature pertinent to the two research topics and to the INEL site. This Annual Report summarizes the other project activities during Phase III, and is organized into three sections: Section I -- an overview of the ongoing efforts related to computer model algorithms and data requirements for modeling the transport process in the unsaturated zone (Dr. Jim Liou). Section H -- a review of ongoing work to predict the growth and decay of the ground water mound beneath the INEL spreading basins, using the computer model UNSAT-2 (Dr. John Finnie). Section M -- a final report of the completed study effort examining the recharge rates associated with stream flow in the Big Lost River, and the effects of this recharge on ground water levels at the INEL site (Dr. Dennis Horn). Phase M of the project has now begun, and will conclude in December 1993 with two final reports documenting the work that has been briefly described in Sections I and H of this report

Management of citation verification requests for multiple projects at Sandia National Laboratories

International Nuclear Information System (INIS)

Crawford, C.S.

1995-01-01

Sandia National Laboratories' (SNL) Technical Library is now responsible for providing citation verification management support for all references cited in technical reports issued by the Nuclear Waste Management (NWM) Program. This paper dancing how this process is managed for the Yucca Mountain Site Characterization (YWP), Waste Isolation Pilot Plant (WIPP), Idaho National Engineering Laboratory (INEL), and Greater Confinement Disposal (GCD) projects. Since technical reports are the main product of these projects, emphasis is placed on meeting the constantly evolving needs of these customers in a timely and cost-effective manner

The INEL Human Reliability Program: The first two years of experience

International Nuclear Information System (INIS)

Minner, D.E.

1986-01-01

This paper provides a review of the design, implementation, and operation of the INEL Human Reliability Program from January 1984 through June of 1986. Human Reliability Programs are defined in terms of the ''insider threat'' to security of nuclear facilities. The design of HRP's are discussed with special attention given the special challenge of the disgruntled employee. Each component of an HRP is reviewed noting pitfalls and opportunities with each: drug testing of applicants and incumbents, psychological evaluation by management, security clearance procedures and administration including the use of an Employee Review Board to recommend action prior to final management decision

INEL test reactor facility alarms: descriptions, technical specifications, and modification procedure

International Nuclear Information System (INIS)

Potash, L.M.; Boone, M.P.

1980-04-01

This report identifies standards, procedures, and practices which will affect any attempt to integrate or introduce human engineering principles into nuclear power plant alarm systems. Additional information concerning type of signal used, expected reaction, type of sensor, etc., is presented because of its relevance to future work on alarm system integration. The INEL test reactors were studied. Interviews were conducted with operators, designers, and management personnel. Additional information was obtained from available documentation. Only fire-alarm systems, and to a lesser extent, criticality alarms, have detailed industry-wide standards. One general standard has been written for control-room annunciators

Idaho National Engineering Laboratory Waste Area Groups 1-7 and 10 Technology Logic Diagram. Volume 2

Energy Technology Data Exchange (ETDEWEB)

O`Brien, M.C.; Meservey, R.H.; Little, M.; Ferguson, J.S.; Gilmore, M.C.

1993-09-01

The Idaho National Engineering Laboratory (INEL) Technology Logic Diagram (TLD) was developed to provide a decision support tool that relates Environmental Restoration (ER) and Waste Management (WM) problems at the INEL to potential technologies that can remediate these problems. The TLD identifies the research, development, demonstration, testing, and evaluation needed to develop these technologies to a state that allows technology transfer and application to an environmental restoration need. It is essential that follow-on engineering and system studies be conducted to build on the output of this project. These studies will begin by selecting the most promising technologies identified in this TLD and finding an optimum mix of technologies that will provide a socially acceptable balance between cost and risk to meet the site windows of opportunity. The TLD consists of three separate volumes: Volume I includes the purpose and scope of the TLD, a brief history of the INEL Waste Area Groups, and environmental problems they represent. A description of the TLD, definitions of terms, a description of the technology evaluation process, and a summary of each subelement, is presented. Volume II (this volume) describes the overall layout and development of the TLD in logic diagram format. This section addresses the environmental restoration of contaminated INEL sites. Specific INEL problem areas/contaminants are identified along with technology solutions, the status of the technologies, precise science and technology needs, and implementation requirements. Volume III provides the Technology Evaluation Data Sheets (TEDS) for Environmental Restoration and Waste Management (EM) activities that are referenced by a TEDS codenumber in Volume II. Each of these sheets represents a single logic trace across the TLD. These sheets contain more detail than provided for technologies in Volume II.

Development of a cumulative risk assessment for the Idaho National Engineering Laboratory's waste area group 2

International Nuclear Information System (INIS)

Burns, D.E.

1995-01-01

In 1989, the Idaho National Engineering Laboratory (INEL) was added to the Environmental Protection Agency's (EPA) National Priorities List of Superfund sites. A Federal Facility Agreement and Consent Order (FFA/CO) for the INEL was signed by the Department of Energy, Idaho Operations Office (DOE-ID), EPA, and the State of Idaho in December 1991. The goal of this agreement is to ensure that potential or actual INEL releases of hazardous substances to the environment are thoroughly investigated in accordance with the National Contingency Plan (NCP) and that appropriate response actions are taken as necessary to protect human health and the environment. The Test Reactor Area (TRA) is included as Waste Area Group (WAG) 2 of ten INEL WAGs identified in the FFA/CO. WAG 2 consists of 13 operable units (OUs) which include pits, tanks, rubble piles, ponds, cooling towers, wells, french drains, perched water and spill areas. OU 2-13 is the Comprehensive Remedial Investigation/Feasibility Study (RI/FS) for WAG 2. The study presented here is a preliminary evaluation of the comprehensive risk for WAG-2. This investigation will be used as the basis of the WAG-2 comprehensive baseline risk assessment (BRA), and it will serve as a model for other INEL comprehensive risk assessments. The WAG-2 preliminary risk evaluation consisted of two broad phases. These phases were (1) a site and contaminant screening that was intended to support the identification of COPCs and risk assessment data gaps, and (2) an exposure pathway analysis that evaluated the comprehensive human health risks associated with WAG-2. The primary purposes of the investigation were to screen WAG-2 release sites and contaminants, and to identify risk assessment data gaps, so the investigation will be referred to as the WAG-2 Screening and Data Gap Analysis (SDGA) for the remainder of this report

TIDBIT - the INEL database of BNCT information and treatment

International Nuclear Information System (INIS)

Mancuso, C.A.

1995-01-01

The INEL Database of BNCT Information and Treatment (TIDBIT) has been under development for several years. Late in 1993, a new software development team took over the project and did and assessment of the current implementation status, and determined that the user interface was unsatisfactory for the expected users and that the data structures were out of step with the current state of reality. The team evaluated several tools that would improve the user interface to make the system easier to use. Uniface turned out to be the product of choice. During 1994, TIDBIT got its name, underwent a complete change of appearance, had a major overhaul to the data structures that support the application, and system documentation was begun. A prototype of the system was demonstrated in September 1994

Hydrologic conditions and distribution of selected radiochemical and chemical constituents in water, Snake River Plain aquifer, Idaho National Engineering Laboratory, Idaho, 1989 through 1991

International Nuclear Information System (INIS)

Bartholomay, R.C.; Orr, B.R.; Liszewski, M.J.; Jensen, R.G.

1995-08-01

Radiochemical and chemical wastewater discharged since 1952 to infiltration ponds and disposal wells at the Idaho National Engineering Laboratory (INEL) has affected water quality in the Snake River Plain aquifer. The U.S. Geological Survey, in cooperation with the U.S. Department of Energy, maintains a continuous monitoring network at the INEL to determine hydrologic trends and to delineate the movement of radiochemical and chemical wastes in the aquifer. This report presents an analysis of water-level and water-quality data collected from the Snake River Plain aquifer during 1989-91. Water in the eastern Snake River Plain aquifer moves principally through fractures and interflow zones in basalt, generally flows southwestward, and eventually discharges at springs along the Snake River. The aquifer is recharged principally from irrigation water, infiltration of streamflow, and ground-water inflow from adjoining mountain drainage basins. Water levels in wells throughout the INEL generally declined during 1989-91 due to drought. Detectable concentrations of radiochemical constituents in water samples from wells in the Snake River Plain aquifer at the INEL decreased or remained constant during 1989-91. Decreased concentrations are attributed to reduced rates of radioactive-waste disposal, sorption processes, radioactive decay, and changes in waste-disposal practices. Detectable concentrations of chemical constituents in water from the Snake River Plain aquifer at the INEL were variable during 1989-91. Sodium and chloride concentrations in the southern part of the INEL increased slightly during 1989-91 because of increased waste-disposal rates and a lack of recharge from the Big Lost River. Plumes of 1,1,1-trichloroethane have developed near the Idaho Chemical Processing Plant and the Radioactive Waste Management Complex as a result of waste disposal practices

Idaho National Engineering Laboratory Waste Area Groups 1-7 and 10 Technology Logic Diagram

International Nuclear Information System (INIS)

O'Brien, M.C.; Meservey, R.H.; Little, M.; Ferguson, J.S.; Gilmore, M.C.

1993-09-01

The Idaho National Engineering Laboratory (INEL) Technology Logic Diagram (TLD) was developed to provide a decision support tool that relates Environmental Restoration (ER) and Waste Management (WM) problems at the INEL to potential technologies that can remediate these problems. The TLD identifies the research, development, demonstration, testing, and evaluation needed to develop these technologies to a state that allows technology transfer and application to an environmental restoration need. It is essential that follow-on engineering and system studies be conducted to build on the output of this project. These studies will begin by selecting the most promising technologies identified in this TLD and finding an optimum mix of technologies that will provide a socially acceptable balance between cost and risk to meet the site windows of opportunity. The TLD consists of three separate volumes: Volume I includes the purpose and scope of the TLD, a brief history of the INEL Waste Area Groups, and environmental problems they represent. A description of the TLD, definitions of terms, a description of the technology evaluation process, and a summary of each subelement, is presented. Volume II describes the overall layout and development of the TLD in logic diagram format. This section addresses the environmental restoration of contaminated INEL sites. Volume III (this volume) provides the Technology Evaluation Data Sheets (TEDS) for Environmental Restoration and Waste Management (EM) activities that are reference by a TEDS code number in Volume II. Each of these sheets represents a single logic trace across the TLD. These sheets contain more detail than provided for technologies in Volume II. Data sheets are arranged alphanumerically by the TEDS code number in the upper right corner of each sheet

Safety analysis report for the mixed waste storage facility and portable storage units at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Peatross, R.

1997-01-01

The Mixed Waste Storage Facility (MWSF) including the Portable Storage Units (PSUs) is a government-owned contractor-operated facility located at the Idaho National Engineering Laboratory (INEL). Lockheed Martin Idaho Technologies Company (LMITCO) is the current operating contractor and facility Architect/Engineer as of September 1996. The operating contractor is referred to as open-quotes the Companyclose quotes or open-quotes Companyclose quotes throughout this document. Oversight of MWSF is provided by the Department of Energy Idaho Operations Office (DOE-ID). The MWSF is located in the Power Burst Facility (PBF) Waste Reduction Operations Complex (WROC) Area, approximately 10.6 km (6.6 mi) from the southern INEL boundary and 4 km (2.5 mi) from U.S. Highway 20

Applicability of a generic monitoring program for radioactive waste burial grounds at Oak Ridge National Laboratory and Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

1978-07-01

Six burial grounds were evaluated at Oak Ridge to determine which would be most suitable for testing the generic monitoring approach, and two were selected. Burial Ground 4 was chosen because it is known to be leaking radioactivity and a monitoring program is desirable to determine the source, pattern and extent of the leakage. Burial Ground 6 was chosen because the most complete radiologic and geologic data is available and modern burial practices have been utilized at this site. At the Idaho National Engineering Laboratory (INEL) only one burial ground exists, the Radioactive Waste Management Complex (RWMC). The data available on the burial grounds are insufficient for an adequate understanding of radionuclide migration patterns and accordingly, inadequate for the design of reliable monitoring programs. It was decided, therefore, that preliminary monitoring programs should be designed in order to obtain additional data for a later implementation of reliable monitoring programs. The monitoring programs designed for ORNL consist primarily of the installation of surface water monitoring stations, the surveillance of trench sump wells, a test boring program to study subsurface geologic conditions, a ground water sampling program and the installation of instrumentation, specifically infiltrometers and evaporation pans, to develop data on site water balances. The program designed for the INEL burial ground includes installation of trench sumps, a ground water monitoring program, test borings to further define subsurface geohydrologic conditions and the installation of instrumentation to develop data on the site water balance. The estimated costs of implementing the recommended programs are about $420,820 for monitoring Burial Grounds 4 and 6 at Oak Ridge and $382,060 for monitoring the RWMC at INEL. 12 figures

Quality assurance on the Idaho National Engineering Laboratory Buried Waste Program

International Nuclear Information System (INIS)

Rasmussen, T.L.

1989-01-01

This paper discusses the clean-up of an Idaho National Engineering Laboratory (INEL) site utilized for disposal of transuranic contaminated waste from 1954 until 1970. The author presents requirements of the environmental protection statutes that have generated quality assurance requirements in addition to those historically implemented as a part of facility design, construction and operation. A hierarchy of program guidance quality documentation and procedures is discussed. Data qualification and computer database management are identified as requirements

User's Guide: Database of literature pertaining to the unsaturated zone and surface water-ground water interactions at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Hall, L.F.

1993-05-01

Since its beginnings in 1949, hydrogeologic investigations at the Idaho National Engineering Laboratory (INEL) have resulted in an extensive collection of technical publications providing information concerning ground water hydraulics and contaminant transport within the unsaturated zone. Funding has been provided by the Department of Energy through the Department of Energy Idaho Field Office in a grant to compile an INEL-wide summary of unsaturated zone studies based on a literature search. University of Idaho researchers are conducting a review of technical documents produced at or pertaining to the INEL, which present or discuss processes in the unsaturated zone and surface water-ground water interactions. Results of this review are being compiled as an electronic database. Fields are available in this database for document title and associated identification number, author, source, abstract, and summary of information (including types of data and parameters). AskSam reg-sign, a text-based database system, was chosen. WordPerfect 5.1 copyright is being used as a text-editor to input data records into askSam

A comparison of the costs of treating wastes from a radio analytical laboratory

International Nuclear Information System (INIS)

Moore, R.

1996-01-01

The Radiological and Environmental Sciences Laboratory (RESL) is a government-owned, government-operated facility at the Idaho National Engineering Laboratory (INEL). RESL's traditional strengths are in precise radionuclide analysis and dosimetry measurements. RESL generates small quantities of various types of waste. This study identified potential waste management options for a solvent extraction process waste stream and the cost differences resulting from either process changes, improved technology usage, or material substitutions or changes at RESL. Where possible, this report identifies changes that have resulted or may result in waste reduction and cost savings. DOE P2 directs the lab to review processes, evaluate waste practices, and estimate potential reductions in waste volumes and waste management costs. This study focused on selected processes, but the processes are illustrative of potential waste volume reductions and cost minimizations that may be achieved elsewhere at the INEL and throughout the DOE complex. In analyzing a waste disposal process, the authors allocated component costs to functional categories. These categories included the following: (1) operational costs, included waste generation and collection into a storage area; (2) administrative costs, including worker training, routine inspections, and reporting; and (3) disposal costs, including preparing the waste for shipment and disposing of it

Buried waste remote survey of the Idaho National Engineering Laboratory subsurface disposal area

International Nuclear Information System (INIS)

Richardson, B.S.; Noakes, M.W.; Griebenow, B.E.; Josten, N.E.

1991-01-01

Burial site characterization is an important first step in the restoration of subsurface disposal sites. Testing and demonstration of technology for remote buried waste site characterization were performed at the Idaho National Engineering Laboratory (INEL) by a team from five US Department of Energy (DOE) laboratories. The US Army's Soldier Robot Interface Project (SRIP) vehicle, on loan to the Oak Ridge National Laboratory (ORNL), was used as a remotely operated sensor platform. The SRIP was equipped with an array of sensors including terrain conductivity meter, magnetometer, ground-penetrating radar (GPR), organic vapor detector, gamma-based radar detector, and spectrum analyzer. The testing and demonstration were successfully completed and provided direction for future work in buried waste site characterization

Remedial design and remedial action guidance for the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

1993-10-01

The US Department of Energy, Idaho Operations Office (DOE-ID), the US Environmental Protection Agency, Region X (EPA), and the Idaho Department of Health and Welfare (IDHW) have developed this guidance on the remedial design and remedial action (RD/RA) process. This guidance is applicable to activities conducted under the Idaho National Engineering Laboratory (INEL) Federal Facility Agreement and Consent Order (FFA/CO) and Action Plan. The INEL FFA/CO and Action Plan provides the framework for performing environmental restoration according to the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA). The guidance is intended for use by the DOE-ID, the EPA, and the IDHW Waste Area Group (WAG) managers and others involved in the planning and implementation of CERCLA environmental restoration activities. The scope of the guidance includes the RD/RA strategy for INEL environmental restoration projects and the approach to development and review of RD/RA documentation. Chapter 2 discusses the general process, roles and responsibilities, and other elements that define the RD/RA strategy. Chapters 3 through 7 describe the RD/RA documents identified in the FFA/CO and Action Plan. Chapter 8 provides examples of how this guidance can be applied to restoration projects. Appendices are included that provide excerpts from the FFA/CO pertinent to RD/RA (Appendix A), a applicable US Department of Energy (DOE) orders (Appendix B), and an EPA Engineering ''Data Gaps in Remedial Design'' (Appendix C)

Radiological, physical, and chemical characterization of transuranic wastes stored at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Apel, M.L.; Becker, G.K.; Ragan, Z.K.; Frasure, J.; Raivo, B.D.; Gale, L.G.; Pace, D.P.

1994-03-01

This document provides radiological, physical and chemical characterization data for transuranic radioactive wastes and transuranic radioactive and hazardous (i.e., mixed) wastes stored at the Idaho National Engineering Laboratory and considered for treatment under the Private Sector Participation Initiative Program (PSPI). Waste characterization data are provided in the form of INEL Waste Profile Sheets. These documents provide, for each content code, information on waste identification, waste description, waste storage configuration, physical/chemical waste composition, radionuclide and associated alpha activity waste characterization data, and hazardous constituents present in the waste. Information is provided for 139 waste streams which represent an estimated total volume of 39,380 3 corresponding to a total mass of approximately 19,000,000 kg. In addition, considerable information concerning alpha, beta, gamma, and neutron source term data specific to Rocky Flats Plant generated waste forms stored at the INEL are provided to assist in facility design specification

Idaho National Engineering Laboratory Waste Area Groups 1-7 and 10 Technology Logic Diagram. Volume 3

Energy Technology Data Exchange (ETDEWEB)

O`Brien, M.C.; Meservey, R.H.; Little, M.; Ferguson, J.S.; Gilmore, M.C.

1993-09-01

The Idaho National Engineering Laboratory (INEL) Technology Logic Diagram (TLD) was developed to provide a decision support tool that relates Environmental Restoration (ER) and Waste Management (WM) problems at the INEL to potential technologies that can remediate these problems. The TLD identifies the research, development, demonstration, testing, and evaluation needed to develop these technologies to a state that allows technology transfer and application to an environmental restoration need. It is essential that follow-on engineering and system studies be conducted to build on the output of this project. These studies will begin by selecting the most promising technologies identified in this TLD and finding an optimum mix of technologies that will provide a socially acceptable balance between cost and risk to meet the site windows of opportunity. The TLD consists of three separate volumes: Volume I includes the purpose and scope of the TLD, a brief history of the INEL Waste Area Groups, and environmental problems they represent. A description of the TLD, definitions of terms, a description of the technology evaluation process, and a summary of each subelement, is presented. Volume II describes the overall layout and development of the TLD in logic diagram format. This section addresses the environmental restoration of contaminated INEL sites. Volume III (this volume) provides the Technology Evaluation Data Sheets (TEDS) for Environmental Restoration and Waste Management (EM) activities that are reference by a TEDS code number in Volume II. Each of these sheets represents a single logic trace across the TLD. These sheets contain more detail than provided for technologies in Volume II. Data sheets are arranged alphanumerically by the TEDS code number in the upper right corner of each sheet.

Petrophysical characteristics of basalt in the vadose zone, Idaho National Engineering Laboratory, Eastern Snake River Plain, Idaho

International Nuclear Information System (INIS)

Knutson, C.F.; Harrison, W.E.; Smith, R.P.

1989-01-01

We have used a core characterization system to measure bulk densities, porosities, and permeabilities of basalt lavas from the vadose zone at the Idaho National Engineering Laboratory (INEL). At the INEL, basalt lava flows with intercalated alluvial, aeolian, and lacustrine sediments extend to depths of one kilometer or more. Individual lava flows are generally less than 15 meters thick and commonly have vesicular tops and bottoms with massive basalt in their interiors. Petrophysical characterization is essential to an understanding of fluid movement in the vadose zone and in the saturated zone. Many hundreds of closely spaced permeability/porosity/bulk density measurements have defined the variability of these parameters within and between individual basalt flows. Based on geological logging and porosity/permeability measurements made on many hundred feet of core, we feel that a rather sophisticated and rigorous logging program is necessary to characterize these complex and highly variable basaltic flow units. This paper endeavors to provide a petrophysical/geological conceptual model of the Snake River Plain basalts from the vadose zone under the Radioactive Waste Management Complex area at the INEL. We hope that this model will aid in subsequent geotechnical logging in this portion of the Eastern Snake River Plain. 8 refs., 14 figs., 2 tabs

Mineralogy of selected sedimentary interbeds at or near the Idaho National Engineering Laboratory, Idaho

International Nuclear Information System (INIS)

Reed, M.F.; Bartholomay, R.C.

1994-08-01

The US Geological Survey's (USGS) Project Office at the Idaho National Engineering Laboratory (INEL) analyzed 66 samples from sedimentary interbed cores during a 38-month period beginning in October 1990 to determine bulk and clay mineralogy. These cores had been collected from 19 sites in the Big Lost River Basin, 2 sites in the Birch Creek Basin, and 1 site in the Mud Lake Basin, and were archived at the USGS lithologic core library at the INEL. Mineralogy data indicate that core samples from the Big Lost River Basin have larger mean and median percentages of quartz, total feldspar, and total clay minerals, but smaller mean and median percentages of calcite than the core samples from the Birch Creek Basin. Core samples from the Mud Lake Basin have abundant quartz, total feldspar, calcite, and total clay minerals. Identification of the mineralogy of the Snake River Plain is needed to aid in the study of the hydrology and geochemistry of subsurface waste disposal

Facility status and progress of the INEL's WERF MLLW and LLW incinerator

International Nuclear Information System (INIS)

Conley, D.; Corrigan, S.

1996-01-01

The Idaho National Engineering Laboratory's (INEL) Waste Experimental Reduction Facility (WERF) incinerator began processing beta/gamma- emitting low-level waste (LLW) in September 1984. A Resource Conservation and Recovery Act (RCRA) trial burn for the WERF incinerator was conducted in 1986, and in 1989 WERF began processing (hazardous and low-level radioactive) waste known as mixed low-level waste (MLLW). On February 14, 1991 WERF operations were suspended to improve operating procedures and configuration management. On July 12, 1995, WERF initiated incineration of LLW; and on September 20, 1995 WERF resumed its primary mission of incinerating MLLW. MLLW incineration is proceeding under RCRA interim status. State of Idaho issuance of the Part B permit is one of the State's highest permitting priorities. The State of Idaho's Division of Environmental Quality is reviewing the permit application along with a revised trial burn plan that was also submitted with the application. The trial burn has been proposed to be performed in 1996 to demonstrate compliance with the current incinerator guidance. This paper describes the experiences and problems associated with WERF's operations, incineration of MLLW, and the RCRA Part B Permit Application. Some of the challenges that have been overcome include waste characterization, waste repackaging, repackaged waste storage, and implementation of RCRA interim status requirements. A number of challenges remain. They include revision of the RCRA Part B Permit Application and the Trial Burn Plan in response to comments from the state permit application reviewers as well as facility and equipment upgrades required to meet RCRA Permitted Status

NRC nuclear-plant-analyzer concept and status at INEL

International Nuclear Information System (INIS)

Aguilar, F.; Wagner, R.J.

1982-01-01

The Office of Research of the US NRC has proposed development of a software-hardware system called the Nuclear Plant Analyzer (NPA). This paper describes how we of the INEL envision the nuclear-plant analyzer. The paper also describes a pilot RELAP5 plant-analyzer project completed during the past year and current work. A great deal of analysis is underway to determine nuclear-steam-system response. System transient analysis being so complex, there is the need to present analytical results in a way that interconnections among phenomena and all the nuances of the transient are apparent. There is the need for the analyst to dynamically control system calculations to simulate plant operation in order to perform what if studies as well as the need to perform system analysis within hours of a plant emergency to diagnose the state of the stricken plant and formulate recovery actions. The NRC-proposed nuclear-plant analyzer can meet these needs

Development of criteria for release of Idaho National Engineering Laboratory sites following decontamination and decommissioning

International Nuclear Information System (INIS)

Kirol, L.

1986-08-01

Criteria have been developed for release of Idaho National Engineering Laboratory (INEL) facilities and land areas following decontamination and decommissioning (D and D). Although these facilities and land areas are not currently being returned to the public domain, and no plans exist for doing so, criteria suitable for unrestricted release to the public were desired. Midway through this study, the implementation of Department of Energy (DOE) Order 5820.2, Radioactive Waste Management, required development of site specific release criteria for use on D and D projects. These criteria will help prevent remedial actions from being required if INEL reuse considerations change in the future. Development of criteria for release of INEL facilities following D and D comprised four study areas: pathways analysis, dose and concentration guidelines, sampling and instrumentation, and implementation procedures. Because of the complex and sensitive nature of the first three categories, a thorough review by experts in those respective fields was desired. Input and support in preparing or reviewing each part of the criteria development task was solicited from several DOE field offices. Experts were identified and contracted to assist in preparing portions of the release criteria, or to serve on a peer-review committee. Thus, the entire release criteria development task was thoroughly reviewed by recognized experts from contractors at several DOE field offices, to validate technical content of the document. Each of the above four study areas was developed originally as an individual task, and a report was generated from each. These reports are combined here to form this document. This release criteria document includes INEL-specific pathways analysis, instrumentation requirements, sampling procedures, the basis for selection of dose and concentration guidelines, and cost-risk-benefit procedures

Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs draft environmental impact statement. Volume 1, Appendix B: Idaho National Engineering Laboratory Spent Nuclear Fuel Management Program

Energy Technology Data Exchange (ETDEWEB)

1994-06-01

The US Department of Energy (DOE) has prepared this report to assist its management in making two decisions. The first decision, which is programmatic, is to determine the management program for DOE spent nuclear fuel. The second decision is on the future direction of environmental restoration, waste management, and spent nuclear fuel management activities at the Idaho National Engineering Laboratory. Volume 1 of the EIS, which supports the programmatic decision, considers the effects of spent nuclear fuel management on the quality of the human and natural environment for planning years 1995 through 2035. DOE has derived the information and analysis results in Volume 1 from several site-specific appendixes. Volume 2 of the EIS, which supports the INEL-specific decision, describes environmental impacts for various environmental restoration, waste management, and spent nuclear fuel management alternatives for planning years 1995 through 2005. This Appendix B to Volume 1 considers the impacts on the INEL environment of the implementation of various DOE-wide spent nuclear fuel management alternatives. The Naval Nuclear Propulsion Program, which is a joint Navy/DOE program, is responsible for spent naval nuclear fuel examination at the INEL. For this appendix, naval fuel that has been examined at the Naval Reactors Facility and turned over to DOE for storage is termed naval-type fuel. This appendix evaluates the management of DOE spent nuclear fuel including naval-type fuel.

A summary of the environmental restoration program retrieval demonstration project at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

McQuary, J.

1991-02-01

This report provides a summary of the Environmental Restoration Program's Retrieval Demonstration Project at the Idaho National Engineering Laboratory. This project developed concepts for demonstrating facilities and equipment for the retrieval of buried transuranic mixed waste at the INEL. Included is a brief assessment of the viability, cost effectiveness, and safety of retrieval based on the developed concept. Changes made in Revision 1 reflect editorial changes only. 31 refs., 1 fig

1984 Environmental monitoring program report for Idaho National Engineering Laboratory Site

International Nuclear Information System (INIS)

Hoff, D.L.; Chew, E.W.; Dickson, R.L.

1985-05-01

The results of the various monitoring programs for 1984 indicated that radioactivity from INEL Site operations could not be distinguished from worldwide fallout and natural radioactivity in the region surrounding the Site. Although some radioactive materials were discharged during Site operations, concentrations and doses to the surrounding population were of no health consequence and were far less than State of Idaho and federal health protection guidelines. This report describes the air, water, and foodstuff samples routinely collected at the INEL boundary locations and at locations distant from the INEL Site; and it compares and evaluates the sample results, discussing implications, if any. The report also summarizes significant environmental activities at the INEL Site during 1984, nonradioactive and radioactive effluent monitoring at the Site, and the US Geological Survey (USGS) groundwater monitoring program. 28 refs., 13 figs., 22 tabs

Environmental protection at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

1987-07-01

The primary objective of radioactive waste management at the INEL is to minimize the generation of waste products and to ensure that these waste products do not constitute a hazard to life forms. All radioactive waste streams are monitored by highly sensitive instruments and are carefully controlled so that corrective action can be taken, if necessary. In addition, the environment itself is monitored to ensure that controls at the various facilities have been adequate to prevent significant releases of radioactivity. Samples of air, soil, water, and foodstuffs from the vicinity of the INEL are routinely monitored. These surveillance activities verify that the doses to people at or near the INEL from radioisotoptes are extremely small, and far below acceptable limits specified by state and federal regulations

The European Register of Specialists in Clinical Chemistry and Laboratory Medicine: guide to the Register, version 3-2010.

LENUS (Irish Health Repository)

McMurray, Janet

2010-07-01

In 1997, the European Communities Confederation of Clinical Chemistry and Laboratory Medicine (EC4) set up a Register for European Specialists in Clinical Chemistry and Laboratory Medicine. The operation of the Register is undertaken by a Register Commission (EC4RC). During the last 12 years, more than 2200 specialists in Clinical Chemistry and Laboratory Medicine have joined the Register. In 2007, EC4 merged with the Forum of European Societies of Clinical Chemistry and Laboratory Medicine (FESCC) to form the European Federation of Clinical Chemistry and Laboratory Medicine (EFCC). Two previous Guides to the Register have been published, one in 1997 and another in 2003. The third version of the Guide is presented in this article and is based on the experience gained and development of the profession since the last revision. Registration is valid for 5 years and the procedure and criteria for re-registration are presented as an Appendix at the end of the article.

Requantification of the Zion risk profile

International Nuclear Information System (INIS)

Park, C.K.; Cazzoli, E.; Lee, M.; Grimshaw, C.; Pratt, W.T.; Unwin, S.D.

1988-01-01

In February 1987, a preliminary version of the Zion Study performed at the Brookhaven National Laboratory was published for comment. This analysis provided one of the technical bases for the draft NUREG-1150 document. Since the publication, various comments both upon general technical terms and specific calculational issues were received from industry, the public and various peer review panels. In the light of methodological and modelling deficiencies identified in the draft analysis by both internal and external reviews, extensive modifications to the preliminary Zion study were undertaken in support of the final version of NUREG-1150. The integrated analysis of Zion is a collaborative effort involving Brookhaven National Laboratory (BNL) and Idaho National Engineering Laboratories (INEL). The current paper discusses preliminary results of the requantification efforts in various stages of the Zion back-end analysis performed at BNL. 7 refs., 7 figs., 6 tabs

Final report for the Idaho National Engineering Laboratory Central Facilities Area Landfill 2

International Nuclear Information System (INIS)

Doornbos, M.H.; Morgan, M.E.; Hubbell, J.M.

1991-04-01

This report summarize activities completed during FY-88 through FY-91 for the US Department of Energy's (DOE's) Hazardous Waste Remedial Actions Program (HAZWRAP) at the Idaho National Engineering Laboratory (INEL) Central Facilities Area (CFA) Landfill 2. The objectives of this program are to demonstrate new technologies or innovative uses of existing technologies for the identification and remediation of hazardous wastes within a municipal-type landfill. The site was chosen as a candidate site because it represents a problem typical of both DOE and public landfills. The HAZWRAP Technology Demonstration Project began at the INEL CFA Landfill 2 in 1987. During characterization and identification activities, several organic ''hotspots'' or anomalies were identified. Proposals were then solicited from the private sector for innovative technologies to remediate the isolated areas. Remediation was planned to be implemented using horizontal wells installed underneath a portion of the landfill. These innovative technologies and the well installation were planned to support the current goals of the DOE and the Environmental Protection Agency to treat hazardous waste in place. 2 refs., 2 figs., 2 tabs

Support for the in situ vitrification treatability study at the Idaho National Engineering Laboratory: FY 1988 summary

International Nuclear Information System (INIS)

Oma, K.H.; Reimus, M.A.H.; Timmerman, C.L.

1989-02-01

The objective of this project is to determine if in situ vitrification (ISV) is a viable, long-term confinement technology for previously buried solid transuranic and mixed waste at the Radioactive Waste Management Complex (RWMC). The RWMC is located at the Idaho National Engineering Laboratory (INEL). In situ vitrification is a thermal treatment process that converts contaminated soils and wastes into a durable glass and crystalline form. During processing, heavy metals or other inorganic constituents are retained and immobilized in the glass structure, and organic constituents are typically destroyed or removed for capture by an off-gas treatment system. The primary FY 1988 activities included engineering-scale feasibility tests on INEL soils containing a high metals loading. Results of engineering-scale testing indicate that wastes with a high metals content can be successfully processed by ISV. The process successfully vitrified soils containing localized metal concentrations as high as 42 wt % without requiring special methods to prevent electrical shorting within the melt zone. Vitrification of this localized concentration resulted in a 15.9 wt % metals content in the entire ISV test block. This ISV metals limit is related to the quantity of metal that accumulates at the bottom of the molten glass zone. Intermediate pilot-scale testing is recommended to determine metals content scale-up parameters in order to project metals content limits for large-scale ISV operation at INEL

In Situ Vitrification Engineering-Scale Test ES-INEL-4, ES-INEL-5, ES-INEL-6, and ES-INEL-7 Test Plan

International Nuclear Information System (INIS)

Weidner, J.R.; Stoots, P.R.

1990-10-01

The In Situ Vitrification Engineering-Scale Tests ES-4, ES-5, ES-6, and ES-7 Product Characterization Test Plan describes the methods and procedures to be used or the physical and chemical characterization of the solid product(s) resulting from the Idaho National Engineering Laboratory engineering scale in situ vitrification tests ES-4, ES-5, ES-6, and ES-7. The goals of this Test Plan are to insure that the product characterization results are sufficient to meet the data needs of the In Situ Vitrification Program and are technically and legally defensible. Important issues addressed by the test plan include sampling and analysis strategy, sampling procedures, laboratory analysis, sample control and document management, equipment, data reporting and validation, quality assurance, specific routine procedures to assess data representativeness, safety and training program, and data management. 9 refs., 1 fig., 3 tabs

Use of Monte Carlo methods in environmental risk assessments at the INEL: Applications and issues

Energy Technology Data Exchange (ETDEWEB)

Harris, G.; Van Horn, R.

1996-06-01

The EPA is increasingly considering the use of probabilistic risk assessment techniques as an alternative or refinement of the current point estimate of risk. This report provides an overview of the probabilistic technique called Monte Carlo Analysis. Advantages and disadvantages of implementing a Monte Carlo analysis over a point estimate analysis for environmental risk assessment are discussed. The general methodology is provided along with an example of its implementation. A phased approach to risk analysis that allows iterative refinement of the risk estimates is recommended for use at the INEL.

Environmental and other evaluations of alternatives for long-term management of stored INEL transuranic waste

International Nuclear Information System (INIS)

1979-12-01

This study identifies, develops, and evaluates, in a preliminary manner, alternatives for long-term management of TRU waste stored at the Radioactive Waste Management Complex (RWMC) at the INEL. The evaluations concern waste currently at the RWMC and waste expected to be received by the beginning of the year 1985. The effects of waste that might be received after that data are addressed in an appendix. The technology required for managing the waste, the environmental effects, the risks to the public, the radiological and nonradiological hazards to workers, and the estimated costs are discussed

Use of Monte Carlo methods in environmental risk assessments at the INEL: Applications and issues

International Nuclear Information System (INIS)

Harris, G.; Van Horn, R.

1996-06-01

The EPA is increasingly considering the use of probabilistic risk assessment techniques as an alternative or refinement of the current point estimate of risk. This report provides an overview of the probabilistic technique called Monte Carlo Analysis. Advantages and disadvantages of implementing a Monte Carlo analysis over a point estimate analysis for environmental risk assessment are discussed. The general methodology is provided along with an example of its implementation. A phased approach to risk analysis that allows iterative refinement of the risk estimates is recommended for use at the INEL

Environmental and other evaluations of alternatives for long-term management of stored INEL transuranic waste

Energy Technology Data Exchange (ETDEWEB)

1979-02-01

This study identifies, develops, and evaluates, in a preliminary manner, alternatives for long-term management of TRU waste stored at the Radioactive Waste Management Complex (RWMC) at the INEL. The evaluations concern waste currently at the RWMC and waste expected to be received by the beginning of the year 1985. The effects of waste that might be received after that date are addressed in an appendix. The technology required for managing the waste, the environmental effects, the risks to the public, the radiological and nonradiological hazards to workers, and the estimated costs are discussed.

Environmental and other evaluations of alternatives for long-term management of stored INEL transuranic waste

International Nuclear Information System (INIS)

1979-02-01

This study identifies, develops, and evaluates, in a preliminary manner, alternatives for long-term management of TRU waste stored at the Radioactive Waste Management Complex (RWMC) at the INEL. The evaluations concern waste currently at the RWMC and waste expected to be received by the beginning of the year 1985. The effects of waste that might be received after that date are addressed in an appendix. The technology required for managing the waste, the environmental effects, the risks to the public, the radiological and nonradiological hazards to workers, and the estimated costs are discussed

Spent fuel storage cask testing and operational experience at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Eslinger, L.E.; Schmitt, R.C.

1989-01-01

Spent-fuel storage cask research, development, and demonstration activities are being performed for the U.S. Department of Energy's (DOE's) Office of Civilian Radioactive Waste Management (OCRWM) as a part of the storage cask testing program. The cask testing program at federal sites and other locations supports the Nuclear Waste Policy Act (NWPA) and DOE objectives for cooperative demonstrations with the cask vendors and utilities for development of at-reactor dry cask storage capabilities for spent nuclear fuel assemblies. One research and development program for the storage cask performance testing of metal storage cask was initiated through a cooperative agreement between Virginia Power and DOE in 1984. The performance testing was conducted for the DOE and the Electric Power Research Institute by the Pacific Northwest laboratory, operated for DOE by Battelle Memorial Institute, and the Idaho National Engineering Laboratory (INEL), operated for DOE by EG ampersand G Idaho, Inc. In 1988 a cooperative agreement was entered into by DOE with Pacific Sierra Nuclear Associates (PSN) for performance testing of the PSN concrete Ventilated Storage Cask. Another closely related activity involving INEL is a transportable storage cask project identified as the Nuclear Fuel Services Spent-Fuel Shipping/Storage Cask Demonstration Project. The purpose of this project is to demonstrate the feasibility of packing, transporting, and storing commercial spent fuel in dual-purpose transport/storage casks

Ecology studies at the Idaho National Engineering Laboratory Radioactive Waste Management Complex

International Nuclear Information System (INIS)

Arthur, W.J.; Markham, O.D.

1978-01-01

In September 1977 a radioecological research program was initiated at the Idaho National Engineering Laboratory (INEL) Radioactive Waste Management Complex in the southcentral Idaho. The primary goals of the research are to: (1) determine floral and faunal composition in the area; (2) sample various ecosystem components for radionuclides; (3) determine impacts of small mammal burrowing and vegetation growth on movement of radioactive materials; (4) compare ambient radiation exposures to radiation doses received by animals inhabiting the area; and (5) understand the interrelationships between the organisms and their role in radionuclide transport

Initial performance assessment of the disposal of spent nuclear fuel and high-level waste stored at Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Rechard, R.P.

1993-12-01

This performance assessment characterized plausible treatment options conceived by the Idaho National Engineering Laboratory (INEL) for its spent fuel and high-level radioactive waste and then modeled the performance of the resulting waste forms in two hypothetical, deep, geologic repositories: one in bedded salt and the other in granite. The results of the performance assessment are intended to help guide INEL in its study of how to prepare wastes and spent fuel for eventual permanent disposal. This assessment was part of the Waste Management Technology Development Program designed to help the US Department of Energy develop and demonstrate the capability to dispose of its nuclear waste. Although numerous caveats must be placed on the results, the general findings were as follows: Though the waste form behavior depended upon the repository type, all current and proposed waste forms provided acceptable behavior in the salt and granite repositories

Radiological, physical, and chemical characterization of low-level alpha contaminated wastes stored at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Apel, M.L.; Becker, G.K.; Ragan, Z.K.; Frasure, J.; Raivo, B.D.; Gale, L.G.; Pace, D.P.

1994-03-01

This document provides radiological, physical, and chemical characterization data for low-level alpha-contaminated radioactive and low-level alpha-contaminated radioactive and hazardous (i.e., mixed) wastes stored at the Idaho National Engineering Laboratory and considered for treatment under the Private Sector Participation Initiative Program. Waste characterization data are provided in the form of INEL Waste Profile Sheets. These documents provide, for each content code, information on waste identification, waste description, waste storage configuration, physical/chemical waste composition, radionuclide and associated alpha activity waste characterization data, and hazardous constituents present in the waste. Information is provided for 97 waste streams which represent an estimated total volume of 25,450 m 3 corresponding to a total mass of approximately 12,000,000 kg. In addition, considerable information concerning alpha, beta, gamma, and neutron source term data specific to Rocky Flats-generated waste forms stored at the INEL are provided to assist in facility design specification

Radiological, physical, and chemical characterization of low-level alpha contaminated wastes stored at the Idaho National Engineering Laboratory

Energy Technology Data Exchange (ETDEWEB)

Apel, M.L.; Becker, G.K.; Ragan, Z.K.; Frasure, J.; Raivo, B.D.; Gale, L.G.; Pace, D.P.

1994-03-01

This document provides radiological, physical, and chemical characterization data for low-level alpha-contaminated radioactive and low-level alpha-contaminated radioactive and hazardous (i.e., mixed) wastes stored at the Idaho National Engineering Laboratory and considered for treatment under the Private Sector Participation Initiative Program. Waste characterization data are provided in the form of INEL Waste Profile Sheets. These documents provide, for each content code, information on waste identification, waste description, waste storage configuration, physical/chemical waste composition, radionuclide and associated alpha activity waste characterization data, and hazardous constituents present in the waste. Information is provided for 97 waste streams which represent an estimated total volume of 25,450 m 3 corresponding to a total mass of approximately 12,000,000 kg. In addition, considerable information concerning alpha, beta, gamma, and neutron source term data specific to Rocky Flats-generated waste forms stored at the INEL are provided to assist in facility design specification.

University Research Consortium annual review meeting program

International Nuclear Information System (INIS)

1996-07-01

This brochure presents the program for the first annual review meeting of the University Research Consortium (URC) of the Idaho National Engineering Laboratory (INEL). INEL is a multiprogram laboratory with a distinctive role in applied engineering. It also conducts basic science research and development, and complex facility operations. The URC program consists of a portfolio of research projects funded by INEL and conducted at universities in the United States. In this program, summaries and participant lists for each project are presented as received from the principal investigators

University Research Consortium annual review meeting program

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-07-01

This brochure presents the program for the first annual review meeting of the University Research Consortium (URC) of the Idaho National Engineering Laboratory (INEL). INEL is a multiprogram laboratory with a distinctive role in applied engineering. It also conducts basic science research and development, and complex facility operations. The URC program consists of a portfolio of research projects funded by INEL and conducted at universities in the United States. In this program, summaries and participant lists for each project are presented as received from the principal investigators.

Mixed waste treatment at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Larsen, M.M.; Hunt, L.F.; Sanow, D.J.

1988-01-01

The Idaho Operations Office of the Department of Energy (DOE) made the decision in 1984 to prohibit the disposal of mixed waste (MW) (combustible waste-toxic metal waste) in the Idaho National Engineering Laboratory (INEL) low-level radioactive waste (LLW) disposal facility. As a result of this decision and due to there being no EPA-permitted MW treatment/storage/disposal (T/S/D) facilities, the development of waste treatment methods for MW was initiated and a storage facility was established to store these wastes while awaiting development of treatment systems. This report discusses the treatment systems developed and their status. 3 refs., 2 figs., 1 tab

Procedures for use of, and drill cores and cuttings available for study at, the Lithologic Core Storage Library, Idaho National Engineering Laboratory, Idaho

International Nuclear Information System (INIS)

Davis, L.C.; Hannula, S.R.; Bowers, B.

1997-03-01

In 1990, the US Geological Survey, in cooperation with the US Department of Energy, Idaho Operations Office, established the Lithologic Core Storage Library at the Idaho National Engineering Laboratory (INEL). The facility was established to consolidate, catalog, and permanently store nonradioactive drill cores and cuttings from investigations of the subsurface conducted at the INEL, and to provide a location for researchers to examine, sample, and test these materials. The facility is open by appointment to researchers for examination, sampling, and testing of cores and cuttings. This report describes the facility and cores and cuttings stored at the facility. Descriptions of cores and cuttings include the well names, well locations, and depth intervals available. Most cores and cuttings stored at the facility were drilled at or near the INEL, on the eastern Snake River Plain; however, two cores drilled on the western Snake River Plain are stored for comparative studies. Basalt, rhyolite, sedimentary interbeds, and surficial sediments compose the majority of cores and cuttings, most of which are continuous from land surface to their total depth. The deepest core stored at the facility was drilled to 5,000 feet below land surface. This report describes procedures and researchers' responsibilities for access to the facility, and examination, sampling, and return of materials

Hazardous and mixed waste solidification development conducted at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Boehmer, A.M.; Larsen, M.M.

1986-04-01

EG and G Idaho, Inc., has initiated a program to develop safe, efficient, cost-effective solidification treatment methods for the disposal of some of the hazardous and mixed wastes generated at the Idaho National Engineering Laboratory (INEL). Testing has shown that Extraction Procedure (EP) toxic wastes can be successfully solidified using cement, cement-silicate, or ENVIROSTONE binders to produce nontoxic stable waste forms for safe, long-term disposal as general or low-level waste, depending upon the radioactivity. The results of the solidification development program are presented in this report

Idaho National Engineering Laboratory Site environmental report for Calendar Year 1994

Energy Technology Data Exchange (ETDEWEB)

Mitchell, R.G.; Peterson, D. [Environmental Science and Research Foundation, Idaho Falls, ID (United States); Hoff, D.L. [USDOE Idaho Operations Office, Idaho Falls, ID (United States)

1995-07-01

This report presents a compilation of data collected in 1994 for routine environmental surveillance programs conducted on and around INEL. EG&G conducted the onsite surveillance program January-- September; Lockheed Idaho conducted the program October--December. The offsite surveillance program was conducted by the Environmental Science and Research Foundation. Ground water monitoring (both on and off site) was performed by USGS. This report presents summaries of facility effluent monitoring data collected by INEL contractors. It includes collection of foodstuffs at the INEL boundary and distant offsite locations, and the collection of air and water samples at onsite locations and offsite boundary and distant locations. The report also compares and evaluates the sample results to federal regulations and standards.

Idaho National Engineering Laboratory Site environmental report for Calendar Year 1994

International Nuclear Information System (INIS)

Mitchell, R.G.; Peterson, D.; Hoff, D.L.

1995-07-01

This report presents a compilation of data collected in 1994 for routine environmental surveillance programs conducted on and around INEL. EG ampersand G conducted the onsite surveillance program January-- September; Lockheed Idaho conducted the program October--December. The offsite surveillance program was conducted by the Environmental Science and Research Foundation. Ground water monitoring (both on and off site) was performed by USGS. This report presents summaries of facility effluent monitoring data collected by INEL contractors. It includes collection of foodstuffs at the INEL boundary and distant offsite locations, and the collection of air and water samples at onsite locations and offsite boundary and distant locations. The report also compares and evaluates the sample results to federal regulations and standards

Initial performance assessment of the disposal of spent nuclear fuel and high-level waste stored at Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Rechard, R.P.

1993-12-01

This performance assessment characterized plausible treatment options conceived by the Idaho National Engineering Laboratory (INEL) for its spent fuel and high-level radioactive waste and then modeled the performance of the resulting waste forms in two hypothetical, deep, geologic repositories: one in bedded salt and the other in granite. The results of the performance assessment are intended to help guide INEL in its study of how to prepare wastes and spent fuel for eventual permanent disposal. This assessment was part of the Waste Management Technology Development Program designed to help the US Department of Energy develop and demonstrate the capability to dispose of its nuclear waste, as mandated by the Nuclear Waste Policy Act of 1982. The waste forms comprised about 700 metric tons of initial heavy metal (or equivalent units) stored at the INEL: graphite spent fuel, experimental low enriched and highly enriched spent fuel, and high-level waste generated during reprocessing of some spent fuel. Five different waste treatment options were studied; in the analysis, the options and resulting waste forms were analyzed separately and in combination as five waste disposal groups. When the waste forms were studied in combination, the repository was assumed to also contain vitrified high-level waste from three DOE sites for a common basis of comparison and to simulate the impact of the INEL waste forms on a moderate-sized repository, The performance of the waste form was assessed within the context of a whole disposal system, using the U.S. Environmental Protection Agency's Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes, 40 CFR 191, promulgated in 1985. Though the waste form behavior depended upon the repository type, all current and proposed waste forms provided acceptable behavior in the salt and granite repositories

Inclusion in the Workplace - Text Version | NREL

Science.gov (United States)

Careers » Inclusion in the Workplace - Text Version Inclusion in the Workplace - Text Version This is the text version for the Inclusion: Leading by Example video. I'm Martin Keller. I'm the NREL of the laboratory. Another very important element in inclusion is diversity. Because if we have a

Special isotope separation project, Idaho National Engineering Laboratory, Idaho Falls, Idaho

International Nuclear Information System (INIS)

1988-02-01

Construction and operation of a Special Isotope Separation (SIS) project using the Atomic Vapor Laser Isotope Separation (AVLIS) process technology at the Idaho National Engineering Laboratory (INEL) near Idaho Falls, Idaho are proposed. The SIS project would process fuel-grade plutonium administered by the Department of Energy (DOE) into weapon-grade plutonium using AVLIS and supporting chemical processes. The SIS project would require construction and operation of a Laser Support Facility to house the laser system and a Plutonium Processing Facility. The SIS project would be integrated with existing support and waste management facilities at the selected site. The SIS project would provide DOE with the capability of segregating the isotopes of DOE-owned plutonium into specific isotopic concentrations. This capability would provide redundancy in production capacity, technological diversity, and flexibility in DOE's production of nuclear materials for national defense. Use of the INEL site would impact 151,350 square meters (37.4 acres) of land, of which more than 70% has been previously disturbed. During construction, plant and animal habitat associated with a sagebrush vegetation community would be lost. During operation of the SIS facilities, unavoidable radiation exposures would include occupational exposures and exposures to the public from normal atmospheric releases of radioactive materials that would be minimal compared to natural background radiation

Annual technology assessment and progress report for the buried transuranic waste program at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Berreth, P.D.

1984-11-01

The US Department of Energy (DOE) is responsible for developing and implementing methods for the safe and environmentally acceptable disposal of radioactive waste. In 1983, DOE formulated a comprehensive plan to manage transuranic (TRU) defense waste. The DOE plan for buried TRU waste is to monitor it, take remedial actions as necessary, and reevaluate its safety periodically. The DOE strategy reflects concern that, based on present technology, retrieval and processing of buried waste may be risky and costly. To implement the DOE plan, EG and G Idaho, Inc., prime contractor at the Idaho National Engineering Laboratory (INEL), has developed a strategy for long-term management of the 2 million cubic feet of INEL buried TRU waste. That strategy involves four main activities: (a) environmental monitoring, (b) remedial action if necessary, (c) assimilation of data from both special studies and ongoing waste management activities, and (d) selection of a long-term management alternative in 1995. This report, submitted as the first in a series of annual reports, summarizes the buried TRU waste activities performed in fiscal year (FY) 1984 at the INEL in response to the DOE plan. Specifically, technologies applicable to buried waste confinement, retrieval, certification, and processing have been assessed, a long-range plan to conduct buried wasted studies over the next ten years has been prepared, and retrieval and soil management alternatives have been evaluated. 17 references, 7 figures, 1 table

Development of a regional groundwater flow model for the area of the Idaho National Engineering Laboratory, Eastern Snake River Plain Aquifer

International Nuclear Information System (INIS)

McCarthy, J.M.; Arnett, R.C.; Neupauer, R.M.

1995-03-01

This report documents a study conducted to develop a regional groundwater flow model for the Eastern Snake River Plain Aquifer in the area of the Idaho National Engineering Laboratory. The model was developed to support Waste Area Group 10, Operable Unit 10-04 groundwater flow and transport studies. The products of this study are this report and a set of computational tools designed to numerically model the regional groundwater flow in the Eastern Snake River Plain aquifer. The objective of developing the current model was to create a tool for defining the regional groundwater flow at the INEL. The model was developed to (a) support future transport modeling for WAG 10-04 by providing the regional groundwater flow information needed for the WAG 10-04 risk assessment, (b) define the regional groundwater flow setting for modeling groundwater contaminant transport at the scale of the individual WAGs, (c) provide a tool for improving the understanding of the groundwater flow system below the INEL, and (d) consolidate the existing regional groundwater modeling information into one usable model. The current model is appropriate for defining the regional flow setting for flow submodels as well as hypothesis testing to better understand the regional groundwater flow in the area of the INEL. The scale of the submodels must be chosen based on accuracy required for the study

Quality-assurance plan and field methods for quality-of-water activities, U.S. Geological Survey, Idaho National Engineering Laboratory, Idaho

International Nuclear Information System (INIS)

Mann, L.J.

1996-10-01

Water-quality activities at the Idaho National Engineering Laboratory (INEL) Project Office are part of the US Geological Survey's (USGS) Water Resources Division (WRD) mission of appraising the quantity and quality of the Nation's water resources. The purpose of the Quality Assurance Plan (QAP) for water-quality activities performed by the INEL Project Office is to maintain and improve the quality of technical products, and to provide a formal standardization, documentation, and review of the activities that lead to these products. The principles of this plan are as follows: (1) water-quality programs will be planned in a competent manner and activities will be monitored for compliance with stated objectives and approaches; (2) field, laboratory, and office activities will be performed in a conscientious and professional manner in accordance with specified WRD practices and procedures by qualified and experienced employees who are well trained and supervised, if or when, WRD practices and procedures are inadequate, data will be collected in a manner that its quality will be documented; (3) all water-quality activities will be reviewed for completeness, reliability, credibility, and conformance to specified standards and guidelines; (4) a record of actions will be kept to document the activity and the assigned responsibility; (5) remedial action will be taken to correct activities that are deficient

Hydrologic conditions at the Idaho National Engineering Laboratory, Idaho - emphasis: 1974-1978

International Nuclear Information System (INIS)

Barraclough, J.T.; Lewis, B.D.; Jensen, R.G.

1982-09-01

The Idaho National Engineering Laboratory (INEL) site covers about 890 square miles of the eastern Snake River Plain and overlies the Snake River Plain aquifer. Low concentrations of aqueous chemical and radioactive wastes have been discharged to shallow ponds and to shallow or deep wells on the site since 1952. A large body of perched ground water has formed in the basalt underlying the waste disposal ponds in the Test Reactor Area. This perched zone contains tritium, chromium-51, cobalt-60, strontium-90, and several nonradioactive ions. Tritium is the only mappable waste constituent in that portion of the Snake River Plain aquifer directly underlying this perched zone. Low concentrations of chemical and low-level radioactive wastes enter directly into the Snake River Plain aquifer through the Idaho Chemical Processing Plant (ICPP) disposal well. Tritium has been discharged to the well since 1953 and has formed the largest waste plume, about 28 square miles in area, in the regional aquifer, and minute concentrations have migrated downgradient a horizontal distance of 7.5 miles. Other waste plumes south of the ICPP contain sodium, chloride, nitrate, and the resultant specific conductance. These plumes have similar configurations and flow southward; the contaminants are in general laterally dispersed in that portion of the aquifer underlying the INEL. Other waste plumes, containing strontium-90 and iodine-129, cover small areas near their points of discharge because strontium-90 is sorbed from solution as it moves through the aquifer and iodine-129 is discharged in very low quantities. Cesium-137 is also discharged through the well but it is strongly sorbed from solution and has never been detected in a sample of ground water at the INEL

Plan for shipment, storage, and examination of TMI-2 fuel

International Nuclear Information System (INIS)

Quinn, G.J.; Engen, I.A.; Tyacke, M.J.; Reno, H.W.

1984-05-01

This Plan addresses the preparation and shipment of core debris from Three Mile Island Unit 2 (TMI-2) to the Idaho National Engineering Laboratory (INEL) for receipt, storage, and examination. The Manager of the Nuclear Materials Evaluation Programs Division of EG and G Idaho, Inc. will manage two separate but integrated programs, one located at TMI (Part 1) and the other at INEL (Part 2). The Technical Integration Office (at TMI) is responsible for developing and implementing Part 1, TMI-2 Core Shipment Program. That portion of the Plan establishes coordination between TMI and INEL (and others) for shipment of core debris, and it provides the coordination by which handling systems at both locations are designed, constructed, or modified to establish and maintain system compatibility. The Technical Support Branch (at INEL) is responsible for developing and implementing Part 2, Core Activities Program. That portion of the Plan details operational and examination activities at INEL, as well as defines core-related activities planned at other DOE laboratories

Buried Waste Integrated Demonstration FY-93 Deployment Plan

International Nuclear Information System (INIS)

Bonnenberg, R.W.; Heard, R.E.; Milam, L.M.; Watson, L.R.

1993-02-01

The Buried Waste Integrated Demonstration (BWID) is a program funded by the US Department of Energy Office of Technology Development. BWID supports the applied research, development, demonstration, and evaluation of a suite of advanced technologies that together form a comprehensive remediation system for the effective and efficient remediation of buried waste. The fiscal year 1993 effort will deploy seven major field demonstrations at the Idaho National Engineering Laboratory's (INEL's) Radioactive Waste Management Complex Cold Test Pit. These major demonstrations are Remote Characterization System, Remote Excavation System, Overburden Removal, Waste Isolation, Contamination Control Unit, Rapid Monitoring Unit, and Fixation of Soil Surface Contamination. This document is the basic operational planning document for BWID deployment of the INEL field demonstrations. Additional sections deal briefly with four nonINEL field and laboratory demonstrations (Buried Waste Retrieval, Arc Melter Vitrification, Graphite DC Plasma Arc Melter, and Fixed Hearth Plasma Process) and with four INEL laboratory demonstrations (Electrostatic Curtain, Thermal Kinetics, Multiaxis Crane Control System, and Dig-Face Characterization)

UNSAT-H infiltration model calibration at the Subsurface Disposal Area, Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Martian, P.

1995-10-01

Soil moisture monitoring data from the expanded neutron probe monitoring network located at the Subsurface Disposal Area (SDA) of the Idaho National Engineering Laboratory (INEL) were used to calibrate numerical infiltration models for 15 locations within and near the SDA. These calibrated models were then used to simulate infiltration into the SDA surficial sediments and underlying basalts for the entire operational period of the SDA (1952--1995). The purpose of performing the simulations was to obtain a time variant infiltration source term for future subsurface pathway modeling efforts as part of baseline risk assessment or performance assessments. The simulation results also provided estimates of the average recharge rate for the simulation period and insight into infiltration patterns at the SDA. These results suggest that the average aquifer recharge rate below the SDA may be at least 8 cm/yr and may be as high as 12 cm/yr. These values represent 38 and 57% of the average annual precipitation occurring at the INEL, respectively. The simulation results also indicate that the maximum evaporative depth may vary between 28 and 148 cm and is highly dependent on localized lithology within the SDA

Environmental assessment: Closure of the Waste Calcining Facility (CPP-633), Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

1996-07-01

The U.S. Department of Energy (DOE) proposes to close the Waste Calcining Facility (WCF). The WCF is a surplus DOE facility located at the Idaho Chemical Processing Plant (ICPP) on the Idaho National Engineering Laboratory (INEL). Six facility components in the WCF have been identified as Resource Conservation and Recovery Ace (RCRA)-units in the INEL RCRA Part A application. The WCF is an interim status facility. Consequently, the proposed WCF closure must comply with Idaho Rules and Standards for Hazardous Waste contained in the Idaho Administrative Procedures Act (IDAPA) Section 16.01.05. These state regulations, in addition to prescribing other requirements, incorporate by reference the federal regulations, found at 40 CFR Part 265, that prescribe the requirements for facilities granted interim status pursuant to the RCRA. The purpose of the proposed action is to reduce the risk of radioactive exposure and release of hazardous constituents and eliminate the need for extensive long-term surveillance and maintenance. DOE has determined that the closure is needed to reduce potential risks to human health and the environment, and to comply with the Idaho Hazardous Waste Management Act (HWMA) requirements

TRAC-PF1/MOD2 status and plans

International Nuclear Information System (INIS)

Spore, J.W.; Steinke, R.G.; Nelson, R.A.; Cappiello, M.W.; Jenks, R.

1989-01-01

The development of the TRAC-PF1/MOD1 code was completed in July 1988 with the release of Version 14.4. A TRAC-PF1/MOD2 code development plan addresses code deficiencies identified in the MOD1 code in order to provide an accurate and defensible tool that can be used to simulate large-break loss-of-coolant accidents (LOCAs), small-break LOCAs, and operational transients. The MOD2 code development plan is an international cooperative effort that includes contributions from Los Alamos National Laboratory, Idaho National Engineering Laboratory (INEL), Japanese Atomic Energy Research Institute (JAERI), Cray Research, Central Electricity Generating Board (CEGB), and United Kingdom Atomic Energy Authority (UKAEA)

Separation technologies for the treatment of Idaho National Engineering Laboratory wastes

Energy Technology Data Exchange (ETDEWEB)

Todd, T.A. [Idaho National Engineering Lab., Idaho Falls, ID (United States)

1997-10-01

Currently about 6.8 million L of acidic, radioactive liquid waste that is not amenable to calcination, and about 3800 m{sup 3} of calcine exist at the ICPP. Legal drivers (court orders) and agreements between the state of Idaho, the U.S. Navy, and DOE exist that obligate INEL to develop, demonstrate, and implement technologies for treatment and interim storage of the radioactive liquid and calcine wastes. Per these agreements, all tank waste must be removed from the underground liquid storage tanks by the year 2012, and high-level radioactive waste must be treated and removed from INEL by 2035. Separation of the radionuclides from the wastes, followed by immobilization of the high-activity and low-activity fractions in glass and grout, respectively, is the approach preferred by INEL. Technologies to remove actinides (U, Np, Pu, and Am), Cs, Sr, and possibly Tc from highly acidic solutions are required to process INEL wastes. Decontamination of the wastes to NRC Class A low-level waste (LLW) is planned. Separation and isolation of Resource Conservation and Recovery Act (RCRA) metals (Hg, Pb, Cd, and Cr) from the highly radioactive waste streams may also be required. Remediation efforts will begin in FY 1997 to remove volatile organic compounds (VOCs) and radionuclides (Cs and Sr) from groundwater located at the Test Area North facility at INEL. A plume of VOCs and radionuclides has spread from the former TSF-05 injection well, and a Comprehensive Environmental Response, Conservation, and Liability Act (CERCLA) remediation action is under way. A Record of Decision was signed in August 1995 that commits INEL to remediate the plume from TSF-05. Removal of Sr and Cs from the groundwater using commercially available ion-exchange resins has been unsuccessful at meeting maximum contaminant levels, which are 119 pCi/L and 8 pCi/L for Cs and Sr, respectively. Cesium and Sr are the major contaminants that must be removed from the groundwater.

Evaporation Basin Test Reactor Area, Idaho National Engineering Laboratory: Environmental assessment

International Nuclear Information System (INIS)

1991-12-01

The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA-0501, on the construction and operation of the proposed Evaporation Basin at the Test Reactor Area (TRA) at the Idaho National Engineering Laboratory (INEL) near Idaho Falls, Idaho. Based on the analyses in the EA, DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment, within the meaning of the National Environmental Policy Act (NEPA) of 1969. Therefore, the preparation of an environmental impact statement (EIS) is not required, and the Department is issuing this Finding of No Significant Impact

Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs draft environmental impact statement

International Nuclear Information System (INIS)

1994-06-01

The US Department of Energy (DOE) has prepared this report to assist its management in making two decisions. The first decision, which is programmatic, is to determine the management program for DOE spent nuclear fuel. The second decision is on the future direction of environmental restoration, waste management, and spent nuclear fuel management activities at the Idaho National Engineering Laboratory. Volume 1 of the EIS, which supports the programmatic decision, considers the effects of spent nuclear fuel management on the quality of the human and natural environment for planning years 1995 through 2035. DOE has derived the information and analysis results in Volume 1 from several site-specific appendixes. Volume 2 of the EIS, which supports the INEL-specific decision, describes environmental impacts for various environmental restoration, waste management, and spent nuclear fuel management alternatives for planning years 1995 through 2005. This Appendix B to Volume 1 considers the impacts on the INEL environment of the implementation of various DOE-wide spent nuclear fuel management alternatives. The Naval Nuclear Propulsion Program, which is a joint Navy/DOE program, is responsible for spent naval nuclear fuel examination at the INEL. For this appendix, naval fuel that has been examined at the Naval Reactors Facility and turned over to DOE for storage is termed naval-type fuel. This appendix evaluates the management of DOE spent nuclear fuel including naval-type fuel

Initial performance assessment of the disposal of spent nuclear fuel and high-level waste stored at Idaho National Engineering Laboratory. Volume 2: Appendices

Energy Technology Data Exchange (ETDEWEB)

Rechard, R.P. [ed.

1993-12-01

This performance assessment characterized plausible treatment options conceived by the Idaho National Engineering Laboratory (INEL) for its spent fuel and high-level radioactive waste and then modeled the performance of the resulting waste forms in two hypothetical, deep, geologic repositories: one in bedded salt and the other in granite. The results of the performance assessment are intended to help guide INEL in its study of how to prepare wastes and spent fuel for eventual permanent disposal. This assessment was part of the Waste Management Technology Development Program designed to help the US Department of Energy develop and demonstrate the capability to dispose of its nuclear waste, as mandated by the Nuclear Waste Policy Act of 1982. The waste forms comprised about 700 metric tons of initial heavy metal (or equivalent units) stored at the INEL: graphite spent fuel, experimental low enriched and highly enriched spent fuel, and high-level waste generated during reprocessing of some spent fuel. Five different waste treatment options were studied; in the analysis, the options and resulting waste forms were analyzed separately and in combination as five waste disposal groups. When the waste forms were studied in combination, the repository was assumed to also contain vitrified high-level waste from three DOE sites for a common basis of comparison and to simulate the impact of the INEL waste forms on a moderate-sized repository, The performance of the waste form was assessed within the context of a whole disposal system, using the U.S. Environmental Protection Agency`s Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes, 40 CFR 191, promulgated in 1985. Though the waste form behavior depended upon the repository type, all current and proposed waste forms provided acceptable behavior in the salt and granite repositories.

Initial performance assessment of the disposal of spent nuclear fuel and high-level waste stored at Idaho National Engineering Laboratory. Volume 1, Methodology and results

Energy Technology Data Exchange (ETDEWEB)

Rechard, R.P. [ed.

1993-12-01

This performance assessment characterized plausible treatment options conceived by the Idaho National Engineering Laboratory (INEL) for its spent fuel and high-level radioactive waste and then modeled the performance of the resulting waste forms in two hypothetical, deep, geologic repositories: one in bedded salt and the other in granite. The results of the performance assessment are intended to help guide INEL in its study of how to prepare wastes and spent fuel for eventual permanent disposal. This assessment was part of the Waste Management Technology Development Program designed to help the US Department of Energy develop and demonstrate the capability to dispose of its nuclear waste. Although numerous caveats must be placed on the results, the general findings were as follows: Though the waste form behavior depended upon the repository type, all current and proposed waste forms provided acceptable behavior in the salt and granite repositories.

Geologic processes in the RWMC area, Idaho National Engineering Laboratory: Implications for long term stability and soil erosion at the radioactive waste management complex

International Nuclear Information System (INIS)

Hackett, W.R.; Tullis, J.A.; Smith, R.P.

1995-09-01

The Radioactive Waste Management Complex (RWMC) is the disposal and storage facility for low-level radioactive waste at the Idaho National Engineering Laboratory (INEL). Transuranic waste and mixed wastes were also disposed at the RWMC until 1970. It is located in the southwestern part of the INEL about 80 km west of Idaho Falls, Idaho. The INEL occupies a portion of the Eastern Snake River Plain (ESRP), a low-relief, basalt, and sediment-floored basin within the northern Rocky Mountains and northeastern Basin and Range Province. It is a cool and semiarid, sagebrush steppe desert characterized by irregular, rolling terrain. The RWMC began disposal of INEL-generated wastes in 1952, and since 1954, wastes have been accepted from other Federal facilities. Much of the waste is buried in shallow trenches, pits, and soil vaults. Until about 1970, trenches and pits were excavated to the basalt surface, leaving no sediments between the waste and the top of the basalt. Since 1970, a layer of sediment (about 1 m) has been left between the waste and the basalt. The United States Department of Energy (DOE) has developed regulations specific to radioactive-waste disposal, including environmental standards and performance objectives. The regulation applicable to all DOE facilities is DOE Order 5820.2A (Radioactive Waste Management). An important consideration for the performance assessment of the RWMC is the long-term geomorphic stability of the site. Several investigators have identified geologic processes and events that could disrupt a radioactive waste disposal facility. Examples of these open-quotes geomorphic hazardsclose quotes include changes in stream discharge, sediment load, and base level, which may result from climate change, tectonic processes, or magmatic processes. In the performance assessment, these hazards are incorporated into scenarios that may affect the future performance of the RWMC

An Overview of INEL Fusion Safety R&D Facilities

Science.gov (United States)

McCarthy, K. A.; Smolik, G. R.; Anderl, R. A.; Carmack, W. J.; Longhurst, G. R.

1997-06-01

The Fusion Safety Program at the Idaho National Engineering Laboratory has the lead for fusion safety work in the United States. Over the years, we have developed several experimental facilities to provide data for fusion reactor safety analyses. We now have four major experimental facilities that provide data for use in safety assessments. The Steam-Reactivity Measurement System measures hydrogen generation rates and tritium mobilization rates in high-temperature (up to 1200°C) fusion relevant materials exposed to steam. The Volatilization of Activation Product Oxides Reactor Facility provides information on mobilization and transport and chemical reactivity of fusion relevant materials at high temperature (up to 1200°C) in an oxidizing environment (air or steam). The Fusion Aerosol Source Test Facility is a scaled-up version of VAPOR. The ion-implanta-tion/thermal-desorption system is dedicated to research into processes and phenomena associated with the interaction of hydrogen isotopes with fusion materials. In this paper we describe the capabilities of these facilities.

Fusion Safety Program annual report, Fiscal Year 1993

International Nuclear Information System (INIS)

Longhurst, G.R.; Cadwallader, L.C.; Dolan, T.J.; Herring, J.S.; McCarthy, K.A.; Merrill, B.J.; Motloch, C.G.; Petti, D.A.

1993-12-01

This report summarizes the major activities of the Fusion Safety Program in Fiscal Year 1993. The Idaho National Engineering Laboratory (INEL) has been designated by DOE as the lead laboratory for fusion safety, and EG ampersand G Idaho, Inc., is the prime contractor for INEL operations. The Fusion Safety Program was initiated in 1979. Activities are conducted at the INEL and in participating organizations, including universities and private companies. Technical areas covered in the report include tritium safety, beryllium safety, activation product release, reactions involving potential plasma-facing materials, safety of fusion magnet systems, plasma disruptions and edge physics modeling, risk assessment failure rates, computer codes for reactor transient analysis, and regulatory support. These areas include work completed in support of the International Thermonuclear Experimental Reactor (ITER). Also included in the report are summaries of the safety and environmental studies performed at the INEL for the Tokamak Physics Experiment and the Tokamak Fusion Test Reactor projects at the Princeton Plasma Physics Laboratory and a summary of the technical support for the ARIES/PULSAR commercial reactor design studies

Abstracts and parameter index database for reports pertaining to the unsaturated zone and surface water-ground water interactions at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Bloomsburg, G.; Finnie, J.; Horn, D.; King, B.; Liou, J.

1993-05-01

This report is a product generated by faculty at the University of Idaho in support of research and development projects on Unsaturated Zone Contamination and Transport Processes, and on Surface Water-Groundwater Interactions and Regional Groundwater Flow at the Idaho National Engineering Laboratory. These projects are managed by the State of Idaho's INEL Oversight Program under a grant from the US Department of Energy. In particular, this report meets project objectives to produce a site-wide summary of hydrological information based on a literature search and review of field, laboratory and modeling studies at INEL, including a cross-referenced index to site-specific physical, chemical, mineralogic, geologic and hydrologic parameters determined from these studies. This report includes abstracts of 149 reports with hydrological information. For reports which focus on hydrological issues, the abstracts are taken directly from those reports; for reports dealing with a variety of issues beside hydrology, the abstracts were generated by the University of Idaho authors concentrating on hydrology-related issues. Each abstract is followed by a ''Data'' section which identifies types of technical information included in a given report, such as information on parameters or chemistry, mineralogy, stream flows, water levels. The ''Data'' section does not include actual values or data

Characterizing aquifer hydrogeology and anthropogenic chemical influences on groundwater near the Idaho Chemical Processing Plant, Idaho National Engineering Laboratory, Idaho

International Nuclear Information System (INIS)

Fromm, J.M.

1995-01-01

A conceptual model of the Eastern Snake River Plain aquifer in the vicinity of monitoring well USGS-44, downgradient of the Idaho Chemical Processing Plant (ICPP) on the Idaho National Engineering Laboratory (INEL), was developed by synthesis and comparison of previous work (40 years) and new investigations into local natural hydrogeological conditions and anthropogenic influences. Quantitative tests of the model, and other recommendations are suggested. The ICPP recovered fissionable uranium from spent nuclear fuel rods and disposed of waste fluids by release to the regional aquifer and lithosphere. Environmental impacts were assessed by a monitoring well network. The conceptual model identifies multiple, highly variable, interacting, and transient components, including INEL facilities multiple operations and liquid waste handling, systems; the anisotropic, in homogeneous aquifer; the network of monitoring and production wells, and the intermittent flow of the Big Lost River. Pre anthropogenic natural conditions and early records of anthropogenic activities were sparsely or unreliably documented making reconstruction of natural conditions or early hydrologic impacts impossible or very broad characterizations

Annual technology assessment and progress report for the Buried Transuranic Waste Studies Program at the Idaho National Engineering Laboratory (1987)

International Nuclear Information System (INIS)

Loomis, G.G.; Low, J.O.

1988-01-01

This report presents FY-87 activities for the Buried Transuranic (TRU) Waste Studies Program at the Idaho National Engineering Laboratory (INEL). This program investigates techniques to provide long-term confinement of buried TRU waste, as well as methods of retrieval. The confinement method of in situ grouting was examined in a simulated shallow-land buried TRU waste pit constructed adjacent to the RWMC TRU waste burial pits. The in situ grouting technique involved an experimental dyanmic compaction process which simultaneously grouts and compacts the waste. The simulated waste pit consisted of regions of randomly dumped drums, stacked boxes, and stacked drums, thus representing the various conditions of buried waste at the RWMC. Simulated waste and airborne tracers were loaded into the various simulated buried waste containers. Pregrouting and post-grouting data, such as hydraulic conductivity, were obtained to assess the hydrological integrity of the grouted waste material. In addition, post-grouting destructive examinations were performed and the results analyzed. Retrieval and processing of the TRU buried waste is also being examined at the INEL. At a conceptual level, retrieval of TRU buried waste involves a movable containment building to confine airborne particulate, heavy equipment to remove the waste, processing equipment, and equipment to control the air quality within the building. Studies were performed in FY-87 to identify containment building requirements such as type, mobility, and ventilation. An experimental program to demonstrate the retrieval technique using existing INEL heavy equipment has also been identified. 11 refs., 17 figs., 11 tabs

Fusion Safety Program annual report, fiscal year 1984

International Nuclear Information System (INIS)

Crocker, J.G.; Holland, D.F.

1985-06-01

This report summarizes the Fusion Safety Program major activities in fiscal year 1984. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory and EG and G Idaho, Inc., is the prime contractor for this program, which was initiated in 1979. A report section titled ''Activities at the INEL'' includes progress reports on the tritium implantation experiment, tritium blanket permeation, volatilization of reactor alloys, plasma disruptions, a comparative blanket safety assessment, transient code development, and a discussion of the INEL's participation in the Tokamak Fusion Core Experiment (TFCX) design study. The report section titled ''Outside Contracts'' includes progress reports on tritium conversion by the Oak Ridge National Laboratory (ORNL), lithium-lead reactions by the Hanford Engineering Development Laboratory (HEDL) and the University of Wisconsin, magnet safety by the Francis Bitter Magnet Laboratory of the Massachusetts Institute of Technology (MIT) and Argonne National Laboratory (ANL), risk assessment by MIT, tritium retention by the University of Virginia, and activation product release by GA Technologies. A list of publications produced during the year and brief descriptions of activities planned for FY-1985 are also included

Department of Energy, highly enriched uranium ES ampersand H vulnerability assessment, Idaho National Engineering Laboratory site assessment team report

International Nuclear Information System (INIS)

1996-01-01

In accordance with the February 22, 1996 directive issued by Secretary of Energy O'Leary on the Vulnerability Assessment of Highly Enriched Uranium (HEU) Storage, the Idaho National Engineering Laboratory conducted an assessment of the site's HEU holdings and any associated vulnerabilities. The assessment was conducted between April 25 and May 24, 1996. The scope of this assessment, as defined in the Assessment Plan, included all HEU, and any spent fuel not evaluated in the Spent Fuel Vulnerability Assessment. Addressed in this assessment were all of the holdings at the Idaho National Engineering Laboratory (INEL) except any located at Argonne National Laboratory-West (ANL-W) and the Naval Reactors Facility. Excluded from the assessment were those HEU holdings previously assessed in the Idaho National Engineering Laboratory Spent Nuclear Fuel Inventory and Vulnerability Site Assessment Report and any HEU holdings evaluated in the Plutonium Vulnerability Assessment Report

Confirmatory radiological survey of the BORAX-V turbine building Idaho National Engineering Laboratory, Idaho Falls, Idaho

International Nuclear Information System (INIS)

Stevens, G.H.; Coleman, R.L.; Jensen, M.K.; Pierce, G.A.; Egidi, P.V.; Mather, S.K.

1993-01-01

An independent assessment of the remediation of the BORAX-V (Boiling Water Reactor Experiment) turbine building at the Idaho National Engineering Laboratory (INEL), Idaho Falls, Idaho, was accomplished by the Oak Ridge National Laboratory Pollutant Assessments Group (ORNL/PAG). The purpose of the assessment was to confirm the site's compliance with applicable Department of Energy guidelines. The assessment included reviews of both the decontamination and decommissioning Plan and data provided from the pre- and post-remedial action surveys and an independent verification survey of the facility. The independent verification survey included determination of background exposure rates and soil concentrations, beta-gamma and gamma radiation scans, smears for detection of removable contamination, and direct measurements for alpha and beta-gamma radiation activity on the basement and mezzanine floors and the building's interior and exterior walls. Soil samples were taken, and beta-gamma and gamma radiation exposure rates were measured on areas adjacent to the building. Results of measurements on building surfaces at this facility were within established contamination guidelines except for elevated beta-gamma radiation levels located on three isolated areas of the basement floor. Following remediation of these areas, ORNL/PAG reviewed the remedial action contractor's report and agreed that remediation was effective in removing the source of the elevated direct radiation. Results of all independent soil analyses for 60 Co were below the detection limit. The highest 137 Cs analysis result was 4.6 pCi/g; this value is below the INEL site-specific guideline of 10 pCi/g

Mineralogy and depositional sources of sedimentary interbeds beneath the Idaho National Engineering Laboratory; eastern Snake River Plain, Idaho

International Nuclear Information System (INIS)

Reed, M.F.

1994-01-01

Idaho State University, in cooperation with the U.S. Geological Survey, and the U.S. Department of Energy, collected 57 samples of sedimentary interbeds at 19 sites at the Idaho National Engineering Laboratory (INEL) for mineralogical analysis. Previous work by the U.S. Geological Survey on surficial sediments showed that ratios detrital of quartz, total feldspars, and calcite can be used to distinguish the sedimentary mineralogy of specific stream drainages at the INEL. Semi-quantitative x-ray diffraction analyses were used to determine mineral abundances in the sedimentary interbeds. Samples were collected from wells at the New Production Reactor (NPR) area, Idaho Chemical Processing Plant (ICPP), Test Reactor Area (TRA), miscellaneous sites, Radioactive Waste Management Complex (RWMC), Naval Reactors Facility (NRF), and Test Area North (TAN). Normalized mean percentages of quartz, feldspar, and carbonate were calculated from sample data sets at each site. Percentages for quartz, feldspar, and carbonate from the NPR, ICPP, TRA, miscellaneous sites, RWMC, and NRF ranged from 37 to 59, 26 to 40, and 5 to 25, respectively. Percentages for quartz, feldspar, and carbonate from wells at Test Area North (TAN) were 24, 10, and 66, respectively. Mineralogical data indicate that sedimentary interbed samples collected from the NPR, ICPP, TRA, miscellaneous sites, RWMC, and NRF correlate with surficial sediment samples from the present day Big Lost River. Sedimentary interbeds from TAN sites correlate with surficial sediment samples from Birch Creek. These correlations suggest that the sources for the sediments at and near the INEL have remained relatively consistent for the last 580,000 years. 12 refs., 4 figs., 3 tabs

Idaho National Engineering Laboratory Radiological Control performance indicator report: First quarter, calendar year 1995

International Nuclear Information System (INIS)

Aitken, S.B.

1995-07-01

The INEL Radiological Control Performance Indicator Report is provided quarterly, inaccordance with Article 133 of the INEL Radiological Control Manual. Indicators are used as a measure of performance of the Radiological Control Program and as a motivation for improvement, not as a goal in themselves. These indicators should be used by management to assist in focusing priorities and attention and adherence to As-Low-As-Reasonably-Achievable (ALARA) practices. The ALARA Committees establish ALARA goals for the INEL based on forecasts and goals provided by each facility organizational manager or supervisor.Performance goals are realistic and measurable. Stringent goals are set at least annually to reflect expected workloads and improvement of radiological performance. Goals higher than previous goals may occasionally be set due to changes in work scope or mission. The INEL Radiological Control Performance Indicators consist of: Collective dose in person-rem; average worker dose, maximum dose to a worker, and maximum neutron dose to a worker;the number of skin and clothing contaminations, including the number of contaminated wounds and facial contaminations; the number of radioactive material intakes; the area of Contamination, High Contamination, and Airborne Radioactivity Areas in square feet; and airborne radioactivity events and spills

Preliminary Hanford technical input for the Department of Energy programmatic spent nuclear fuel management and Idaho National Engineering Laboratory environmental restoration and waste management programs environmental impact statement

International Nuclear Information System (INIS)

Bergsman, K.H.

1995-03-01

The US Department of Energy (DOE) is currently evaluating its programmatic options for the safe management of its diverse spent nuclear fuel (SNF) inventory in the Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Environmental Impact Statement (SNF and INEL EIS). In the SNF and INEL EIS, the DOE is assessing five alternatives for SNF management, which consider at which of the DOE sites each of the various SNF types should be managed until ultimate disposition. The range of SNF inventories considered for management at the Hanford Site in the SNF and INEL EIS include the current Hanford Site inventory, only the current Hanford Site defense production SNF inventory, the DOE complex-wide SNF inventory, or none at all. Site-specific SNF management decisions will be evaluated in separate National Environmental Policy Act evaluations. Appendixes A and B include information on (1) additional facilities required to accommodate inventories of SNF within each management alternative, (2) existing and new SNF management facility descriptions, (3) facility costs for construction and operation, (4) facility workforce requirements for construction and operation, and (5) facility discharges. The information was extrapolated from existing analyses to the extent possible. New facility costs, manpower requirements, and similar information are based on rough-order-of-magnitude estimates

Accelerated Leach Testing of GLASS: ALTGLASS Version 3.0

Energy Technology Data Exchange (ETDEWEB)

Trivelpiece, Cory L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Jantzen, Carol M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Crawford, Charles L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2016-12-31

The Accelerated Leach Testing of GLASS (ALTGLASS) database is a collection of data from short- and long-term product consistency tests (PCT, ASTM C1285 A and B) on high level waste (HLW) as well as low activity waste (LAW) glasses. The database provides both U.S. and international researchers with an archive of experimental data for the purpose of studying, modeling, or validating existing models of nuclear waste glass corrosion. The ALTGLASS database is maintained and updated by researchers at the Savannah River National Laboratory (SRNL). This newest version, ALTGLASS Version 3.0, has been updated with an additional 503 rows of data representing PCT results from corrosion experiments conducted in the United States by the Savannah River National Laboratory, Pacific Northwest National Laboratory, Argonne National Laboratory, and the Vitreous State Laboratory (SRNL, PNNL, ANL, VSL, respectively) as well as the National Nuclear Laboratory (NNL) in the United Kingdom.

Accelerated Leach Testing of GLASS: ALTGLASS Version 3.0

International Nuclear Information System (INIS)

Trivelpiece, Cory L.; Jantzen, Carol M.; Crawford, Charles L.

2016-01-01

The Accelerated Leach Testing of GLASS (ALTGLASS) database is a collection of data from short- and long-term product consistency tests (PCT, ASTM C1285 A and B) on high level waste (HLW) as well as low activity waste (LAW) glasses. The database provides both U.S. and international researchers with an archive of experimental data for the purpose of studying, modeling, or validating existing models of nuclear waste glass corrosion. The ALTGLASS database is maintained and updated by researchers at the Savannah River National Laboratory (SRNL). This newest version, ALTGLASS Version 3.0, has been updated with an additional 503 rows of data representing PCT results from corrosion experiments conducted in the United States by the Savannah River National Laboratory, Pacific Northwest National Laboratory, Argonne National Laboratory, and the Vitreous State Laboratory (SRNL, PNNL, ANL, VSL, respectively) as well as the National Nuclear Laboratory (NNL) in the United Kingdom.

Pipe damping studies

International Nuclear Information System (INIS)

Ware, A.G.

1986-01-01

The Idaho National Engineering Laboratory (INEL) is conducting a research program to assist the United States Nuclear Regulatory Commission (USNRC) in determining best-estimate damping values for use in the dynamic analysis of nuclear power plant piping systems. This paper describes four tasks in the program that were undertaken in FY-86. In the first task, tests were conducted on a 5-in. INEL laboratory piping system and data were analyzed from a 6-in. laboratory system at the ANCO Engineers facility to investigate the parameters influencing damping in the seismic frequency range. Further tests were conducted on 3- and 5-in. INEL laboratory piping systems as the second task to determine damping values representative of vibrations in the 33 to 100 Hz range, typical of hydrodynamic transients. In the third task a statistical evaluation of the available damping data was conduted to determine probability distributions suitable for use in probabilistic risk assessments (PRAs), and the final task evaluated damping data at high strain levels

Air Emission Inventory for the Idaho National Engineering Laboratory: 1992 emissions report

Energy Technology Data Exchange (ETDEWEB)

Stirrup, T.S.

1993-06-01

This report presents the 1992 Air Emission Inventory for the Idaho National Engineering Laboratory. Originally, this report was in response to the Environmental Oversight and Monitoring Agreement in 1989 between the State of Idaho and the Department of Energy Idaho Field Office, and a request from the Idaho Air Quality Bureau. The current purpose of the Air Emission Inventory is to provide the basis for the preparation of the INEL Permit-to-Operate (PTO) an Air Emission Source Application, as required by the recently promulgated Title V regulations of the Clean Air Act. This report includes emissions calculations from 1989 to 1992. The Air Emission Inventory System, an ORACLE-based database system, maintains the emissions inventory.

Air Emission Inventory for the Idaho National Engineering Laboratory: 1992 emissions report

International Nuclear Information System (INIS)

Stirrup, T.S.

1993-06-01

This report presents the 1992 Air Emission Inventory for the Idaho National Engineering Laboratory. Originally, this report was in response to the Environmental Oversight and Monitoring Agreement in 1989 between the State of Idaho and the Department of Energy Idaho Field Office, and a request from the Idaho Air Quality Bureau. The current purpose of the Air Emission Inventory is to provide the basis for the preparation of the INEL Permit-to-Operate (PTO) an Air Emission Source Application, as required by the recently promulgated Title V regulations of the Clean Air Act. This report includes emissions calculations from 1989 to 1992. The Air Emission Inventory System, an ORACLE-based database system, maintains the emissions inventory

Quality Assurance Project Plan for the Gas Generation Testing Program at the INEL

International Nuclear Information System (INIS)

1994-10-01

The data quality objectives (DQOs) for the Program are to evaluate compliance with the limits on total gas generation rates, establish the concentrations of hydrogen and methane in the total gas flow, determine the headspace concentration of VOCs in each drum prior to the start of the test, and obtain estimates of the concentrations of several compounds for mass balance purposes. Criteria for the selection of waste containers at the INEL and the parameters that must be characterized prior to and during the tests are described. Collection of gaseous samples from 55-gallon drums of contact-handled transuranic waste for the gas generation testing is discussed. Analytical methods and calibrations are summarized. Administrative quality control measures described in this QAPjP include the generation, review, and approval of project documentation; control and retention of records; measures to ensure that personnel, subcontractors or vendors, and equipment meet the specifications necessary to achieve the required data quality for the project

The role of performance assessment in the evaluation of remedial action alternatives for the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Rood, A.S.; Case, M.J.

1988-01-01

The Idaho National Engineering Laboratory (INEL) is operated by the Department of Energy (DOE) and is involved in nuclear research and development. The Radioactive Waste Management Complex (RWMC) at the INEL serves as a disposal facility for low level radioactive wastes generated onsite. Transuranic (TRU) wastes received from other DOE sites are currently stored at the RWMC, but were buried at the facility from 1952 until 1970. Recent findings of the Subsurface Investigations Program have determined that migration of TRU nuclides and hazardous materials from the RWMC has occurred. The primary source of organics in the buried TRU waste was generated by the Rocky Flats Plant. The INEL has proposed an aggressive four-year action plan for buried TRU waste. As a part of this plan, a task has been identified to evaluate existing remedial technologies for preventing further contaminant migration or removing the source of TRU radionuclides and nonradioactive hazardous material from the RWMC. A systems approach is being applied to evaluate, compare and recommend technologies or combinations of technologies. One criterion used in the evaluation is the net risk reduction afforded by each proposed remedial action. The method used to develop the criterion relies on models to assess the potential pathways and scenarios for the migration of radioactive and nonradioactive materials and the subsequent exposure of individuals to those materials. This paper describes the approach used to assess the performance of various remedial actions and the results obtained to date

Radioactive waste management information, 1982 summary and record-to-date

International Nuclear Information System (INIS)

Cassidy, G.B.

1983-07-01

This document summarizes radioactive waste data records for the Idaho National Engineering Laboratory (INEL) compiled since 1952. Kinds of information include volume, radioactivity, isotopic identity, origin, and decay status. The radioactive waste data presented was obtained from the INEL Radioactive Waste Management Information System (RWMIS). This report is updated annually to incorporate waste management data for the current year and reflects changes in previous annual reports. Changes are made to more accurately reflect the current status of waste operations at the INEL

Vapor vacuum extraction treatability study at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Herd, M.D.; Matthern, G.; Michael, D.L.; Spang, N.; Downs, W.; Weidner, J.; Cleary, P.

1993-01-01

During the 1960s and early 1970s, barreled mixed waste containing volatile organic compounds (VOCS) and radioactive waste was buried at the Subsurface Disposal Area (SDA) at the Idaho National Engineering Laboratory (INEL) Radioactive Waste Management Complex (RWMC). Over time, some of the barrels have deteriorated allowing, VOC vapors to be released into the vadose zone. The primary VOC contaminates of concern are CCl 4 and trichloroethylene; however, chloroform, tetrachloroethylene, and 1,1,1-trichloroethane have also been detected. Vapor Vacuum Extraction (VVE) is one alternative being considered for remediation of the RWMC SDA vadose zone. A proposed pilot-scale treatability study (TS) will provide operation and maintenance costs for the design of the potential scale-up of the system

Stable isotopes of hydrogen and oxygen in surface water and ground water at selected sites on or near the Idaho National Engineering Laboratory, Idaho

International Nuclear Information System (INIS)

Ott, D.S.; Cecil, L.D.; Knobel, L.L.

1994-01-01

Relative stable isotopic ratios for hydrogen and oxygen compared to standard mean ocean water are presented for water from 4 surface-water sites and 38 ground-water sites on or near the Idaho National Engineering Laboratory (INEL). The surface-water samples were collected monthly from March 1991 through April 1992 and after a storm event on June 18, 1992. The ground-water samples either were collected during 1991 or 1992. These data were collected as part of the US Geological Survey's continuing hydrogeological investigations at the INEL. The relative isotopic ratios of hydrogen and oxygen are reported as delta 2 H (δ 2 H) and as delta 18 O (δ 18 O), respectively. The values of δ 2 H and δ 18 O in water from the four surface-water sites ranged from -143.0 to -122 and from -18.75 to -15.55, respectively. The values of δ 2 H and δ 18 O in water from the 38 ground-water sites ranged from -141.0 to -120.0 and from -18.55 to -14.95, respectively

New Open-Source Version of FLORIS Released | News | NREL

Science.gov (United States)

New Open-Source Version of FLORIS Released New Open-Source Version of FLORIS Released January 26 , 2018 National Renewable Energy Laboratory (NREL) researchers recently released an updated open-source simplified and documented. Because of the living, open-source nature of the newly updated utility, NREL

EC4 European Syllabus for Post-Graduate Training in Clinical Chemistry and Laboratory Medicine: version 3 - 2005.

Science.gov (United States)

Zerah, Simone; McMurray, Janet; Bousquet, Bernard; Baum, Hannsjorg; Beastall, Graham H; Blaton, Vic; Cals, Marie-Josèphe; Duchassaing, Danielle; Gaudeau-Toussaint, Marie-Françoise; Harmoinen, Aimo; Hoffmann, Hans; Jansen, Rob T; Kenny, Desmond; Kohse, Klaus P; Köller, Ursula; Gobert, Jean-Gérard; Linget, Christine; Lund, Erik; Nubile, Giuseppe; Opp, Matthias; Pazzagli, Mario; Pinon, Georges; Queralto, José M; Reguengo, Henrique; Rizos, Demetrios; Szekeres, Thomas; Vidaud, Michel; Wallinder, Hans

2006-01-01

The EC4 Syllabus for Postgraduate Training is the basis for the European Register of Specialists in Clinical Chemistry and Laboratory Medicine. The syllabus: Indicates the level of requirements in postgraduate training to harmonise the postgraduate education in the European Union (EU); Indicates the level of content of national training programmes to obtain adequate knowledge and experience; Is approved by all EU societies for clinical chemistry and laboratory medicine. The syllabus is not primarily meant to be a training guide, but on the basis of the overview given (common minimal programme), national societies should formulate programmes that indicate where knowledge and experience is needed. The main points of this programme are: Indicates the level of requirements in postgraduate training to harmonise the postgraduate education in the European Union (EU); Indicates the level of content of national training programmes to obtain adequate knowledge and experience; Is approved by all EU societies for clinical chemistry and laboratory medicine. Knowledge in biochemistry, haematology, immunology, etc.; Pre-analytical conditions; Evaluation of results; Interpretations (post-analytical phase); Laboratory management; and Quality insurance management. The aim of this version of the syllabus is to be in accordance with the Directive of Professional Qualifications published on 30 September 2005. To prepare the common platforms planned in this directive, the disciplines are divided into four categories: Indicates the level of requirements in postgraduate training to harmonise the postgraduate education in the European Union (EU); Indicates the level of content of national training programmes to obtain adequate knowledge and experience; Is approved by all EU societies for clinical chemistry and laboratory medicine. Knowledge in biochemistry, haematology, immunology, etc.; Pre-analytical conditions; Evaluation of results; Interpretations (post-analytical phase); Laboratory

Industrial waste management information for 1990 and record-to-date

International Nuclear Information System (INIS)

Litteer, D.L.; Peterson, C.N.; Sims, A.M.

1991-08-01

This product provides detailed data and graphics on airborne and liquid effluent releases, fuel oil consumption, and water usage for the calendar year 1990. It summarizes industrial waste data records compiled since 1971 for the Idaho National Engineering Laboratory (INEL). The data presented are from the INEL Industrial Waste Management Information System (IWMIS)

A guide for the laboratory information management system (LIMS) for light stable isotopes--Versions 7 and 8

Science.gov (United States)

Coplen, Tyler B.

2000-01-01

The reliability and accuracy of isotopic data can be improved by utilizing database software to (i) store information about samples, (ii) store the results of mass spectrometric isotope-ratio analyses of samples, (iii) calculate analytical results using standardized algorithms stored in a database, (iv) normalize stable isotopic data to international scales using isotopic reference materials, and (v) generate multi-sheet paper templates for convenient sample loading of automated mass-spectrometer sample preparation manifolds. Such a database program, the Laboratory Information Management System (LIMS) for Light Stable Isotopes, is presented herein. Major benefits of this system include (i) a dramatic improvement in quality assurance, (ii) an increase in laboratory efficiency, (iii) a reduction in workload due to the elimination or reduction of retyping of data by laboratory personnel, and (iv) a decrease in errors in data reported to sample submitters. Such a database provides a complete record of when and how often laboratory reference materials have been analyzed and provides a record of what correction factors have been used through time. It provides an audit trail for laboratories. LIMS for Light Stable Isotopes is available for both Microsoft Office 97 Professional and Microsoft Office 2000 Professional as versions 7 and 8, respectively. Both source code (mdb file) and precompiled executable files (mde) are available. Numerous improvements have been made for continuous flow isotopic analysis in this version (specifically 7.13 for Microsoft Access 97 and 8.13 for Microsoft Access 2000). It is much easier to import isotopic results from Finnigan ISODAT worksheets, even worksheets on which corrections for amount of sample (linearity corrections) have been added. The capability to determine blank corrections using isotope mass balance from analyses of elemental analyzer samples has been added. It is now possible to calculate and apply drift corrections to isotopic

1982 environmental monitoring program report for Idaho National Engineering Laboratory site

International Nuclear Information System (INIS)

1983-05-01

The results of the various monitoring programs for 1982 indicated that radioactivity from the Site operations could not be distinguished from worldwide fallout and natural radioactivity in the region. Although some radioactive materials were discharged during Site operations, concentrations and dose to the surrounding population were of no health consequence and were far less than State of Idaho and federal health protection guidelines. This report describes the air, water, and foodstuff samples routinely collected at the INEL boundary locations and at locations distant from the INEL Site. The report also compares and evaluates the sample results and discusses implications

Experience and improved techniques in radiological environmental monitoring at major DOE low-level waste disposal sites

International Nuclear Information System (INIS)

1986-09-01

A summary of routine radiological environmental surveillance programs conducted at major active US Department of Energy (DOE) solid low-level waste (LLW) disposal sites is provided. The DOE disposal sites at which monitoring programs were reviewed include those located at Hanford, Idaho National Engineering Laboratory (INEL), Nevada Test Site (NTS), Los Alamos National Laboratory (LANL), Oak Ridge National Laboratory (ORNL) and Savannah River Plant (SRP). The review is limited to activities conducted for the purpose of monitoring disposal site performance. Areas of environmental monitoring reviewed include air monitoring for particulates and gases, monitoring of surface water runoff, surface water bodies, ground water, monitoring of surface soils and the vadose zone, and monitoring of ambient penetrating radiation. Routine environmental surveillance is conducted at major LLW disposal sites at various levels of effort for specific environmental media. In summary, all sites implement a routine monitoring program for penetrating radiation. Four sites (INEL, NTS, LANL, and SRP) monitor particulates in air specifically at LLW disposal sites. Hanford monitors particulates at LLW sites in conjunction with monitoring of other site operations. Particulates are monitored on a reservationwide network at ORNL. Gases are monitored specifically at active LLW sites operated at NTS, LANL, and SRP. Ground water is monitored specifically at LLW sites at INEL, LANL, and SRP, in conjunction with other operations at Hanford, and as part of a reservationwide program at NTS and ORNL. Surface water is monitored at INEL, LANL, and SRP LLW sites. Surface soil is sampled and analyzed on a routine basis at INEL and LANL. Routine monitoring of the vadose zone is conducted at the INEL and SRP. Techniques and equipment in use are described and other aspects of environmental monitoring programs, such as quality assurance and data base management, are reviewed

Fusion Safety Program annual report: Fiscal year 1986

International Nuclear Information System (INIS)

Holland, D.F.; Merrill, B.J.; Herring, J.S.; Piet, S.J.; Longhurst, G.R.

1987-06-01

This report summarizes the Fusion Safety Program's (FSP) major activities in fiscal year 1986. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory, and EG and G Idaho, Inc., is the prime contractor for FSP, which was initiated in 1979. Activities are conducted at the INEL and in participating facilities, including the Hanford Engineering Development Laboratory (HEDL), the Massachusetts Institute of Technology (MIT), and the University of Wisconsin. The technical areas covered in this report include tritium safety, activation product release, reactions involving lithium breeding materials, safety of fusion magnet systems, plasma disruption, risk assessment methodology, and computer code development for reactor transients. Contributions to the Technical Planning Activity (TPA) and the ''white paper'' study by the Environmental, Safety,and Economics Committee (ESECOM) are summarized. The report also includes a summary of the safety and environmental analysis and documentation performed by the INEL for the Compact Ignition Tokamak (CIT) design project

Engineering simulator applications to emergency preparedness at DOE reactor sites

International Nuclear Information System (INIS)

Beelman, R.J.

1990-01-01

This paper reports that since 1984 the Idaho National Engineering Laboratory (INEL) has conducted twenty-seven comprehensive emergency preparedness exercises at the U.S. Nuclear Regulatory Commission's (NRC) Headquarters Operations Center and Regional Incident Response Centers using the NRC's Nuclear Plant Analyzer (NPA), developed at the INEL, as an engineering simulator. The objective of these exercises has been to assist the NRC in upgrading its preparedness to provide technical support backup and oversight to U.S. commercial nuclear plant licensees during emergencies. With the current focus on Department of Energy (DOE) reactor operational safety and emergency preparedness, this capability is envisioned as a means of upgrading emergency preparedness at DOE production and test reactor sites such as the K-Reactor at Savannah River Laboratory (SRL) and the Advanced Test Reactor (ATR) at INEL

Issues in radioactive mixed waste compliance with RCRA [Resource Conservation and Recovery Act]: Some examples from ongoing operations at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Eaton, D.L.; Smith, T.H.; Clements, T.L. Jr.; Hodge, V.

1990-01-01

Radioactive mixed waste is subject to regulation under both the Resource Conservation and Recovery Act (RCRA) and the Atomic Energy Act (AEA). The regulation of such waste is the responsibility of the Environmental Protection Agency (EPA) and either the Nuclear Regulatory Commission (NRC) or the Department of Energy (DOE), depending on whether the waste is commercially generated or defense-related. The recent application of the RCRA regulations to ongoing operations at the DOE's Idaho National Engineering Laboratory (INEL) are described in greater detail. 8 refs., 2 figs

Environmental surveillance for EG ampersand G Idaho Waste Management facilities at the Idaho National Engineering Laboratory. 1993 annual report

International Nuclear Information System (INIS)

Wilhelmsen, R.N.; Wright, K.C.; McBride, D.W.; Borsella, B.W.

1994-08-01

This report describes calendar year 1993 environmental surveillance activities of Environmental Monitoring of EG ampersand G Idaho, Inc., performed at EG ampersand G Idaho operated Waste Management facilities at the Idaho National Engineering Laboratory (INEL). The major facilities monitored include the Radioactive Waste Management Complex, the Waste Experimental Reduction Facility, the Mixed Waste Storage Facility, and two surplus facilities. Included are results of the sampling performed by the Radiological and Environmental Sciences Laboratory and the United States Geological Survey. The primary purposes of monitoring are to evaluate environmental conditions, to provide and interpret data, to ensure compliance with applicable regulations or standards, and to ensure protection of human health and the environment. This report compares 1993 environmental surveillance data with US Department of Energy derived concentration guides and with data from previous years

Annual report -- 1992: Environmental surveillance for EG ampersand G Idaho Waste Management Facilities at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Wilhelmsen, R.N.; Wright, K.C.; McBride, D.W.

1993-08-01

This report describes the 1992 environmental surveillance activities of the Environmental Monitoring Unit of EG ampersand G Idaho, Inc., at EG ampersand G Idaho-operated Waste Management facilities at the Idaho National Engineering Laboratory (INEL). The major facilities monitored include the Radioactive Waste Management Complex, the Waste Experimental Reduction Facility, the Mixed Waste Storage Facility, and two surplus facilities. Included are some results of the sampling performed by the Radiological and Environmental Sciences Laboratory and the United States Geological Survey. The primary purposes of monitoring are to evaluate environmental conditions, to provide and interpret data, to ensure compliance with applicable regulations or standards, and to ensure protection of human health and the environment. This report compares 1992 environmental surveillance data with DOE derived concentration guides, and with data from previous years

LMFBR safety: Interim test report for the characterization of released particle tests conducted at INEL during FY 1979

International Nuclear Information System (INIS)

Johnson, R.P.; Nelson, C.T.

1979-01-01

Two additional atmospheric sodium release tests were jointly conducted by ESG and ARL at INEL. These tests were conducted under very stable (Pasquill E and G) meteorological conditions where the natural humidity content was high (47 and 96% RH). Sufficient experimental data was obtained on Test 7 to quantitatively qualify the formation of Na 2 CO 3 in the open atmosphere from primary sodium combustion products. These data show that a maximum concentration of approx. 60% Na 2 CO 3 is reached with the plume 100 meters from the release point. This concentration increases slightly as the plume is dispersed beyond 2400 meters. The available particle fallout data is consistent with predictions

INEL waste cleanup

International Nuclear Information System (INIS)

Chapin, J.A.

1979-01-01

Decommissioning and decontamination activities at the Idaho National Engineering Laboratory are discussed. The projects planned and completed are presented. Problems encountered on these projects are discussed. A developmental program is recommended. Contaminated areas consist of test reactors, reactor support facilities, a fuel reprocessing facility and various soil areas. One D and D project in 1960 occurred as a result of an accident at a low-power reactor in which 3 persons were killed, the reactor and containment building were destroyed, and large areas of land were contaminated

Environmental and other evaluations of alternatives for management of defense transuranic waste at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

1982-04-01

Appendices to this report contain the following information: INEL history of Waste Management; text of communications between Idaho and the federal government on long-term management; agency and public response to a proposed environmental impact statement; updated estimates on radiological releases from the slagging-pyrolysis incinerator; modeling studies of subsurface migration of radionuclides; nonradiological emissions and their environmental effects; methods for calculating radiological consequences; analysis of abnormal events in conceptual retrieval and processing operations; environmental contamination by accidental releases; hazards to waste management workers; environmental and other effects of rail and truck shipment of wastes; effects of hypothetical worst-case shipping accidents in urban areas; environmental and other effects of processing INEL transuranic waste at the offsite geological repository; and regulations applicable to INEL TRU waste management

Radioactive waste management information for 1993 and record-to-date

International Nuclear Information System (INIS)

Taylor, K.A.

1994-07-01

This document presents detailed data, bar graphs, and pie charts on volume, radioactivity, isotopic identity, origin, and decay status of radioactive waste for the calendar year 1993. It also summarizes the radioactive waste data records compiled from 1952 to present for the Idaho National Engineering Laboratory (INEL). The data presented are from the INEL Radioactive Waste Management Information System

Radioactive waste management information for 1990 and record-to-date

International Nuclear Information System (INIS)

Litteer, D.L.; Peterson, C.N.; Sims, A.M.

1991-07-01

This document presents detailed data and graphics on volume, radioactivity, isotopic identity, origin, and decay status of radioactive waste for the calendar year 1990. It also summarizes the radioactive waste data records compiled from 1952 to present for the Idaho National Engineering Laboratory (INEL). The data presented are from the INEL Radioactive Waste Management Information System (RWMIS)

The implementation of the CDC version of RELAP5/MOD1/019 on an IBM compatible computer system (AMDAHL 470/V8)

International Nuclear Information System (INIS)

Kolar, W.; Brewka, W.

1984-01-01

RELAP5/MOD1 is an advanced one-dimensional best estimate system code, which is used for safety analysis studies of nuclear pressurized water reactor systems and related integral and separate effect test facilities. The program predicts the system response for large break, small break LOCA and special transients. To a large extent RELAP5/MOD1 is written in Fortran, only a small part of the program is coded in CDC assembler. RELAP5/MOD1 was developed on the CDC CYBER 176 at INEL*. The code development team made use of CDC system programs like the CDC UPDATE facility and incorporated in the program special purpose software packages. The report describes the problems which have been encountered when implementing the CDC version of RELAP5/MOD1 on an IBM compatible computer systems (AMDAHL 470/V8)

Environmental monitoring for EG and G Idaho facilities at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Tkachyk, J.W.; Wright, K.C.; Wilhelmsen, R.N.

1990-08-01

This report describes the 1989 environmental-monitoring activities of the Environmental Monitoring Unit of EG ampersand G Idaho, Inc., at EG ampersand G-operated facilities at the Idaho National Engineering Laboratory (INEL). The major facilities monitored include the Radioactive Waste Management Complex, the Waste Experimental Reduction Facility, the Mixed Waste Storage Facility, and two surplus facilities. Additional monitoring activities performed by Environmental Monitoring are also discussed, including drinking-water monitoring and nonradiological liquid-effluent monitoring, as well as data management. The primary purposes of monitoring are to evaluate environmental conditions and to provide and interpret data, in compliance with applicable regulations, to ensure protection of human health and the environment. This report compares 1989 environmental-monitoring data with derived concentration guides and with data from previous years. This report also presents results of sampling performed by the Radiological and Environmental Sciences Laboratory and by the United States Geological Survey. 17 refs., 49 figs., 11 tabs

Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Draft Environmental Impact Statement

International Nuclear Information System (INIS)

1994-06-01

Two types of projects in the spent nuclear fuel and environmental restoration and waste management activities at the Idaho National Engineering Laboratory (INEL) are described. These are: foreseeable proposed projects where some funding for preliminary planning and/or conceptual design may already be authorized, but detailed design or planning will not begin until the Department of Energy (DOE) has determined that the requirements of the National Environmental Policy Act process for the project have been completed; planned or ongoing projects not yet completed but whose National Environmental Policy Act documentation is already completed or is expected to be completed before the Record of Decision for this Envirorunental Impact Statement (EIS) is issued. The section on project summaries describe the projects (both foreseeable proposed and ongoing).They provide specific information necessary to analyze the environmental impacts of these projects. Chapter 3 describes which alternative(s) each project supports. Summaries are included for (a) spent nuclear fuel projects, (b) environmental remediation projects, (c) the decontamination and decommissioning of surplus INEL facilities, (d) the construction, upgrade, or replacement of existing waste management facilities, (e) infrastructure projects supporting waste management activities, and (f) research and development projects supporting waste management activities

Research reactor usage at the Idaho National Engineering Laboratory in support of university research and education

International Nuclear Information System (INIS)

Woodall, D.M.; Dolan, T.J.; Stephens, A.G.

1990-01-01

The Idaho National Engineering Laboratory is a US Department of Energy laboratory which has a substantial history of research and development in nuclear reactor technologies. There are a number of available nuclear reactor facilities which have been incorporated into the research and training needs of university nuclear engineering programs. This paper addresses the utilization of the Advanced Reactivity Measurement Facility (ARMF) and the Coupled Fast Reactivity Measurement Facility (CFRMF) for thesis and dissertation research in the PhD program in Nuclear Science and Engineering by the University of Idaho and Idaho State University. Other reactors at the INEL are also being used by various members of the academic community for thesis and dissertation research, as well as for research to advance the state of knowledge in innovative nuclear technologies, with the EBR-II facility playing an essential role in liquid metal breeder reactor research. 3 refs

Environmental considerations associated with siting, constructing, and operating a special isotope separation plant at INEL: Volume 1, Proceedings: Report of public hearings

International Nuclear Information System (INIS)

1987-03-01

This report documents the two public hearings conducted for the purpose of determining the scope of issues to be addressed in relation to the siting, constructing, and operating of a special isotope separation plant at INEL. The report includes transcripts of the public hearings held in Idaho Falls, Idaho, February 24, 1987, and in Boise, Idaho, February 26, 1987, and includes the exhibits of records relating to those hearings. The review and hearing process meets pertinent National Environmental Policy Act (NEPA) requirements, Council on Environmental Quality (CEQ) regulations, and DOE guidelines

Environmental considerations associated with siting, constructing, and operating a special isotope separation plant at INEL: Volume 2, Proceedings: Report of public hearings

International Nuclear Information System (INIS)

1987-03-01

This report documents the two public hearings conducted for the purpose of determining the scope of issues to be addressed in relation to the siting, constructing, and operating of a special isotope separation plant at INEL. The report includes transcripts of the public hearings held in Idaho Falls, Idaho, February 24, 1987, and in Boise, Idaho, February 26, 1987, and includes the exhibits of record relating to those hearings. The review and hearing process meets pertinent National Environmental Policy Act (NEPA) requirements, Council on Environmental Quality (CEQ) regulations, and DOE guidelines

Environmental Restoration and Waste Management Site-Specific Plan for Fiscal Year 1993

Energy Technology Data Exchange (ETDEWEB)

1993-03-01

The Idaho National Engineering Laboratory (INEL) is a US Department of Energy (DOE) multiprogram laboratory whose primary mission has been to research nuclear technologies. Working with these technologies and conducting other types of research generates waste, including radioactive and/or hazardous wastes. While most of the waste treatment, storage, and disposal practices have been effective, some practices have led to the release of contaminants to the environment. As a result, DOE has developed (1) an Environmental Restoration (ER) Program to identify and, where necessary, cleanup releases from inactive waste sites and (2) a Waste Management (WM) Program to safely treat, store, and dispose of DOE wastes generated from current and future activities in an environmentally sound manner. This document describes the plans for FY 1993 for the INEL`s ER and WM programs as managed by DOE`s Idaho Field Office (DOE-ID).

Initial tests on in situ vitrification using electrode feeding techniques

International Nuclear Information System (INIS)

Farnsworth, R.K.; Oma, K.H.; Bigelow, C.E.

1990-05-01

This report summarizes the results of an engineering-scale in situ vitrification (ISV) test conducted to demonstrate the potential for electrode feeding in soils with a high concentration of metals. The engineering-scale test was part of a Pacific Northwest Laboratory (PNL) program to assist Idaho National Engineering Laboratory (INEL) in conducting treatability studies of the potential for applying ISV to the mixed transuranic waste buried at the INEL subsurface disposal area. The purpose of this test was to evaluate the effectiveness of both gravity fed and operator-controlled electrode feeding in reducing or eliminating many of the potential problems associated with fixed-electrode processing of soils with high concentrations of metal. Actual site soils from INEL were mixed with representative concentrations of carbon steel and stainless steel for this engineering-scale test. 18 refs., 14 figs., 3 tabs

Deployment of Remotely-Accessible Robotics Laboratory

Directory of Open Access Journals (Sweden)

Richard Balogh

2012-03-01

Full Text Available Robotnacka is an autonomous drawing mobile robot, designed for eaching beginners in the Logo programming language. It can also be used as an experimental platform, in our case in a remotely accessible robotic laboratory with the possibility to control the robots via the Internet. In addition to a basic version of the robot a version equipped with a gripper is available too, one with a wireless camera, and one with additional ultrasonic distance sensors. The laboratory is available on-line permanently and provides a simple way to incorporate robotics in teaching mathematics, programming and other subjects. The laboratory has been in use several years. We provide description of its functionality and summarize our experience.

Radioactive Waste Management Information for 1992 and record-to-date

International Nuclear Information System (INIS)

Litteer, D.L.; Randall, V.C.; Sims, A.M.; Taylor, K.A.

1993-07-01

This document provides detailed data and graphics on air borne and liquid effluent releases, fuel oil and coal consumption, water usage, and hazardous and mixed waste generated for calendar year 1992. This report summarizes industrial waste data records compiled since 1971 for the Idaho National Engineering Laboratory (INEL). The data presented are from the INEL Nonradiological Waste Management Information System

Core Activities Program. TMI-2 Core Receipt and Storage Project Plan

International Nuclear Information System (INIS)

Ayers, A.L. Jr.

1984-12-01

The TMI-2 Core Receipt and Storage Project is funded by the US Department of Energy and managed by the Technical Support Branch of EG and G Idaho, Inc. at the Idaho National Engineering Laboratory (INEL). As part of the Core Activities Program, this project will include: (a) preparations for receipt and storage of the Three Mile Island Unit 2 core debris at INEL; and (b) receipt and storage operations. This document outlines procedures; project management; safety, environment, and quality; safeguards and security; deliverables; and cost and schedule for the receipt and storage activities at INEL

Cost Quality Management Assessment for the Idaho Operations Office. Final report

International Nuclear Information System (INIS)

1995-06-01

The Office of Engineering and Cost Management (EM-24) conducted a Cost Quality Management Assessment of EM-30 and EM-40 activities at the Idaho National Engineering Laboratory on Feb. 3--19, 1992 (Round I). The CQMA team assessed the cost and cost-related management activities at INEL. The Round II CQMA, conducted at INEL Sept. 19--29, 1994, reviewed EM-30, EM-40, EM-50, and EM-60 cost and cost-related management practices against performance objectives and criteria. Round II did not address indirect cost analysis. INEL has made measurable progress since Round I

Damping values for nuclear power plant piping during seismic events and fluid-induced transients

International Nuclear Information System (INIS)

Ware, A.G.

1986-01-01

For several years the Idaho National Engineering Laboratory (INEL) has been assisting the United States Nuclear Regulatory Commission (USNRC) in efforts to establish best-estimate damping values for use in the dynamic analysis of nuclear power plant piping systems. Data from a number of piping vibration tests conducted at facilities worldwide (including the INEL) have been collected, evaluated, reported, and placed in a nuclear piping data bank at the INEL. These data are being used to justify changes in allowable damping values for use in nuclear piping design, thus making piping systems safer, less costly, and easier to inspect and maintain

Supplement analysis of transuranic waste characterization and repackaging activities at the Idaho National Engineering Laboratory in support of the Waste Isolation Pilot Plant test program

International Nuclear Information System (INIS)

1991-03-01

This supplement analysis has been prepared to describe new information relevant to waste retrieval, handling, and characterization at the Idaho National Engineering Laboratory (INEL) and to evaluate the need for additional documentation to satisfy the National Environmental Policy Act (NEPA). The INEL proposes to characterize and repackage contact-handled transuranic waste to support the Waste Isolation Pilot Plant (WIPP) Test Phase. Waste retrieval, handling and processing activities in support of test phase activities at the WIPP were addressed in the Supplemental Environmental Impact Statement (SEIS) for the WIPP. To ensure that test-phase wastes are properly characterized and packaged, waste containers would be retrieved, nondestructively examined, and transported from the Radioactive Waste Management Complex (RWMC) to the Hot-Fuel Examination Facility for headspace gas analysis, visual inspections to verify content code, and waste acceptance criteria compliance, then repackaging into WIPP experimental test bins or returned to drums. Following repackaging the characterized wastes would be returned to the RWMC. Waste characterization would help DOE determine WIPP compliance with US Environmental Protection Agency regulations governing disposal of transuranic waste and hazardous waste. Additionally, this program supports onsite compliance with Resource Conservation and Recovery Act (RCRA) requirements, compliance with the terms of the No-Migration Variance at WIPP, and provides data to support future waste shipments to WIPP. This analysis will help DOE determine whether there have been substantial changes made to the proposed action at the INEL, or if preparation of a supplement to the WIPP Final Environmental Impact Statement (DOE, 1980) and SEIS (DOE, 1990a) is required. This analysis is based on current information and includes details not available to the SEIS

Preparations to load, transport, receive, and store the damaged TMI-2 [Three Mile Island] reactor core

International Nuclear Information System (INIS)

Reno, H.W.; Schmitt, R.C.; Quinn, G.J.; Ayers, A.L. Jr.; Lilburn, B.J. Jr.; Uhl, D.L.

1986-03-01

The March 1979 incident at the Three Mile Island Nuclear Power Station (TMI) which damaged the core of the Unit 2 reactor resulted in numerous scientific and technical challenges. Some of those challenges involve removing, packaging, and transporting the core debris to the Idaho National Engineering Laboratory (INEL) for storage, examination, and preparation for final disposal. This paper highlights preparations for transporting the core debris from TMI to INEL and receiving and storing that material at INEL. Issues discussed include interfacing of equipment and facilities at TMI, loading operations, transportation activities using a newly designed cask, receiving and storing operations at INEL, and criticality control during storage. Key to the transportation effort was designing, testing, fabricating, and licensing two rail casks which individually provide double containment of the damaged fuel. 27 figs

Environmental and other evaluations of alternatives for management of defense transuranic waste at the Idaho National Engineering Laboratory. Volume 1 of 2

International Nuclear Information System (INIS)

1982-04-01

The US Department of Energy (DOE) is responsible for developing and implementing methods for the safe and environmentally acceptable disposal of radioactive wastes. In connection with this responsibility, the DOE is formulating a program for the long-term management of transuranic (TRU) waste buried and stored at the Idaho National Engineering Laboratory (INEL). This report has been prepared to document the results of environmental and other evaluations for three decisions that the DOE is considering: (1) the selection of a general method for the long-term management of the buried TRU waste; (2) the selection of a method for processing the stored waste and for processing the buried waste, if it is retrieved; (3) the selection of a location for the waste-processing facility. This document pertains only to the contact-handled TRU waste buried in pits and trenches and the contact-handled TRU waste held in aboveground storage at the INEL. A decision has previously been made on a method for the long-term management of the stored waste; it will be retrieved and shipped to the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. The WIPP is also used in this report as a reference repository for evaluation purposes for the buried waste. This report is contained in two volumes. Volume I is arranged as follows: the summary is an overview of the analyses contained in this document. Section 1 is a statement of the underlying purpose and need to which the report is responding. Section 2 describes the alterntives. Section 3 describes the affected environment at the INEL and the WIPP sites. Section 4 analyzes the environmental effects of each alternative. The appendices in Volume II contain data and discussions supporting the material presented in Volume I

Status report

International Nuclear Information System (INIS)

Parsons, D.K.; Nigg, D.W.; Yoon, W.Y.

1987-01-01

This paper reports that as part of project to d develop a package of reactor physics codes for Personal Computers (PCs), the Idaho National Engineering Laboratory (INEL) is developing microcomputer versions of two reactor shielding codes that previously were available for mainframe computers only: QAD-CG and ANISN. QAD-CG is a point kernel code for gamma ray shielding calculations that is similar to MICROSHIELD. ANISN is a well known one-dimensional discrete ordinates transport theory code for reactor design, criticality, and shielding. Of the two, QAD-CG is most frequently used for gamma shielding calculations, while ANISN is better suited for calculations involving neutrons and/or gammas when scattering needs to be treated more accurately

CPP-603 Underwater Fuel Storage Facility Site Integrated Stabilization Management Plan (SISMP), Volume I

International Nuclear Information System (INIS)

Denney, R.D.

1995-10-01

The CPP-603 Underwater Fuel Storage Facility (UFSF) Site Integrated Stabilization Management Plan (SISMP) has been constructed to describe the activities required for the relocation of spent nuclear fuel (SNF) from the CPP-603 facility. These activities are the only Idaho National Engineering Laboratory (INEL) actions identified in the Implementation Plan developed to meet the requirements of the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 94-1 to the Secretary of Energy regarding an improved schedule for remediation in the Defense Nuclear Facilities Complex. As described in the DNFSB Recommendation 94-1 Implementation Plan, issued February 28, 1995, an INEL Spent Nuclear Fuel Management Plan is currently under development to direct the placement of SNF currently in existing INEL facilities into interim storage, and to address the coordination of intrasite SNF movements with new receipts and intersite transfers that were identified in the DOE SNF Programmatic and INEL Environmental Restoration and Waste Management Environmental Impact Statement Record, of Decision. This SISMP will be a subset of the INEL Spent Nuclear Fuel Management Plan and the activities described are being coordinated with other INEL SNF management activities. The CPP-603 relocation activities have been assigned a high priority so that established milestones will be meet, but there will be some cases where other activities will take precedence in utilization of available resources. The Draft INEL Site Integrated Stabilization Management Plan (SISMP), INEL-94/0279, Draft Rev. 2, dated March 10, 1995, is being superseded by the INEL Spent Nuclear Fuel Management Plan and this CPP-603 specific SISMP

Preliminary delineation of natural geochemical reactions, Snake River Plain aquifer system, Idaho National Engineering Laboratory and vicinity, Idaho

International Nuclear Information System (INIS)

Knobel, L.L.; Bartholomay, R.C.; Orr, B.R.

1997-05-01

The U.S. Geological Survey, in cooperation with the U.S. Department of Energy, is conducting a study to determine the natural geochemistry of the Snake River Plain aquifer system at the Idaho National Engineering Laboratory (INEL), Idaho. As part of this study, a group of geochemical reactions that partially control the natural chemistry of ground water at the INEL were identified. Mineralogy of the aquifer matrix was determined using X-ray diffraction and thin-section analysis and theoretical stabilities of the minerals were used to identify potential solid-phase reactants and products of the reactions. The reactants and products that have an important contribution to the natural geochemistry include labradorite, olivine, pyroxene, smectite, calcite, ferric oxyhydroxide, and several silica phases. To further identify the reactions, analyses of 22 representative water samples from sites tapping the Snake River Plain aquifer system were used to determine the thermodynamic condition of the ground water relative to the minerals in the framework of the aquifer system. Principal reactions modifying the natural geochemical system include congruent dissolution of olivine, diopside, amorphous silica, and anhydrite; incongruent dissolution of labradorite with calcium montmorillonite as a residual product; precipitation of calcite and ferric oxyhydroxide; and oxidation of ferrous iron to ferric iron. Cation exchange reactions retard the downward movement of heavy, multivalent waste constituents where infiltration ponds are used for waste disposal

Fusion Safety Program annual report, fiscal year 1992

International Nuclear Information System (INIS)

Holland, D.F.; Cadwallader, L.C.; Herring, J.S.; Longhurst, G.R.; McCarthy, K.A.; Merrill, B.J.; Piet, S.J.

1993-01-01

This report summarizes the major activities of the Fusion Safety Program in fiscal year 1992. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory and EG ampersand G Idaho, Inc. is the prime contractor for this program. The Fusion Safety Program was initiated in 1979. Activities are conducted at the INEL and in participating organizations including the Westinghouse Hanford Company at the Hanford Engineering Development Laboratory, the Massachusetts Institute of Technology, and the University of Wisconsin. The technical areas covered in the report include tritium safety, activation product release, reactions involving beryllium, reactions involving lithium breeding materials, safety of fusion magnet systems, plasma disruptions, risk assessment failure rate data base, and computer code development for reactor transients. Also included in the report is a summary of the safety and environmental studies performed by the INEL for the Tokamak Physics Experiments and the Tokamak Fusion Test Reactor, the safety analysis for the International Thermonuclear Experimental Reactor design, and the technical support for the ARIES commercial reactor design study

Fusion Safety Program annual report: Fiscal year 1987

International Nuclear Information System (INIS)

Holland, D.F.; Herring, J.S.; Longhurst, G.R.; Lyon, R.E.; Merrill, B.J.; Piet, S.J.

1988-02-01

This report summarizes the Fusion Safety Program major activities in fiscal year 1987. The Idaho National Engineering Laboratory (INEL) is the designated lead laboraotry and EG and G Idaho, Inc., is the prime contractor for this program, which was initiated in 1979. Activities are conducted at the INEL and in participating laboratories including the Hanford Engineering Development Laboratory (HEDL), the Massachusetts Institute of Technology (MIT), and the University of Wisconsin. The technical areas covered in the report include tritium safety, activation product release, reactions involving lithium breeding materials, safety of fusion magnet systems, plasma disruptions, risk assessment methodology, computer codes development for reactor transients, and fusion waste management. Also included in the report is a summary of the safety and environmental analysis and conventional facilities design performed by INEL for the Compact Ignition Tokamak design project, the safety analysis and documentation performed for the Tokamak Ignition/Burn Experimental Reactor design, and the technical support provided to the Environmental Safety and Economics Committee (ESECOM). 42 refs., 17 figs., 4 tabs

In situ vitrification program at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Loehr, C.A.; Merrill, S.K.

1991-01-01

A program to demonstrate the viability of in situ vitrification (ISV) technology in remediating a buried mixed transuranic (TRU) waste site is under way at the Idaho National Engineering Laboratory (INEL). The application of the technology to buried waste is being evaluated as part of a Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) feasibility study. The ISV thermal treatment process converts contaminated soil into a chemically inert and stable glass and crystalline product. The process uses joule heating, accomplished by applying electric potential to electrodes that are placed in the soil to initiate and maintain soil melting. Organic contaminants in the soil are destroyed or removed while inorganic contaminants, including radionuclides, are incorporated into the stable, glass-like product or volatilized. Off-gases are collected in a confinement hood over the melt area and processed through an off-gas treatment system. The paper illustrates and describes the ISV process

Report on the participation of US laboratories in the work of the IAEA coordinated research program on the measurement and evaluation of transactinium isotope nuclear decay data

International Nuclear Information System (INIS)

Reich, C.W.

1984-01-01

In this report, we summarize the current status of the work being carried out in various US laboratories that is specifically oriented toward the objectives of this IAEA CRP. Reported below are the gamma-ray emission probability measurements, and related work, at INEL and α-particle related work being conducted by I. Ahmad at ANL. The results of the work of the US Half-Life Evaluation Committee on the half-lives of 234 240 241 Pu have now all been published; and no additional information regarding this activity is included in this report

Assessment of radionuclide databases in CAP88 mainframe version 1.0 and Windows-based version 3.0.

Science.gov (United States)

LaBone, Elizabeth D; Farfán, Eduardo B; Lee, Patricia L; Jannik, G Timothy; Donnelly, Elizabeth H; Foley, Trevor Q

2009-09-01

In this study the radionuclide databases for two versions of the Clean Air Act Assessment Package-1988 (CAP88) computer model were assessed in detail. CAP88 estimates radiation dose and the risk of health effects to human populations from radionuclide emissions to air. This program is used by several U.S. Department of Energy (DOE) facilities to comply with National Emission Standards for Hazardous Air Pollutants regulations. CAP88 Mainframe, referred to as version 1.0 on the U.S. Environmental Protection Agency Web site (http://www.epa.gov/radiation/assessment/CAP88/), was the very first CAP88 version released in 1988. Some DOE facilities including the Savannah River Site still employ this version (1.0) while others use the more user-friendly personal computer Windows-based version 3.0 released in December 2007. Version 1.0 uses the program RADRISK based on International Commission on Radiological Protection Publication 30 as its radionuclide database. Version 3.0 uses half-life, dose, and risk factor values based on Federal Guidance Report 13. Differences in these values could cause different results for the same input exposure data (same scenario), depending on which version of CAP88 is used. Consequently, the differences between the two versions are being assessed in detail at Savannah River National Laboratory. The version 1.0 and 3.0 database files contain 496 and 838 radionuclides, respectively, and though one would expect the newer version to include all the 496 radionuclides, 35 radionuclides are listed in version 1.0 that are not included in version 3.0. The majority of these has either extremely short or long half-lives or is no longer in production; however, some of the short-lived radionuclides might produce progeny of great interest at DOE sites. In addition, 122 radionuclides were found to have different half-lives in the two versions, with 21 over 3 percent different and 12 over 10 percent different.

Cost estimate of grouting the proposed test pits at Idaho National Engineering Laboratory using the ORNL-recommended grouts

International Nuclear Information System (INIS)

Spence, R.D.

1987-08-01

EG and G Idaho will construct three experimental pits to simulate the TRU waste trenches at Idaho National Engineering Laboratory (INEL). Two of these pits will be grouted and then one will be destructively examined as soon as the grout cures and the other will be monitored for 10 years. Oak Ridge National Laboratory (ORNL) is evaluating grouts and will recommend a grout to EG and G Idaho to reduce the permeability of the pit, fill the large voids, and encapsulate the waste. A previous ORNL report (ORNL/TM-9881) discusses the grouts evaluated and the grout recommended based on those evaluations. This report evaluates the economics of grouting the experimental pits. The cost of double grouting two of the EG and G Idaho design pits at the Idaho National Engineering Laboratory using lance injection was estimated to be $100,000. Jet grouting the same two pits was estimated to cost $85,000. Both should be tried as part of the test EG and G Idaho is conducting

Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Draft Environmental Impact Statement. Volume 2, Part B

Energy Technology Data Exchange (ETDEWEB)

1994-06-01

Two types of projects in the spent nuclear fuel and environmental restoration and waste management activities at the Idaho National Engineering Laboratory (INEL) are described. These are: foreseeable proposed projects where some funding for preliminary planning and/or conceptual design may already be authorized, but detailed design or planning will not begin until the Department of Energy (DOE) has determined that the requirements of the National Environmental Policy Act process for the project have been completed; planned or ongoing projects not yet completed but whose National Environmental Policy Act documentation is already completed or is expected to be completed before the Record of Decision for this Envirorunental Impact Statement (EIS) is issued. The section on project summaries describe the projects (both foreseeable proposed and ongoing).They provide specific information necessary to analyze the environmental impacts of these projects. Chapter 3 describes which alternative(s) each project supports. Summaries are included for (a) spent nuclear fuel projects, (b) environmental remediation projects, (c) the decontamination and decommissioning of surplus INEL facilities, (d) the construction, upgrade, or replacement of existing waste management facilities, (e) infrastructure projects supporting waste management activities, and (f) research and development projects supporting waste management activities.

The results of an ecological risk assessment screening at the Idaho National Engineering`s waste area group 2

Energy Technology Data Exchange (ETDEWEB)

VanHorn, R.

1995-11-01

The Idaho National Engineering Laboratory (INEL) is a Department of Energy (DOE) facility located in southeastern Idaho and occupies approximately 890 square miles on the northwestern portion of the eastern Snake River Plain. INEL has been devoted to nuclear energy research and related activities since its establishment in 1949. In the process of fulfilling this mission, wastes were generated, including radioactive and hazardous materials. Most materials were effectively stored or disposed of, however, some release of contaminants to the environment has occurred. For this reason, the INEL was listed by the US environmental Protection Agency on the National Priorities List (NPL), in November, 1989. This report describes the results of an ecological risk assessment performed for the Waste Area Groups 2 (WAG 2) at the INEL. It also summarizes the performance of screening level ecological risk assessments (SLERA).

The results of an ecological risk assessment screening at the Idaho National Engineering's waste area group 2

International Nuclear Information System (INIS)

VanHorn, R.

1995-01-01

The Idaho National Engineering Laboratory (INEL) is a Department of Energy (DOE) facility located in southeastern Idaho and occupies approximately 890 square miles on the northwestern portion of the eastern Snake River Plain. INEL has been devoted to nuclear energy research and related activities since its establishment in 1949. In the process of fulfilling this mission, wastes were generated, including radioactive and hazardous materials. Most materials were effectively stored or disposed of, however, some release of contaminants to the environment has occurred. For this reason, the INEL was listed by the US environmental Protection Agency on the National Priorities List (NPL), in November, 1989. This report describes the results of an ecological risk assessment performed for the Waste Area Groups 2 (WAG 2) at the INEL. It also summarizes the performance of screening level ecological risk assessments (SLERA)

Hot Fuel Examination Facility/South

Energy Technology Data Exchange (ETDEWEB)

1990-05-01

This document describes the potential environmental impacts associated with proposed modifications to the Hot Fuel Examination Facility/South (HFEF/S). The proposed action, to modify the existing HFEF/S at the Argonne National Laboratory-West (ANL-W) on the Idaho National Engineering Laboratory (INEL) in southeastern Idaho, would allow important aspects of the Integral Fast Reactor (IFR) concept, offering potential advantages in nuclear safety and economics, to be demonstrated. It would support fuel cycle experiments and would supply fresh fuel to the Experimental Breeder Reactor-II (EBR-II) at the INEL. 35 refs., 12 figs., 13 tabs.

Hot Fuel Examination Facility/South

International Nuclear Information System (INIS)

1990-05-01

This document describes the potential environmental impacts associated with proposed modifications to the Hot Fuel Examination Facility/South (HFEF/S). The proposed action, to modify the existing HFEF/S at the Argonne National Laboratory-West (ANL-W) on the Idaho National Engineering Laboratory (INEL) in southeastern Idaho, would allow important aspects of the Integral Fast Reactor (IFR) concept, offering potential advantages in nuclear safety and economics, to be demonstrated. It would support fuel cycle experiments and would supply fresh fuel to the Experimental Breeder Reactor-II (EBR-II) at the INEL. 35 refs., 12 figs., 13 tabs

Analysis of the low-level waste radionuclide inventory for the Radioactive Waste Management Complex performance assessment

Energy Technology Data Exchange (ETDEWEB)

Plansky, L.E.; Hoiland, S.A.

1992-02-01

This report summarizes the results of a study to improve the estimates of the radionuclides in the low-level radioactive waste (LLW) inventory which is buried in the Idaho National Engineering Laboratory (INEL) Radioactive Waste Management Complex (RWMC) Subsurface Disposal Area (SDA). The work is done to support the RWMC draft performance assessment (PA). Improved radionuclide inventory estimates are provided for the INEL LLW generators. Engineering, environmental assessment or other research areas may find use for the information in this report. It may also serve as a LLW inventory baseline for data quality assurance. The individual INEL LLW generators, their history and their activities are also described in detail.

Analysis of the low-level waste radionuclide inventory for the Radioactive Waste Management Complex performance assessment

International Nuclear Information System (INIS)

Plansky, L.E.; Hoiland, S.A.

1992-02-01

This report summarizes the results of a study to improve the estimates of the radionuclides in the low-level radioactive waste (LLW) inventory which is buried in the Idaho National Engineering Laboratory (INEL) Radioactive Waste Management Complex (RWMC) Subsurface Disposal Area (SDA). The work is done to support the RWMC draft performance assessment (PA). Improved radionuclide inventory estimates are provided for the INEL LLW generators. Engineering, environmental assessment or other research areas may find use for the information in this report. It may also serve as a LLW inventory baseline for data quality assurance. The individual INEL LLW generators, their history and their activities are also described in detail

Development of on-site accident criteria for waste transfer casks

International Nuclear Information System (INIS)

Uldrich, E.D.

1989-01-01

Removal of radioactive waste must withstand the scrutiny of the public and various regulatory offices. Currently, there is no standard accident criteria or methodology for intra-site shipments at the Idaho National Engineering Laboratory (INEL). Since the radioactive waste transfer casks only carry material within the INEL site boundaries and are not used for normal over-the-road transport, the requirements of 10 CFR 71 Packaging and Transportation of Radioactive Material, do not provide suitable requirements for cask design or safety analyses. The objective is to develop realistically conservative accident scenarios consistent with the limited uses at the INEL for which the cask is approved

Expansion of the Idaho National Engineering Laboratory Research Center: Environmental assessment

International Nuclear Information System (INIS)

1994-03-01

The US Department of Energy (DOE) proposes to expand and upgrade facilities at the Idaho National Engineering Laboratory (INEL) Research Center (IRC) by constructing a research laboratory addition on the northeast corner of existing laboratory building; upgrading the fume hood system in the existing laboratory building; and constructing a hazardous waste handling facility and a chemical storage building. The DOE also proposes to expand the capabilities of biotechnology research programs by increasing use of radiolabeled compounds to levels in excess of current facility limits for three radionuclides (carbon-14, sulfur-35, and phosphorus-32). This Environmental assessment identifies the need for the new facilities, describes the proposed projects and environmental setting, and evaluates the potential environmental effects. Impacts associated with current operation are discussed and established as a baseline. Impacts associated with the proposed action and cumulative impacts are described against this background. Alternatives to the proposed action (No action; Locating proposed facilities at a different site) are discussed and a list of applicable regulations is provided. The no action alternative is continuation of existing operations at existing levels as described in Section 4 of this EA. Proposed facilities could be constructed at a different location, but these facilities would not be useful or practical since they are needed to provide a support function for IRC operations. Further, the potential environmental impacts would not be reduced if a different site was selected

Stored Transuranic Waste Management Program at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Clements, T.L.

1996-01-01

Since 1970, INEL has provided interim storage capacity for transuranic (TRU)-contaminated wastes generated by activities supporting US national defense needs. About 60% of the nation's current inventory of TRU-contaminated waste is stored at INEL, awaiting opening of the Waste Isolation Pilot Plant (WIPP), the designated federal repository. A number of activities are currently underway for enhancing current management capabilities, conducting projects that support local and national TRU management activities, and preparing for production-level waste retrieval, characterization, examination, certification, and shipment of untreated TRU waste to WIPP in April 1998. Implementation of treatment capability is planned in 2003 to achieve disposal of all stored TRU-contaminated waste by a target date of December 31, 2015, but no later than December 31, 2018

Melter development needs assessment for RWMC buried wastes

International Nuclear Information System (INIS)

Donaldson, A.D.; Carpenedo, R.J.; Anderson, G.L.

1992-02-01

This report presents a survey and initial assessment of the existing state-of-the-art melter technology necessary to thermally treat (stabilize) buried TRU waste, by producing a highly leach resistant glass/ceramic waste form suitable for final disposal. Buried mixed transuranic (TRU) waste at the Idaho National Engineering Laboratory (INEL) represents an environmental hazard requiring remediation. The Environmental Protection Agency (EPA) placed the INEL on the National Priorities List in 1989. Remediation of the buried TRU-contaminated waste via the CERCLA decision process is required to remove INEL from the National Priorities List. A Waste Technology Development (WTD) Preliminary Systems Design and Thermal Technologies Screening Study identified joule-heated and plasma-heated melters as the most probable thermal systems technologies capable of melting the INEL soil and waste to produce the desired final waste form [Iron-Enriched Basalt (IEB) glass/ceramic]. The work reported herein then surveys the state of existing melter technology and assesses it within the context of processing INEL buried TRU wastes and contaminated soils. Necessary technology development work is recommended

Thermal-Hydraulic Experiment Facility (THEF)

International Nuclear Information System (INIS)

Martinell, J.S.

1982-01-01

This paper provides an overview of the Thermal-Hydraulic Experiment Facility (THEF) at the Idaho National Engineering Laboratory (INEL). The overview describes the major test systems, measurements, and data acquisition system, and presents objectives, facility configuration, and results for major experimental projects recently conducted at the THEF. Plans for future projects are also discussed. The THEF is located in the Water Reactor Research Test Facility (WRRTF) area at the INEL

TRAC development at General Electric

International Nuclear Information System (INIS)

Andersen, J.G.M.; Shaug, J.C.; Shiralkar, B.S.

1987-01-01

TRAC is a computer code for transient analysis of light water reactors. The BWR version of TRAC has been developed as a result of a close cooperation between General Electric Company and Idaho National Engineering Laboratory. Up through 1985 the development work at General Electric was jointly funded by General Electric, the Nuclear Regulatory Commission and Electric Power Research Institute under the Refill-Reflood and FIST programs. At INEL (which has the main responsibility for the NRC version of TRAC-BWR) this work has led to the development of TRACBD1 and TRACBF1, while at GE, TRACB04 was the final product of the Refill-Reflood and FIST programs. TRAC development has continued at General Electric after the completion of these programs with the evolution of the TRACG code. The purpose of the paper is to describe this work. The TRAC development at General Electric can be divided into two main categories: extended benchmark capability and improved user convenience

Structural analysis of hatch cover plates on Fuels and Materials Examination Facility high bay mezzanine

International Nuclear Information System (INIS)

Dixson, G.E.

1997-01-01

In order to move the Idaho National Engineering Laboratory (INEL) Light Duty Utility Arm (LDUA) trailer into position for testing on the Fuels and Materials Examination Facility (FMEF) 42 ft level mezzanine one of the trailer's wheels will have to sit on a circular hatch cover fabricated from one-inch thick steel plate. The attached calculations verify that the hatch cover plate is strong enough to support the weight of the INEL LDUA trailer's wheel

Preparations to receive and store the TMI-2 core debris

International Nuclear Information System (INIS)

Ayers, A.L.R. Jr.; Lilburn, B.J. Jr.

1986-01-01

The March 1979 accident at Unit 2 of Three Mile Island Nuclear Power Station (TMI-2) resulted in considerable damage to the core of the reactor. The core debris will be packaged in canisters and transported by rail cask to the Idaho National Engineering Laboratory (INEL) for storage, examination, and preparation for final disposal. A significant part of recovering from the TMI-2 accident involves receiving and storing the TMI-2 core debris canisters at INEL. This paper highlights preparations for receiving the rail cask at INEL, unloading canisters from the cask in the Hot Shop of Test Area North Building 607, and storing/monitoring those canisters in the Water Pit for up to 30 years

Nuclear Plant Analyzer development at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Laats, E.T.; Beelman, R.J.; Charlton, T.R.; Hampton, N.L.; Burtt, J.D.

1985-01-01

The Nuclear Plant Analyzer (NPA) is a state-of-the-art safety analysis and engineering tool being used to address key nuclear power plant safety issues. The NPA has been developed to integrate the NRC's computerized reactor behavior simulation codes such as RELAP5, TRAC-BWR, and TRAC-PWR, with well-developed computer graphics programs and large repositories of reactor design and experimental data. An important feature of the NAP is the capability to allow an analyst to redirect a RELAP5 or TRAC calculation as it progresses through its simulated scenario. The analyst can have the same power plant control capabilities as the operator of an actual plant. The NPA resides on the dual CDS Cyber-176 mainframe computers at the INEL and is being converted to operate on a Cray-1S computer at the LANL. The subject of this paper is the program conducted at the INEL

GENII Version 2 Users’ Guide

Energy Technology Data Exchange (ETDEWEB)

Napier, Bruce A.

2004-03-08

The GENII Version 2 computer code was developed for the Environmental Protection Agency (EPA) at Pacific Northwest National Laboratory (PNNL) to incorporate the internal dosimetry models recommended by the International Commission on Radiological Protection (ICRP) and the radiological risk estimating procedures of Federal Guidance Report 13 into updated versions of existing environmental pathway analysis models. The resulting environmental dosimetry computer codes are compiled in the GENII Environmental Dosimetry System. The GENII system was developed to provide a state-of-the-art, technically peer-reviewed, documented set of programs for calculating radiation dose and risk from radionuclides released to the environment. The codes were designed with the flexibility to accommodate input parameters for a wide variety of generic sites. Operation of a new version of the codes, GENII Version 2, is described in this report. Two versions of the GENII Version 2 code system are available, a full-featured version and a version specifically designed for demonstrating compliance with the dose limits specified in 40 CFR 61.93(a), the National Emission Standards for Hazardous Air Pollutants (NESHAPS) for radionuclides. The only differences lie in the limitation of the capabilities of the user to change specific parameters in the NESHAPS version. This report describes the data entry, accomplished via interactive, menu-driven user interfaces. Default exposure and consumption parameters are provided for both the average (population) and maximum individual; however, these may be modified by the user. Source term information may be entered as radionuclide release quantities for transport scenarios, or as basic radionuclide concentrations in environmental media (air, water, soil). For input of basic or derived concentrations, decay of parent radionuclides and ingrowth of radioactive decay products prior to the start of the exposure scenario may be considered. A single code run can

Environmental Molecular Sciences Laboratory Operations System: Version 4.0 - system requirements specification

Energy Technology Data Exchange (ETDEWEB)

Kashporenko, D.

1996-07-01

This document is intended to provide an operations standard for the Environmental Molecular Sciences Laboratory OPerations System (EMSL OPS). It is directed toward three primary audiences: (1) Environmental Molecular Sciences Laboratory (EMSL) facility and operations personnel; (2) laboratory line managers and staff; and (3) researchers, equipment operators, and laboratory users. It is also a statement of system requirements for software developers of EMSL OPS. The need for a finely tuned, superior research environment as provided by the US Department of Energy`s (DOE) Environmental Molecular Sciences Laboratory has never been greater. The abrupt end of the Cold War and the realignment of national priorities caused major US and competing overseas laboratories to reposition themselves in a highly competitive research marketplace. For a new laboratory such as the EMSL, this means coming into existence in a rapidly changing external environment. For any major laboratory, these changes create funding uncertainties and increasing global competition along with concomitant demands for higher standards of research product quality and innovation. While more laboratories are chasing fewer funding dollars, research ideas and proposals, especially for molecular-level research in the materials and biological sciences, are burgeoning. In such an economically constrained atmosphere, reduced costs, improved productivity, and strategic research project portfolio building become essential to establish and maintain any distinct competitive advantage. For EMSL, this environment and these demands require clear operational objectives, specific goals, and a well-crafted strategy. Specific goals will evolve and change with the evolution of the nature and definition of DOE`s environmental research needs. Hence, EMSL OPS is designed to facilitate migration of these changes with ease into every pertinent job function, creating a facile {open_quotes}learning organization.{close_quotes}

Intelligent Mobile Sensor System (IMSS) for drum inspection and monitoring - Volume 3. Final report, October 1, 1993 - April 22, 1995

International Nuclear Information System (INIS)

1995-01-01

This manual is intended to be read by people who will use the IMSS system on a regular basis, who will be referred to as IMSS system operators. Portions of this manual are intended to be read by operations staff who need to understand certain aspects of the IMSS system since their staff will be working near the IMSS vehicle and docking station. Sections 1 through 4 provide general information of interest both to operations staff and IMSS system operators. The remainder of this manual provides information of interest mainly to IMSS system operators. This manual is customized for use of the IMSS system at the DOE Idaho National Engineering Laboratory (INEL), specifically in Buildings 628 through 634 at INEL's Radioactive Waste Management Complex (RWMC). The vast majority of this manual is applicable to any installation site--only a few minor details are specific to INEL. This manual will be complemented by one-on-one training provided to INEL personnel by the IMSS system development team

Software engineering laboratory series: Annotated bibliography of software engineering laboratory literature

Science.gov (United States)

Morusiewicz, Linda; Valett, Jon

1992-01-01

This document is an annotated bibliography of technical papers, documents, and memorandums produced by or related to the Software Engineering Laboratory. More than 100 publications are summarized. These publications cover many areas of software engineering and range from research reports to software documentation. This document has been updated and reorganized substantially since the original version (SEL-82-006, November 1982). All materials have been grouped into eight general subject areas for easy reference: (1) the Software Engineering Laboratory; (2) the Software Engineering Laboratory: Software Development Documents; (3) Software Tools; (4) Software Models; (5) Software Measurement; (6) Technology Evaluations; (7) Ada Technology; and (8) Data Collection. This document contains an index of these publications classified by individual author.

Ohmically heated toroidal experiment (OHTE) mobile ignition test reactor facility concept study

International Nuclear Information System (INIS)

Masson, L.S.; Watts, K.D.; Piscitella, R.R.; Sekot, J.P.; Drexler, R.L.

1983-02-01

This report presents the results of a study to evaluate the use of an existing nuclear test complex at the Idaho National Engineering Laboratory (INEL) for the assembly, testing, and remote maintenance of the ohmically heated toroidal experiment (OHTE) compact reactor. The portable reactor concept is described and its application to OHTE testing and maintenance requirements is developed. Pertinent INEL facilities are described and several test system configurations that apply to these facilities are developed and evaluated

FY-1981 project status for the Transuranic Waste Treatment Facility

International Nuclear Information System (INIS)

Benedetti, R.L.; Tait, T.D.

1981-11-01

The primary objective of the Transuranic Waste Treatment Facility (TWTF) Project is to provide a facility to process low-level transuranic waste stored at the Idaho National Engineering Laboratory (INEL) into a form acceptable for disposal at the Waste Isolation Pilot Plant. This report provides brief summary descriptions of the project objectives and background, project status through FY-1981, planned activities for FY-1982, and the EG and G TWTF Project office position on processing INEL transuranic waste

Preliminary siting criteria for the proposed mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Jorgenson-Waters, M.

1992-09-01

The Mixed and Low-Level Waste Treatment Facility project was established in 1991 by the US Department of Energy Idaho Field Office. This facility will provide treatment capabilities for Idaho National Engineering Laboratory (INEL) low-level mixed waste and low-level waste. This report identifies the siting requirements imposed on facilities that treat and store these waste types by Federal and State regulatory agencies and the US Department of Energy. Site selection criteria based on cost, environmental, health and safety, archeological, geological and service, and support requirements are presented. These criteria will be used to recommend alternative sites for the new facility. The National Environmental Policy Act process will then be invoked to evaluate the alternatives and the alternative sites and make a final site determination

Department of Energy treatment capabilities for greater-than-Class C low-level radioactive waste

International Nuclear Information System (INIS)

Morrell, D.K.; Fischer, D.K.

1995-01-01

This report provides brief profiles for 26 low-level and high-level waste treatment capabilities available at the Idaho National Engineering Laboratory (INEL), Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), Oak Ridge National Laboratory (ORNL), Pacific Northwest Laboratory (PNL), Rocky Flats Plant (RFP), Savannah River Site (SRS), and West Valley Demonstration Plant (WVDP). Six of the treatments have potential use for greater-than-Class C low-level waste (GTCC LLW). They include: (a) the glass ceramic process and (b) the Waste Experimental Reduction Facility incinerator at INEL; (c) the Super Compaction and Repackaging Facility and (d) microwave melting solidification at RFP; (e) the vitrification plant at SRS; and (f) the vitrification plant at WVDP. No individual treatment has the capability to treat all GTCC LLW streams. It is recommended that complete physical and chemical characterizations be performed for each GTCC waste stream, to permit using multiple treatments for GTCC LLW

Site-specific probabilistic seismic hazard analyses for the Idaho National Engineering Laboratory. Volume 2: Appendices

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-05-01

The identification of seismic sources is often based on a combination of geologic and tectonic considerations and patterns of observed seismicity; hence, a historical earthquake catalogue is important. A historical catalogue of earthquakes of approximate magnitude (M) 2.5 and greater for the time period 1850 through 1992 was compiled for the INEL region. The primary data source used was the Decade of North American Geology (DNAG) catalogue for the time period from about 1800 through 1985 (Engdahl and Rinehart, 1988). A large number of felt earthquakes, especially prior to the 1970`s, which were below the threshold of completeness established in the DNAG catalogue (Engdahl and Rinehart, 1991), were taken from the state catalogues compiled by Stover and colleagues at the National Earthquake Information Center (NEIC) and combined with the DNAG catalogue for the INEL region. The state catalogues were those of Idaho, Montana, Nevada, Utah, and Wyoming. NEIC`s Preliminary Determination of Epicenters (PDE) and the state catalogues compiled by the Oregon Department of Geology and Mineral Industries (DOGAMI), and the University of Nevada at Reno (UNR) were also used to supplement the pre-1986 time period. A few events reanalyzed by Jim Zollweg (Boise State University, written communication, 1994) were also modified in the catalogue. In the case of duplicate events, the DNAG entry was preferred over the Stover et al. entry for the period 1850 through 1985. A few events from Berg and Baker (1963) were also added to the catalogue. This information was and will be used in determining the seismic risk of buildings and facilities located at the Idaho National Engineering Laboratory.

Site-specific probabilistic seismic hazard analyses for the Idaho National Engineering Laboratory. Volume 2: Appendices

International Nuclear Information System (INIS)

1996-05-01

The identification of seismic sources is often based on a combination of geologic and tectonic considerations and patterns of observed seismicity; hence, a historical earthquake catalogue is important. A historical catalogue of earthquakes of approximate magnitude (M) 2.5 and greater for the time period 1850 through 1992 was compiled for the INEL region. The primary data source used was the Decade of North American Geology (DNAG) catalogue for the time period from about 1800 through 1985 (Engdahl and Rinehart, 1988). A large number of felt earthquakes, especially prior to the 1970's, which were below the threshold of completeness established in the DNAG catalogue (Engdahl and Rinehart, 1991), were taken from the state catalogues compiled by Stover and colleagues at the National Earthquake Information Center (NEIC) and combined with the DNAG catalogue for the INEL region. The state catalogues were those of Idaho, Montana, Nevada, Utah, and Wyoming. NEIC's Preliminary Determination of Epicenters (PDE) and the state catalogues compiled by the Oregon Department of Geology and Mineral Industries (DOGAMI), and the University of Nevada at Reno (UNR) were also used to supplement the pre-1986 time period. A few events reanalyzed by Jim Zollweg (Boise State University, written communication, 1994) were also modified in the catalogue. In the case of duplicate events, the DNAG entry was preferred over the Stover et al. entry for the period 1850 through 1985. A few events from Berg and Baker (1963) were also added to the catalogue. This information was and will be used in determining the seismic risk of buildings and facilities located at the Idaho National Engineering Laboratory

Development of proposed free release criteria for Idaho National Engineering Laboratory lead

International Nuclear Information System (INIS)

Losinski, S.J.

1994-01-01

The INEL Lead Management Project (LMP) performed an investigation of the origin of lead used as shielding at the INEL and developed radiological profile information that was then used to establish a baseline for the DOE ''no-rad-added'' standard. Primary findings of the investigation include the following: (a) Much of the lead at the INEL was obtained from a DOE lead bank; (b) Lead inventory at the DOE lead bank was derived primarily from recycled sources and was most likely in the form of pure lead; (c) Secondary lead (lead from recycled sources), available in today's market, is expected to have radiological characteristics similar to those of the DOE lead bank; (d) Highly sensitive radiological testing of 20 samples of lead from secondary sources revealed the lead to be radiologically pristine. Beta-, gamma-, and alpha-emitting radionuclide concentrations were all found to be less than detectable, except for a very small quantity of lead-210 (an alpha emitter), which is a naturally occurring isotope of lead. Based on the pristine nature of lead, a proposed free release criterion for lead was developed based on a statistical null hypothesis approach. The free release criterion compares the natural background count of a clean lead standard with the natural background count of a sample. When the sample background count cannot be distinguished as different from the standard background count at the 95% confidence level, then the sample is considered radiologically clean

Idaho National Engineering Laboratory code assessment of the Rocky Flats transuranic waste

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-07-01

This report is an assessment of the content codes associated with transuranic waste shipped from the Rocky Flats Plant in Golden, Colorado, to INEL. The primary objective of this document is to characterize and describe the transuranic wastes shipped to INEL from Rocky Flats by item description code (IDC). This information will aid INEL in determining if the waste meets the waste acceptance criteria (WAC) of the Waste Isolation Pilot Plant (WIPP). The waste covered by this content code assessment was shipped from Rocky Flats between 1985 and 1989. These years coincide with the dates for information available in the Rocky Flats Solid Waste Information Management System (SWIMS). The majority of waste shipped during this time was certified to the existing WIPP WAC. This waste is referred to as precertified waste. Reassessment of these precertified waste containers is necessary because of changes in the WIPP WAC. To accomplish this assessment, the analytical and process knowledge available on the various IDCs used at Rocky Flats were evaluated. Rocky Flats sources for this information include employee interviews, SWIMS, Transuranic Waste Certification Program, Transuranic Waste Inspection Procedure, Backlog Waste Baseline Books, WIPP Experimental Waste Characterization Program (headspace analysis), and other related documents, procedures, and programs. Summaries are provided of: (a) certification information, (b) waste description, (c) generation source, (d) recovery method, (e) waste packaging and handling information, (f) container preparation information, (g) assay information, (h) inspection information, (i) analytical data, and (j) RCRA characterization.

Department of Transportation -- Exemption for using the Transuranic Package Transporter-I (TRUPACT-I) at the Idaho National Engineering Laboratory (Code of Federal Regulations, Title 49, Part 107, Subpart B -- Exemptions, 107-103 Application for Exemption)

International Nuclear Information System (INIS)

Tyacke, M.J.; Macdonald, R.J.

1992-08-01

Exemption from specific regulations is being sought for the Transuranic Package Transporter Model I (TRUPACT-I) container. The design has successfully undergone extensive testing of a quarter-scale model and a full-scale prototype of the container. Results from the analysis and testing are in the TRUPACT-1 Safely Analysis Report for Packaging (SARP), GA-Al8695/SAND 87-7104 (TTC0735), April 1987 (see Attachment 1). The container was never certified or used because of questions raised during the certification process. Two features of the container design failed to satisfy the regulations for Type B packaging. First, the design utilizes a venting system to control internal and external pressures; this venting system is not allowed by the Code of Federal Regulations, Title 10, Parts 71(h) and 71.51(b) [10 CFR 71.(h) and 71.51(b)]. Second, the maximum quantity fissile material proposed to be hauled in TRUPACT-I exceeded the limits in 10 CFR 71.63(b) for a single-containment container. To correct these design deficiencies, the vents would be plugged during transport, and the maximum quantity of fissile material would be limited to the allowables for a single-containment container. An engineering analysis showed that the container could safely transport radioactive material within the boundaries of the Idaho National Engineering Laboratory (INEL) with the vent system plugged (see Attachment 2). However, some of the requirements for determining pressure on a container need to be changed (i.e., exempted) to reflect conditions unique to the INEL. The following are the requirements needing to be changed for INEL conditions, variances being sought, and justifications for the variances

Modeling in situ vitrification

International Nuclear Information System (INIS)

Mecham, D.C.; MacKinnon, R.J.; Murray, P.E.; Johnson, R.W.

1990-01-01

In Situ Vitrification (ISV) process is being assessed by the Idaho National Engineering Laboratory (INEL) to determine its applicability to transuranic and mixed wastes buried at INEL'S Subsurface Disposal Area (SDA). This process uses electrical resistance heating to melt waste and contaminated soil in place to produce a durable glasslike material that encapsulates and immobilizes buried wastes. This paper outlines the requirements for the model being developed at the INEL which will provide analytical support for the ISV technology assessment program. The model includes representations of the electric potential field, thermal transport with melting, gas and particulate release, vapor migration, off-gas combustion and process chemistry. The modeling objectives are to help determine the safety of the process by assessing the air and surrounding soil radionuclides and chemical pollution hazards, the nuclear criticality hazard, and the explosion and fire hazards, help determine the suitability of the ISV process for stabilizing the buried wastes involved, and help design laboratory and field tests and interpret results. 3 refs., 2 figs., 1 tab

Cost-time management for environmental restoration activities at the Department of Energy's Idaho National Engineering Laboratory, Idaho Chemical Processing Plant

International Nuclear Information System (INIS)

Fourr, B.R.; Owen, A.H.; Williamson, D.J.; Nash, C.L.

1992-01-01

Cost-time management methods have been developed by Westinghouse to examine business applications from a cost-time perspective. The initial application of cost-time management within Westinghouse was targeted at reducing cycle time in the manufacturing sector. As a result of the tremendous success of reduced cycle time in manufacturing, Westinghouse initiated application of the management technique to Environmental Restoration activities at its Government Owned Contractor Operated facilities. The Westinghouse initiative was proposed in support of the Department of Energy's goals for cost effective Environmental Restoration activities. This paper describes the application of the cost-time method to Environmental Restoration work currently being performed at the Idaho National Engineering Laboratory (INEL) for the Department of Energy (DOE) by Westinghouse Idaho Nuclear Company (WINCO)

Nuclear power plant simulation using advanced simulation codes through a state-of-the-art workstation

International Nuclear Information System (INIS)

Laats, E.T.; Hagen, R.N.

1985-01-01

The Nuclear Plant Analyzer (NPA) currently resides in a Control Data Corporation 176 mainframe computer at the Idaho National Engineering Laboratory (INEL). The NPA user community is expanding to include worldwide users who cannot consistently access the INEL mainframe computer from their own facilities. Thus, an alternate mechanism is needed to enable their use of the NPA. Therefore, a feasibility study was undertaken by EG and G Idaho to evaluate the possibility of developing a standalone workstation dedicated to the NPA

Data analysis through interactive computer animation method (DATICAM)

International Nuclear Information System (INIS)

Curtis, J.N.; Schwieder, D.H.

1983-01-01

DATICAM is an interactive computer animation method designed to aid in the analysis of nuclear research data. DATICAM was developed at the Idaho National Engineering Laboratory (INEL) by EG and G Idaho, Inc. INEL analysts use DATICAM to produce computer codes that are better able to predict the behavior of nuclear power reactors. In addition to increased code accuracy, DATICAM has saved manpower and computer costs. DATICAM has been generalized to assist in the data analysis of virtually any data-producing dynamic process

Pit 9 project: A private sector initiative

International Nuclear Information System (INIS)

Macdonald, D.W.; Hughes, F.P.; Burton, B.N.

1993-01-01

This report discusses the Pit 9 Comprehensive Demonstration which is intended to demonstrate a cost-effective approach to remediate an Idaho National Engineering Laboratory (INEL) waste disposal pit through a Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Interim Action. The remediation will include additional requirements, if needed, to provide high confidence that only minor additional work would be necessary to accomplish the final closure as part of the overall final closure strategy for the INEL's Subsurface Disposal Area (SDA)

Test plan for FY-91 alpha CAM evaluation

International Nuclear Information System (INIS)

Winberg, M.R.

1991-03-01

This report describes the test plan for evaluating the Merlin Gerin, Inc., Edgar alpha continuous air monitor (CAM) and associated analysis system to be conducted by Idaho National Engineering Laboratory (INEL) for the Department of Energy. INEL has evaluated other commercial alpha CAM systems to detect transuranic contaminants during waste handling and retrieval operations. This test plan outlines experimental methods, sampling methods, sampling and analysis techniques, and equipment needed and safety and quality requirements to test the commercial CAM. 8 refs., 3 figs

Radioactive Waste Management information for 1994 and record-to-date

International Nuclear Information System (INIS)

French, D.L.; Lisee, D.J.; Taylor, K.A.

1995-07-01

This document, Radioactive Waste Management Information for 1994 and Record-To-Date, contains computerized radioactive waste data records from the Idaho National Engineering Laboratory (INEL). Data are compiled from information supplied by the US Department of Energy (DOE) contractors. Data listed are on airborne and liquid radioactive effluents and solid radioactive waste that is stored, disposed, and sent to the INEL for reduction. Data are summarized for the years 1952 through 1993. Data are detailed for the calendar year 1994

Version pressure feedback mechanisms for speculative versioning caches

Science.gov (United States)

Eichenberger, Alexandre E.; Gara, Alan; O& #x27; Brien, Kathryn M.; Ohmacht, Martin; Zhuang, Xiaotong

2013-03-12

Mechanisms are provided for controlling version pressure on a speculative versioning cache. Raw version pressure data is collected based on one or more threads accessing cache lines of the speculative versioning cache. One or more statistical measures of version pressure are generated based on the collected raw version pressure data. A determination is made as to whether one or more modifications to an operation of a data processing system are to be performed based on the one or more statistical measures of version pressure, the one or more modifications affecting version pressure exerted on the speculative versioning cache. An operation of the data processing system is modified based on the one or more determined modifications, in response to a determination that one or more modifications to the operation of the data processing system are to be performed, to affect the version pressure exerted on the speculative versioning cache.

Use of base isolation techniques for the design of high-level waste storage facility enclosure at INEL

International Nuclear Information System (INIS)

Vallenas, J.M.; Wong, Chun K.; Beer, M.J.

1993-08-01

Current Department of Energy criteria for facilities subjected to natural hazards provide guidelines to place facilities or portions of facilities into usage categories. Usage categories are based on characteristics such as mission dependence, type of hazardous materials involved, and performance goals. Seismic requirements are significantly more stringent for facilities falling into higher ''hazard facility use categories''. A special problem arises in cases where a facility or portion of a facility is dependent on another facility of lower ''hazard facility use category'' for support or protection. Creative solutions can minimize the cost Unpact of ensuring that the lower category item does not compromise the performance of the higher category item. In this paper, a base isolation solution is provided for a ''low hazard facility use category'' weather enclosure designed so it will not collapse onto a ''high hazard facility use category'' high level waste storage facility at INEL. This solution is compared to other more conventional procedures. Details, practical limitations, licensing and regulatory considerations, and cost comparisons are provided

Hydrologic testing in wells near the Idaho Chemical Processing Plant at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Johnson, G.S.; Olsen, J.H.; Ralston, D.R.

1994-01-01

The Snake River Plain aquifer beneath the INEL is often viewed as a 2-dimensional system, but may actually possess 3-dimensional properties of concern. A straddle-packer system is being used by the State's INEL Oversight Program to isolate specific aquifer intervals and define the 3-dimensional chemical and hydrologic characteristics of the aquifer. The hydrologic test results from wells USGS 44, 45, and 46 near the Idaho Chemical Processing Plant indicate that: (1) Vertical variation in static head is less than 0.3 feed, (2) barometric efficiencies are between 25 and 55 percent, and (3) the system responds to distant pumping as a multi-layered, but interconnected system. 3 refs., 7 figs., 3 tabs

ADAMS/WT advanced development - version 1.4 and beyond

Energy Technology Data Exchange (ETDEWEB)

Elliott, A.S.; Depauw, T.R. [Mechanical Dynamics, Inc., Mesa, AZ (United States)

1996-12-31

ADAMS/WT is an wind-turbine-specific shell for the general-purpose mechanical system simulation package ADAMS5. It was developed under the guidance of the National Renewable Energy Laboratory to give engineers and analysts in the wind turbine community access to the analytical power of ADAMS, without having to become expert in its particular technology. The 1.4 version of ADAMS/WT is the most recent upgrade to the package, incorporating the most up-to-date version of the AeroDyn aerodynamic forcing subroutines from the University of Utah. It is also the first version to be made available on the Windows/NT platform. In version 1.4, ADAMS/WT has been significantly improved throughout and runs much faster. Automatic generation of standardized output has been added. The documentation has been extensively augmented with more detailed descriptions, more figures and more examples. ADAMS/WT remains the most powerful analytical tool available for horizontal-axis wind turbine development. 10 figs.

Geologic aspects of seismic hazards assessment at the Idaho National Engineering Laboratory, southeastern Idaho

International Nuclear Information System (INIS)

Smith, R.P.; Hackett, W.R.; Rodgers, D.W.

1989-01-01

The Idaho National Engineering Laboratory (INEL), located on the northwestern side of the Eastern Snake River Plain (ESRP), lies in an area influenced by two distinct geologic provinces. The ESRP province is a northeast-trending zone of late Tertiary and Quaternary volcanism which transects the northwest-trending, block-fault mountain ranges of the Basin and Range province. An understanding of the interaction of these two provinces is important for realistic geologic hazards assessment. Of particular importance for seismic hazards analysis is the relationship of volcanic rift zones on the ESRP to basin-and-range faults north of the plain. The Arco Rift Zone, a 20-km-long belt of deformation and volcanism on the plain just west of the INEL, is colinear with the basin-and-range Lost River fault. Recent field studies have demonstrated that Arco Rift Zone deformation is typical of that induced by dike injection in other volcanic rift zones. The deformation is characterized by a predominance of dilational fissuring with less extensive development of faults and grabens. Cumulative vertical displacements over the past 0.6 Ma are an order of magnitude lower than those associated with the Arco Segment of the Lost River fault to the northwest. The evidence suggests that the northeast-directed extension that produces the block fault mountains of the Basin and Range is expressed by dike injection and volcanic rift zone development in the ESRP. Seismicity associated with dike injection during rift zone development is typically of low magnitude and would represent only minor hazard compared to that associated with the block faulting. Since the ESRP responds to extension in a manner distinct from basin-and-range faulting, it is not appropriate to consider the volcanic rift zones as extensions of basin-and-range faults for seismic hazard analysis

Preliminary siting activities for new waste handling facilities at the Idaho National Engineering Laboratory

Energy Technology Data Exchange (ETDEWEB)

Taylor, D.D.; Hoskinson, R.L.; Kingsford, C.O.; Ball, L.W.

1994-09-01

The Idaho Waste Processing Facility, the Mixed and Low-Level Waste Treatment Facility, and the Mixed and Low-Level Waste Disposal Facility are new waste treatment, storage, and disposal facilities that have been proposed at the Idaho National Engineering Laboratory (INEL). A prime consideration in planning for such facilities is the selection of a site. Since spring of 1992, waste management personnel at the INEL have been involved in activities directed to this end. These activities have resulted in the (a) identification of generic siting criteria, considered applicable to either treatment or disposal facilities for the purpose of preliminary site evaluations and comparisons, (b) selection of six candidate locations for siting,and (c) site-specific characterization of candidate sites relative to selected siting criteria. This report describes the information gathered in the above three categories for the six candidate sites. However, a single, preferred site has not yet been identified. Such a determination requires an overall, composite ranking of the candidate sites, which accounts for the fact that the sites under consideration have different advantages and disadvantages, that no single site is superior to all the others in all the siting criteria, and that the criteria should be assigned different weighing factors depending on whether a site is to host a treatment or a disposal facility. Stakeholder input should now be solicited to help guide the final selection. This input will include (a) siting issues not already identified in the siting, work to date, and (b) relative importances of the individual siting criteria. Final site selection will not be completed until stakeholder input (from the State of Idaho, regulatory agencies, the public, etc.) in the above areas has been obtained and a strategy has been developed to make a composite ranking of all candidate sites that accounts for all the siting criteria.

Preliminary siting activities for new waste handling facilities at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Taylor, D.D.; Hoskinson, R.L.; Kingsford, C.O.; Ball, L.W.

1994-09-01

The Idaho Waste Processing Facility, the Mixed and Low-Level Waste Treatment Facility, and the Mixed and Low-Level Waste Disposal Facility are new waste treatment, storage, and disposal facilities that have been proposed at the Idaho National Engineering Laboratory (INEL). A prime consideration in planning for such facilities is the selection of a site. Since spring of 1992, waste management personnel at the INEL have been involved in activities directed to this end. These activities have resulted in the (a) identification of generic siting criteria, considered applicable to either treatment or disposal facilities for the purpose of preliminary site evaluations and comparisons, (b) selection of six candidate locations for siting,and (c) site-specific characterization of candidate sites relative to selected siting criteria. This report describes the information gathered in the above three categories for the six candidate sites. However, a single, preferred site has not yet been identified. Such a determination requires an overall, composite ranking of the candidate sites, which accounts for the fact that the sites under consideration have different advantages and disadvantages, that no single site is superior to all the others in all the siting criteria, and that the criteria should be assigned different weighing factors depending on whether a site is to host a treatment or a disposal facility. Stakeholder input should now be solicited to help guide the final selection. This input will include (a) siting issues not already identified in the siting, work to date, and (b) relative importances of the individual siting criteria. Final site selection will not be completed until stakeholder input (from the State of Idaho, regulatory agencies, the public, etc.) in the above areas has been obtained and a strategy has been developed to make a composite ranking of all candidate sites that accounts for all the siting criteria

Cost-time management for environmental restoration activities at the Department of Energy`s Idaho National Engineering Laboratory, Idaho Chemical Processing Plant

Energy Technology Data Exchange (ETDEWEB)

Fourr, B.R.; Owen, A.H.; Williamson, D.J. [Westinghouse Idaho Nuclear Co., Inc., Idaho Falls, ID (United States); Nash, C.L. [USDOE Idaho Field Office, Idaho Falls, ID (United States)

1992-05-22

Cost-time management methods have been developed by Westinghouse to examine business applications from a cost-time perspective. The initial application of cost-time management within Westinghouse was targeted at reducing cycle time in the manufacturing sector. As a result of the tremendous success of reduced cycle time in manufacturing, Westinghouse initiated application of the management technique to Environmental Restoration activities at its Government Owned Contractor Operated facilities. The Westinghouse initiative was proposed in support of the Department of Energy`s goals for cost effective Environmental Restoration activities. This paper describes the application of the cost-time method to Environmental Restoration work currently being performed at the Idaho National Engineering Laboratory (INEL) for the Department of Energy (DOE) by Westinghouse Idaho Nuclear Company (WINCO).

Safety research experiment facilities, Idaho National Engineering Laboratory, Idaho. Final environmental impact statement

International Nuclear Information System (INIS)

Liverman, J.L.

1977-09-01

This environmental statement was prepared for the Safety Research Experiment Facilities (SAREF) Project. The purpose of the proposed project is to modify some existing facilities and provide a new test facility at the Idaho National Engineering Laboratory (INEL) for conducting fast breeder reactor (FBR) safety experiments. The SAREF Project proposal has been developed after an extensive study which identified the FBR safety research needs requiring in-reactor experiments and which evaluated the capability of various existing and new facilities to meet these needs. The proposed facilities provide for the in-reactor testing of large bundles of prototypical FBR fuel elements under a wide variety of conditions, ranging from those abnormal operating conditions which might be expected to occur during the life of an FBR power plant to the extremely low probability, hypothetical accidents used in the evaluation of some design options and in the assessment of the long-term potential risk associated with wide-acale deployment of the FBR

Fusion Safety Program. Annual report, FY 1982

International Nuclear Information System (INIS)

Crocker, J.G.; Cohen, S.

1983-07-01

The Fusion Safety Program major activities for Fiscal Year 1982 are summarized in this report. The program was started in FY-79, with the Idaho National Engineering Laboratory (INEL) designated as lead laboratory and EG and G Idaho, Inc., named as prime contractor to implement this role. The report contains four sections: EG and G Idaho, Inc., Activities at INEL includes major portions of papers dealing with ongoing work in tritium implantation experiments, tritium risk assessment, transient code development, heat transfer and fluid flow analysis, and high temperature oxidation and mobilization of structural material experiments. The section Outside Contracts includes studies of superconducting magnet safety conducted by Argonne National Laboratory, experiments concerning superconductor safety issues performed by the Francis Bitter Magnet Laboratory of the Massachusetts Institute of Technology (MIT) to verify analytical work, a continuation of safety and environmental studies by MIT, a summary of lithium safety experiments at Hanford Engineering Development Laboratory, and the results of tritium gas conversion to oxide experiments at Oak Ridge National Laboratory. A List of Publications and Proposed FY-83 Activities are also presented

High Level Waste Tank Farm Replacement Project for the Idaho Chemical Processing Plant at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

1993-06-01

The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA-0831, for the construction and operation of the High-Level Waste Tank Farm Replacement (HLWTFR) Project for the Idaho Chemical Processing Plant located at the Idaho National Engineering Laboratory (INEL). The HLWTFR Project as originally proposed by the DOE and as analyzed in this EA included: (1) replacement of five high-level liquid waste storage tanks with four new tanks and (2) the upgrading of existing tank relief piping and high-level liquid waste transfer systems. As a result of the April 1992 decision to discontinue the reprocessing of spent nuclear fuel at INEL, DOE believes that it is unlikely that the tank replacement aspect of the project will be needed in the near term. Therefore, DOE is not proposing to proceed with the replacement of the tanks as described in this-EA. The DOE's instant decision involves only the proposed upgrades aspect of the project described in this EA. The upgrades are needed to comply with Resource Conservation and Recovery Act, the Idaho Hazardous Waste Management Act requirements, and the Department's obligations pursuant to the Federal Facilities Compliance Agreement and Consent Order among the Environmental Protection Agency, DOE, and the State of Idaho. The environmental impacts of the proposed upgrades are adequately covered and are bounded by the analysis in this EA. If DOE later proposes to proceed with the tank replacement aspect of the project as described in the EA or as modified, it will undertake appropriate further review pursuant to the National Environmental Policy Act

Mineralogical correlation of surficial sediment from area drainages with selected sedimentary interbeds at the Idaho National Engineering Laboratory, Idaho

Energy Technology Data Exchange (ETDEWEB)

Bartholomay, R.C.

1990-08-01

Ongoing research by the US Geological Survey at the INEL involves investigation of the migration of radioactive elements contained in low-level radioactive waste, hydrologic and geologic factors affecting waste movement, and geochemical factors that influence the chemical composition of the waste. Identification of the mineralogy of the Snake River Plain is needed to aid in the study of the hydrology and geochemistry of subsurface waste disposal. The US Geological Surveys project office at the Idaho National Engineering Laboratory, in cooperation with the US Department of Energy, used mineralogical data to correlate surficial sediment samples from the Big Lost River, Little Lost River, and Birch Greek drainages with selected sedimentary interbed core samples taken from test holes at the RWMC (Radioactive Waste Management Complex), TRA (Test Reactors Area), ICPP (Idaho Chemical Processing Plant), and TAN (Test Area North). Correlating the mineralogy of a particular present-day drainage area with a particular sedimentary interbed provides information on historical source of sediment for interbeds in and near the INEL. Mineralogical data indicate that surficial sediment samples from the Big Lost River drainage contained a larger amount of feldspar and pyroxene and a smaller amount of calcite and dolomite than samples from the Little Lost River and Birch Creek drainages. Mineralogical data from sedimentary interbeds at the RWMC, TRA, and ICPP correlate with surficial sediment of the present-day big Lost River drainage. Mineralogical data from a sedimentary interbed at TAN correlate with surficial sediment of the present-day Birch Creek drainage. 13 refs., 5 figs., 3 tabs.

Mineralogical correlation of surficial sediment from area drainages with selected sedimentary interbeds at the Idaho National Engineering Laboratory, Idaho

International Nuclear Information System (INIS)

Bartholomay, R.C.

1990-08-01

Ongoing research by the US Geological Survey at the INEL involves investigation of the migration of radioactive elements contained in low-level radioactive waste, hydrologic and geologic factors affecting waste movement, and geochemical factors that influence the chemical composition of the waste. Identification of the mineralogy of the Snake River Plain is needed to aid in the study of the hydrology and geochemistry of subsurface waste disposal. The US Geological Surveys project office at the Idaho National Engineering Laboratory, in cooperation with the US Department of Energy, used mineralogical data to correlate surficial sediment samples from the Big Lost River, Little Lost River, and Birch Greek drainages with selected sedimentary interbed core samples taken from test holes at the RWMC (Radioactive Waste Management Complex), TRA (Test Reactors Area), ICPP (Idaho Chemical Processing Plant), and TAN (Test Area North). Correlating the mineralogy of a particular present-day drainage area with a particular sedimentary interbed provides information on historical source of sediment for interbeds in and near the INEL. Mineralogical data indicate that surficial sediment samples from the Big Lost River drainage contained a larger amount of feldspar and pyroxene and a smaller amount of calcite and dolomite than samples from the Little Lost River and Birch Creek drainages. Mineralogical data from sedimentary interbeds at the RWMC, TRA, and ICPP correlate with surficial sediment of the present-day big Lost River drainage. Mineralogical data from a sedimentary interbed at TAN correlate with surficial sediment of the present-day Birch Creek drainage. 13 refs., 5 figs., 3 tabs

PVWatts Version 5 Manual

Energy Technology Data Exchange (ETDEWEB)

Dobos, A. P.

2014-09-01

The NREL PVWatts calculator is a web application developed by the National Renewable Energy Laboratory (NREL) that estimates the electricity production of a grid-connected photovoltaic system based on a few simple inputs. PVWatts combines a number of sub-models to predict overall system performance, and makes includes several built-in parameters that are hidden from the user. This technical reference describes the sub-models, documents assumptions and hidden parameters, and explains the sequence of calculations that yield the final system performance estimate. This reference is applicable to the significantly revised version of PVWatts released by NREL in 2014.

Department of Energy Idaho Operations Office evaluation of feasibility studies for private sector treatment of alpha and TRU mixed wastes

International Nuclear Information System (INIS)

1995-05-01

The Idaho National Engineering Laboratory (INEL) is currently storing a large quantity of alpha contaminated mixed low level waste which will require treatment prior to disposal. The DOE Idaho Operations Office (DOE-ID) recognized that current knowledge and funding were insufficient to directly pursue services for the requisite treatment. Therefore, it was decided that private sector studies would be funded to clarify cost, regulatory, technology, and contractual issues associated with procuring treatment services. This report analyzes the three private sector studies procured and recommends a path forward for DOE in procuring retrieval, assay, characterization, and treatment services for INEL transuranic and alpha contaminated mixed low level waste. This report was prepared by a team of subject matter experts from the INEL referred to as the DOE-ID Evaluation Team

Preliminary systems design study assessment report

International Nuclear Information System (INIS)

Mayberry, J.L.; Feizollahi, F.; Del Signore, J.C.

1991-09-01

The System Design Study (SDS), part of the Waste Technology Development Department at the Idaho National Engineering Laboratory (INEL), examined techniques available for the remediation of hazardous and transuranic waste stored at the Radioactive Waste Management Complex's Subsurface Disposal Area at the INEL. Using specific technologies, system concepts for treating the buried waste and the surrounding contaminated soil were evaluated. Evaluation included implementability, effectiveness, and cost. The SDS resulted in the development of technology requirements including demonstration, testing, and evaluation activities needed for implementing each concept

ENERGY STAR Laboratory Grade Refrigerators and Freezers

Data.gov (United States)

U.S. Environmental Protection Agency — Certified models meet all ENERGY STAR requirements as listed in the Version 1.0 ENERGY STAR Program Requirements for Laboratory Grade Refrigerators and Freezers that...

Cost-time management for environmental restoration activities at the Department of Energy's Idaho National Engineering Laboratory, Idaho Chemical Processing Plant

Energy Technology Data Exchange (ETDEWEB)

Fourr, B.R.; Owen, A.H.; Williamson, D.J. (Westinghouse Idaho Nuclear Co., Inc., Idaho Falls, ID (United States)); Nash, C.L. (USDOE Idaho Field Office, Idaho Falls, ID (United States))

1992-05-22

Cost-time management methods have been developed by Westinghouse to examine business applications from a cost-time perspective. The initial application of cost-time management within Westinghouse was targeted at reducing cycle time in the manufacturing sector. As a result of the tremendous success of reduced cycle time in manufacturing, Westinghouse initiated application of the management technique to Environmental Restoration activities at its Government Owned Contractor Operated facilities. The Westinghouse initiative was proposed in support of the Department of Energy's goals for cost effective Environmental Restoration activities. This paper describes the application of the cost-time method to Environmental Restoration work currently being performed at the Idaho National Engineering Laboratory (INEL) for the Department of Energy (DOE) by Westinghouse Idaho Nuclear Company (WINCO).

Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Draft Environmental Impact Statement

International Nuclear Information System (INIS)

1994-06-01

The US Department of Energy (DOE) is engaged in two related decision making processes concerning: (1) the transportation, receipt, processing, and storage of spent nuclear fuel (SNF) at the DOE Idaho National Engineering Laboratory (INEL) which will focus on the next 10 years; and (2) programmatic decisions on future spent nuclear fuel management which will emphasize the next 40 years. DOE is analyzing the environmental consequences of these spent nuclear fuel management actions in this two-volume Environmental Impact Statement (EIS). Volume 1 supports broad programmatic decisions that will have applicability across the DOE complex and describes in detail the purpose and need for this DOE action. Volume 2 is specific to actions at the INEL. This document, which limits its discussion to the Savannah River Site (SRS) spent nuclear fuel management program, supports Volume 1 of the EIS. Following the introduction, Chapter 2 contains background information related to the SRS and the framework of environmental regulations pertinent to spent nuclear fuel management. Chapter 3 identifies spent nuclear fuel management alternatives that DOE could implement at the SRS, and summarizes their potential environmental consequences. Chapter 4 describes the existing environmental resources of the SRS that spent nuclear fuel activities could affect. Chapter 5 analyzes in detail the environmental consequences of each spent nuclear fuel management alternative and describes cumulative impacts. The chapter also contains information on unavoidable adverse impacts, commitment of resources, short-term use of the environment and mitigation measures

Improving tag/seal technologies: the vulnerability assessment component

International Nuclear Information System (INIS)

Jones, J.L.

1996-01-01

The Department of Energy (DOE), specifically the Office of Nonproliferation and National Security, has sponsored the development of numerous tag and seal technologies for high-security/high-valued applications. One important component in this technology development effort has been the continuous integration of vulnerability assessments. The Idaho National Engineering Laboratory (INEL) has been the lead laboratory for vulnerability assessments of fiber-optic-based tag/seal technologies. This paper presents a brief historical overview and the current status of the DOE high-security tag/seal development program and discusses INEL's adversarial role and assessment philosophy. Verification testing criteria used to define ''successful'' tampering attempts/attacks are discussed. Finally, the advantages of integrating a vulnerability assessment into the development of commercial security tag/seals are presented

Evaluation of existing EPRI and INEL test data to determine the worm to worm gear coefficient of friction in Limitorque actuators

Energy Technology Data Exchange (ETDEWEB)

Garza, I.A.

1996-12-01

About the last sizing parameter for motor operated valves which has not been determined by utility or NRC sponsored testing is actuator efficiency. A by-product of EPRI testing for valve factors is the measurement of the actuator efficiencies. Motor sizing in this testing provides efficiency testing for motors running near synchronous speed. INEL testing, sponsored by the NRC, for stem factors and rate of loading provides complimentary data for motors loaded down to zero speed. This paper analyzes the data from these two test programs to determine the coefficient of friction for the worm to worm gear interface. This allowed the development of an algorithm for determining the efficiency of actuators which have not been tested. This paper compares the results of this algorithm to the test data to provide a measure of the accuracy of this method for calculating actuator efficiency.

Evaluation of existing EPRI and INEL test data to determine the worm to worm gear coefficient of friction in Limitorque actuators

International Nuclear Information System (INIS)

Garza, I.A.

1996-01-01

About the last sizing parameter for motor operated valves which has not been determined by utility or NRC sponsored testing is actuator efficiency. A by-product of EPRI testing for valve factors is the measurement of the actuator efficiencies. Motor sizing in this testing provides efficiency testing for motors running near synchronous speed. INEL testing, sponsored by the NRC, for stem factors and rate of loading provides complimentary data for motors loaded down to zero speed. This paper analyzes the data from these two test programs to determine the coefficient of friction for the worm to worm gear interface. This allowed the development of an algorithm for determining the efficiency of actuators which have not been tested. This paper compares the results of this algorithm to the test data to provide a measure of the accuracy of this method for calculating actuator efficiency

Idaho National Engineering Laboratory hazardous and radioactive mixed waste identification and characterization report for CY 1986

International Nuclear Information System (INIS)

Nishimoto, D.D.

1987-05-01

This report provides updated tabulations of the hazardous and radioactive mixed wastes generated and/or handled during CY 1986 at each INEL facility operated by EG and G, or any other operating contractor at the Site. These wastes are described in tabular form, providing information such as composition, generating process, contact person, EPA hazardous waste designation, quantity shipped off site (if applicable), and quantity in storage. Waste generation projections for the next ten years are also included for all INEL facilities. Finally, since many of EG and G's inactive disposal sites may prove to be significant sources of either hazardous or radioactive mixed wastes as remedial action activities under RCRA or CERCLA progress, information on these sites is provided. 2 refs., 1 fig., 8 tabs

ISO/IEC 17025–2017 "New requirements to the competence of test and calibration laboratories"

Directory of Open Access Journals (Sweden)

Baranova P. O.

2018-05-01

Full Text Available due to the continuous improvement of the regulatory framework, there is a growing demand for laboratory centers that provide services in the field of testing. The relevance of the topic lies in the transition of laboratories to the new version of ISO/IEC 17025–2017 «General requirements for the competence of test and calibration laboratories». The article compares two versions of the standard, reveals differences and similarities. And changes in the gradation of changes are also highlighted.

Evaluation of field sampling and preservation methods for strontium-90 in ground water at the Idaho National Engineering Laboratory, Idaho

International Nuclear Information System (INIS)

Cecil, L.D.; Knobel, L.L.; Wegner, S.J.; Moore, L.L.

1989-01-01

Water from four wells completed in the Snake River Plain aquifer was sampled as part of the US Geological Survey's quality assurance program to evaluate the effect of filtration and preservation methods on strontium-90 concentrations in groundwater at the Idaho National Engineering Laboratory. Water from each well was filtered through either a 0.45-micrometer membrane or a 0.1-micrometer membrane filter; unfiltered samples also were collected. Two sets of filtered and two sets of unfiltered samples was preserved in the field with reagent-grade hydrochloric acid and the other set of samples was not acidified. For water from wells with strontium-90 concentrations at or above the reporting level, 94% or more of the strontium-90 is in true solution or in colloidal particles smaller than 0.1 micrometer. These results suggest that within-laboratory reproducibility for strontium-90 in groundwater at the INEL is not significantly affected by changes in filtration and preservation methods used for sample collections. 13 refs., 2 figs., 6 tabs

Summary of 1991--1992 misadministration event investigations

Energy Technology Data Exchange (ETDEWEB)

Ostrom, L.T.; Leahy, T.J.; Novack, S.D. [EG and G Idaho, Inc., Idaho Falls, ID (United States)

1994-03-01

Investigation team composed of representatives of the Idaho National Engineering Laboratory (INEL), the US Nuclear Regulatory Commission (NRC), and subcontracts investigated and analyzed seven misadministration events selected by the NRC concerning medical radioisotopes. Each team was led by an INEL member and depending on the nature of the event, included three or more team members with appropriate expertise in radiation oncology, medical physics, nuclear medicine technology, risk analysis, and human factors. The investigations focused on causes of the event, consequences, mitigating actions, and corrective actions. The major findings are described in this report.

Summary of 1991--1992 misadministration event investigations

International Nuclear Information System (INIS)

Ostrom, L.T.; Leahy, T.J.; Novack, S.D.

1994-03-01

Investigation team composed of representatives of the Idaho National Engineering Laboratory (INEL), the US Nuclear Regulatory Commission (NRC), and subcontracts investigated and analyzed seven misadministration events selected by the NRC concerning medical radioisotopes. Each team was led by an INEL member and depending on the nature of the event, included three or more team members with appropriate expertise in radiation oncology, medical physics, nuclear medicine technology, risk analysis, and human factors. The investigations focused on causes of the event, consequences, mitigating actions, and corrective actions. The major findings are described in this report

In-situ stabilization of TRU/mixed waste project at the INEEL

International Nuclear Information System (INIS)

Milian, L.W.; Heiser, J.H.; Adams, J.W.; Rutenkroeger, S.P.

1997-08-01

Throughout the DOE complex, buried waste poses a threat to the environment by means of contaminant transport. Many of the sites contain buried waste that is untreated, prior to disposal, or insufficiently treated, by today's standards. One option to remedy these disposal problems is to stabilize the waste in situ. This project was in support of the Transuranic/Mixed Buried Waste - Arid Soils product line of the Landfill Focus Area, which is managed currently by the Idaho National Engineering Laboratory (BNL) provided the analytical laboratory and technical support for the various stabilization activities that will be performed as part of the In Situ Stabilization of TRU/Mixed Waste project at the INEL. More specifically, BNL was involved in laboratory testing that included the evaluation of several grouting materials and their compatibility, interaction, and long-term durability/performance, following the encapsulation of various waste materials. The four grouting materials chosen by INEL were: TECT 1, a two component, high density cementious grout, WAXFIX, a two component, molten wax product, Carbray 100, a two component elastomeric epoxy, and phosphate cement, a two component ceramic. A simulated waste stream comprised of sodium nitrate, Canola oil, and INEL soil was used in this study. Seven performance and durability tests were conducted on grout/waste specimens: compressive strength, wet-dry cycling, thermal analysis, base immersion, solvent immersion, hydraulic conductivity, and accelerated leach testing

Nuclear reactor safety research in Idaho

International Nuclear Information System (INIS)

Zeile, H.J.

1983-01-01

Detailed information about the performance of nuclear reactor systems, and especially about the nuclear fuel, is vital in determining the consequences of a reactor accident. Fission products released from the fuel during accidents are the ultimate safety concern to the general public living in the vicinity of a nuclear reactor plant. Safety research conducted at the Idaho National Engineering Laboratory (INEL) in support of the U.S. Nuclear Regulatory Commission (NRC) has provided the NRC with detailed data relating to most of the postulated nuclear reactor accidents. Engineers and scientists at the INEL are now in the process of gathering data related to the most severe nuclear reactor accident - the core melt accident. This paper describes the focus of the nuclear reactor safety research at the INEL. The key results expected from the severe core damage safety research program are discussed

Procedure guideline for thyroid scintigraphy (version 3); Verfahrensanweisung fuer die Schilddruesenszintigraphie (Version 3)

Energy Technology Data Exchange (ETDEWEB)

Dietlein, M.; Schicha, H. [Deutsche Gesellschaft fuer Nuklearmedizin (DGN) (Germany); Koeln Univ. (Germany). Klinik und Poliklinik fuer Nuklearmedizin; Dressler, J. [Deutsche Gesellschaft fuer Nuklearmedizin (DGN) (Germany); Nuklearmedizinische Klinik der Henriettenstiftung, Hannover (Germany); Eschner, W. [Deutsche Gesellschaft fuer Nuklearmedizin (DGN) (Germany); Deutsche Gesellschaft fuer Medizinische Physik (DGMP) (Germany); Koeln Univ. (Germany). Klinik und Poliklinik fuer Nuklearmedizin; Leisner, B. [Deutsche Gesellschaft fuer Nuklearmedizin (DGN) (Germany); Allgemeines Krankenhaus St. Georg, Hamburg (Germany). Abt. fuer Nuklearmedizin; Reiners, C. [Deutsche Gesellschaft fuer Nuklearmedizin (DGN) (Germany); Wuerzburg Univ. (Germany). Klinik und Poliklinik fuer Nuklearmedizin

2007-07-01

The version 3 of the procedure guideline for thyroid scintigraphy is an update of the procedure guideline previously published in 2003. The interpretation of the scintigraphy requires the knowledge of the patients' history, the palpation of the neck, the laboratory parameters and of the sonography. The interpretation of the technetium-99m uptake requires the knowledge of the TSH-level. As a consequence of the improved alimentary iodine supply the {sup 99m}Tc-uptake has decreased; 100 000 counts per scintigraphy should be acquired. For this, an imaging time of 10 minutes is generally needed using a high resolution collimator for thyroid imaging. (orig.)

Comparisons of TRAC-PD2 calculations with Semiscale Mod-3 small-break tests

International Nuclear Information System (INIS)

Gilbert, J.S.; Sahota, M.S.; Boyack, B.E.; Booker, C.P.; Meier, J.K.

1981-01-01

Five experiments conducted in the Semiscale Mod-3 facility at the Idaho National Engineering Laboratory (INEL) were calculated using the latest released version of the Transient Reactor Analysis Code (TRAC-PD2). The results were used to assess TRAC-PD2 predictions of thermal-hydraulic phenomena and the effects of pump operation on system response during slow transients. Tests S-SB-P1, S-SB-P2, and S-SB-P7 simulated equivalent 2.5% communicative cold-leg breaks for early pump-trip (pumps-off), intermediate pump-trip (pumps-on), and late pump-trip (pumps-on) operation, respectively. Tests S-SB-P3 and S-SB-P4 simulated equivalent 2.5% communicative hot-leg breaks for pumps-off and pumps-on operation, respectively. Parameters examined in the study included primary system mass distribution, mass inventory, and void fraction distribution

TMAP4 User`s Manual

Energy Technology Data Exchange (ETDEWEB)

Longhurst, G.R.; Holland, D.F.; Jones, J.L.; Merrill, B.J.

1992-06-12

The Tritium Migration Analysis Program, Version 4 (TMAP4) has been developed by the Fusion Safety Program at the Idaho National Engineering Laboratory (INEL) as a safety analysis code, mainly to analyze tritium retention and loss in fusion reactor structures and systems during normal operation and accident conditions. TMAP4 incorporates one-dimensional thermal- and mass-diffusive transport and trapping calculations through structures and zero dimensional fluid transport between enclosures and across the interface between enclosures and structures. A key feature is the ability to input problem definition parameters as constants, interpolation tables, or FORTRAN equations. The code is specifically intended for use under a DOS operating system on PC-type mini-computers, but it has also been run successfully on workstations and mainframe computer systems. Use of the equation-input feature requires access to a FORTRAN-77 compiler and a linker program.

TMAP4 User's Manual

Energy Technology Data Exchange (ETDEWEB)

Longhurst, G.R.; Holland, D.F.; Jones, J.L.; Merrill, B.J.

1992-06-12

The Tritium Migration Analysis Program, Version 4 (TMAP4) has been developed by the Fusion Safety Program at the Idaho National Engineering Laboratory (INEL) as a safety analysis code, mainly to analyze tritium retention and loss in fusion reactor structures and systems during normal operation and accident conditions. TMAP4 incorporates one-dimensional thermal- and mass-diffusive transport and trapping calculations through structures and zero dimensional fluid transport between enclosures and across the interface between enclosures and structures. A key feature is the ability to input problem definition parameters as constants, interpolation tables, or FORTRAN equations. The code is specifically intended for use under a DOS operating system on PC-type mini-computers, but it has also been run successfully on workstations and mainframe computer systems. Use of the equation-input feature requires access to a FORTRAN-77 compiler and a linker program.

APNEA/WIT system nondestructive assay capability evaluation plan for select accessibly stored INEL RWMC waste forms

International Nuclear Information System (INIS)

Becker, G.K.

1997-01-01

Bio-Imaging Research Inc. (BIR) and Lockheed Martin Speciality Components (LMSC) are engaged in a Program Research and Development Agreement and a Rapid Commercialization Initiative with the Department of Energy, EM-50. The agreement required BIR and LMSC to develop a data interpretation method that merges nondestructive assay and nondestructive examination (NDA/NDE) data and information sufficient to establish compliance with applicable National TRU Program (Program) waste characterization requirements and associated quality assurance performance criteria. This effort required an objective demonstration of the BIR and LMSC waste characterization systems in their standalone and integrated configurations. The goal of the test plan is to provide a mechanism from which evidence can be derived to substantiate nondestructive assay capability and utility statement for the BIT and LMSC systems. The plan must provide for the acquisition, compilation, and reporting of performance data thereby allowing external independent agencies a basis for an objective evaluation of the standalone BIR and LMSC measurement systems, WIT and APNEA respectively, as well as an expected performance resulting from appropriate integration of the two systems. The evaluation is to be structured such that a statement regarding select INEL RWMC waste forms can be made in terms of compliance with applicable Program requirements and criteria

Version 4. 00 of the MINTEQ geochemical code

Energy Technology Data Exchange (ETDEWEB)

Eary, L.E.; Jenne, E.A.

1992-09-01

The MINTEQ code is a thermodynamic model that can be used to calculate solution equilibria for geochemical applications. Included in the MINTEQ code are formulations for ionic speciation, ion exchange, adsorption, solubility, redox, gas-phase equilibria, and the dissolution of finite amounts of specified solids. Since the initial development of the MINTEQ geochemical code, a number of undocumented versions of the source code and data files have come into use at the Pacific Northwest Laboratory (PNL). This report documents these changes, describes source code modifications made for the Aquifer Thermal Energy Storage (ATES) program, and provides comprehensive listings of the data files. A version number of 4.00 has been assigned to the MINTEQ source code and the individual data files described in this report.

Version 4.00 of the MINTEQ geochemical code

Energy Technology Data Exchange (ETDEWEB)

Eary, L.E.; Jenne, E.A.

1992-09-01

The MINTEQ code is a thermodynamic model that can be used to calculate solution equilibria for geochemical applications. Included in the MINTEQ code are formulations for ionic speciation, ion exchange, adsorption, solubility, redox, gas-phase equilibria, and the dissolution of finite amounts of specified solids. Since the initial development of the MINTEQ geochemical code, a number of undocumented versions of the source code and data files have come into use at the Pacific Northwest Laboratory (PNL). This report documents these changes, describes source code modifications made for the Aquifer Thermal Energy Storage (ATES) program, and provides comprehensive listings of the data files. A version number of 4.00 has been assigned to the MINTEQ source code and the individual data files described in this report.

Assessing the outcome of Strengthening Laboratory Management Towards Accreditation (SLMTA) on laboratory quality management system in city government of Addis Ababa, Ethiopia.

Science.gov (United States)

Sisay, Abay; Mindaye, Tedla; Tesfaye, Abrham; Abera, Eyob; Desale, Adino

2015-01-01

Strengthening Laboratory Management Toward Accreditation (SLMTA) is a competency-based management training programme designed to bring about immediate and measurable laboratory improvement. The aim of this study is to assess the outcome of SLMTA on laboratory quality management system in Addis Ababa, Ethiopia. The study used an Institutional based cross sectional study design that employed a secondary and primary data collection approach on the participated institution of medical laboratory in SLMTA. The study was conducted in Addis Ababa city government and the data was collected from February 'April 2014 and data was entered in to EPI-data version 3.1 and was analyzed by SPSS version 20. The assessment finding indicate that there was a significant improvement in average scores (141.4; range of 65-196, 95%CI=86.275-115.5, p=0.000) at final with 3 laboratories become 3 star, 6 laboratories were at 2 star, 11 were 1 star. Laboratory facilities respondents which thought getting adequate and timely manner mentorship were found 2.5 times more likely to get good success in the final score(AOR=2.501, 95% CI=1.109-4.602) than which did not get it. At the end of SLMTA implementation,3 laboratories score 3 star, 6 laboratories were at 2 star, 11 were at 1 star. The most important contributing factor for not scoring star in the final outcome of SLMTA were not conducting their customer satisfaction survey, poor staff motivation, and lack of regular equipment service maintenance. Mentorship, onsite and offsite coaching and training activities had shown a great improvement on laboratory quality management system in most laboratories.

Pressurized-water-reactor station blackout

International Nuclear Information System (INIS)

Dobbe, C.A.

1983-01-01

The purpose of the Severe Accident Sequence Analysis (SASA) Program was to investigate accident scenarios beyond the design basis. The primary objective of SASA was to analyze nuclear plant transients that could lead to partial or total core melt and evaluate potential mitigating actions. The following summarizes the pressurized water reactor (PWR) SASA effort at the Idaho National Engineering Laboratory (INEL). The INEL is presently evaluating Unresolved Safety Issue A-44 - Station Blackout from initiation of the transient to core uncovery. The balance of the analysis from core uncovery until fission product release is being performed at Sandia National Laboratory (SNL). The current analyses involve the Bellefonte Nuclear Steam Supply System (NSSS), a Babcock and Wilcox (B and W) 205 Fuel Assembly (205-FA) raised loop design to be operated by the Tennessee Valley Authority

Hydrology of the solid waste burial ground as related to potential migration of radionuclides, Idaho National Engineering Laboratory

Science.gov (United States)

Barraclough, Jack T.; Robertson, J.B.; Janzer, V.J.; Saindon, L.G.

1976-01-01

A study was made (1970-1974) to evaluate the geohydrologic and geochemical controls on subsurface migration of radionuclides from pits and trenches in the Idaho National Engineering Laboratory (INEL) solid waste burial ground and to determine the existence and extent of radionuclide migration from the burial ground. A total of about 1,700 sediment, rock, and water samples were collected from 10 observation wells drilled in and near the burial ground of Idaho National Engineering Laboratory, formerly the National Reactor Testing Station (NRTS). Within the burial ground area, the subsurface rocks are composed principally of basalt. Wind- and water-deposited sediments occur at the surface and in beds between the thicker basalt zones. Two principal sediment beds occur at about 110 feet and 240 feet below the land surface. The average thickness of the surficial sedimentary layer is about 15 feet while that of the two principal subsurface layers is 13 and 14 feet, respectively. The water table in the aquifer beneath the burial ground is at a depth of about 580 feet. Fission, activation, and transuranic elements were detected in some of the samples from the 110- and 240-foot sedimentary layers. (Woodard-USGS)

BNCT-RTPE: BNCT radiation treatment planning environment

International Nuclear Information System (INIS)

Wessol, D.E.; Wheeler, F.J.; Babcock, R.S.

1995-01-01

Several improvements have been developed for the BNCT radiation treatment planning environment (BNCT-Rtpe) during 1994. These improvements have been incorporated into Version 1.0 of BNCT-Rtpe which is currently installed at the INEL, BNL, Japanese Research Center (JRC), and Finland's Technical Research Center. Platforms supported by this software include Hewlett-Packard (HP), SUN, International Business Machines (IBM), and Silicon Graphics Incorporated (SGI). A draft version of the BNCT-Rtpe user manual is available. Version 1.1 of BNCT-Rtpe is scheduled for release in March 1995. It is anticipated that Version 2.x of BNCT-Rtpe, which includes the nonproprietary NURBS library and data structures, will be released in September 1995

Long-range plan for buried transuranic waste studies at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Berreth, P.D.; Fischer, D.K.; Suckel, R.A.

1984-11-01

This document presents a plan to perform detailed studies of alternatives considered for the long-term management of buried transuranic waste at the INEL. The studies will provide the technical basis for DOE to make a decision on the future management of that waste. Although the waste is currently being handled in an acceptable manner, new solutions are continually being researched to improve handling techniques. Three alternatives are being considered: (a) leave the waste as is; (b) improve in situ confinement of the waste; (c) retrieve, process, and certify the waste for disposal at a federal repository. Fifteen studies are described in this plan for the latter two alternatives. The leave-as-is alternative involves continuing present procedures for managing the buried waste. An ongoing environmental surveillance program, a low-level-waste stabilization program, and enhanced subsurface migration studies begun in FY-1984 at the INEL will provide data for the decision-making process for INEL buried TRU waste. These ongoing studies for the leave-as-is alternative are summarized in this plan in limited detail. The improved-confinement alternative involves leaving the waste in place, but providing additional protection against wind water penetration, erosion, and plant and animal intrusion. Several studies proposed will examine special techniques to immobilize or encapsulate the buried waste. Studies of the third alternative will investigate improved retrieval, processing and certification techniques. New equipment, such as industrial manipulators and excavating machinery, will be tested in the retrieval studies. Processing and certification studies will examine rapidly changing or new technologies. 19 references, 8 figures, 4 tables

Buried Waste Integrated Demonstration FY-95 Deployment Plan

Energy Technology Data Exchange (ETDEWEB)

Stacey, D.E.

1995-03-01

The Buried Waste Integrated Demonstration (BWID) is a program funded by the U.S. Department of Energy Office of Technology Development. BWID supports the applied research, development, demonstration, testing, and evaluation of a suite of advanced technologies that together form a comprehensive remediation system for the effective and efficient remediation of buried waste. The FY-95 effort will fund 24 technologies in five areas of buried waste site remediation: site characterization, waste characterization, retrieval, treatment, and containment/stabilization. Ten of these technologies will take part in the integrated field demonstration that will take place at the Idaho National Engineering Laboratory (INEL) facilities in the summer of 1995. This document is the basic operational planning document for deployment of all BWID projects funded in FY-95. Discussed in this document are the BWID preparations for the INEL integrated field demonstration, INEL research and development (R&D) demonstrations, non-INEL R&D demonstrations, and office research and technical review meetings. Each project will have a test plan detailing the specific procedures, objectives, and tasks of the test. Therefore, information that is specific to testing each technology is intentionally limited in this document.

Buried Waste Integrated Demonstration FY-95 Deployment Plan

International Nuclear Information System (INIS)

Stacey, D.E.

1995-03-01

The Buried Waste Integrated Demonstration (BWID) is a program funded by the U.S. Department of Energy Office of Technology Development. BWID supports the applied research, development, demonstration, testing, and evaluation of a suite of advanced technologies that together form a comprehensive remediation system for the effective and efficient remediation of buried waste. The FY-95 effort will fund 24 technologies in five areas of buried waste site remediation: site characterization, waste characterization, retrieval, treatment, and containment/stabilization. Ten of these technologies will take part in the integrated field demonstration that will take place at the Idaho National Engineering Laboratory (INEL) facilities in the summer of 1995. This document is the basic operational planning document for deployment of all BWID projects funded in FY-95. Discussed in this document are the BWID preparations for the INEL integrated field demonstration, INEL research and development (R ampersand D) demonstrations, non-INEL R ampersand D demonstrations, and office research and technical review meetings. Each project will have a test plan detailing the specific procedures, objectives, and tasks of the test. Therefore, information that is specific to testing each technology is intentionally limited in this document

Fiscal impacts model documentation. Version 1.0

International Nuclear Information System (INIS)

Beck, S.L.; Scott, M.J.

1986-05-01

The Fiscal Impacts (FI) Model, Version 1.0 was developed under Pacific Northwest Laboratory's Monitored Retrievable Storage (MRS) Program to aid in development of the MRS Reference Site Environmental Document (PNL 5476). It computes estimates of 182 fiscal items for state and local government jurisdictions, using input data from the US Census Bureau's 1981 Survey of Governments and local population forecasts. The model can be adapted for any county or group of counties in the United States

A novel natural analog in situ stabilization agent

International Nuclear Information System (INIS)

Shaw, P.

1995-01-01

This report summarizes the laboratory-scale test results on a synthetic analog of natural hematite cement for potential as an in situ treatment and stabilization agent for buried hazardous and radioactive waste. The concept is based on the principle that the ideal waste isolation materials are synthetic analogs of those natural encapsulating materials (cements), which are in equilibrium with the environment in which they occur. If equilibrium is achieved, then such materials will remain intact as long as the natural environment remains unchanged. The specific waste application is long-term stabilization of transuranic-contaminated waste pits and trenches at the Idaho National Engineering Laboratory (INEL). Six properties of the natural analog agent and resulting wasteforms are discussed to access the agent's effectiveness and implementability: hydraulic conductivity; compressive strength; mineralogy and microstructure; compatibility with possible waste materials, nitrates, machine cutting oil, and metallic iron; leachability of hazardous metals; and field application parameters. Data indicated that the iron waste encapsulation materials tested are appropriate choices for buried waste mixed with INEL soil. Iron oxide/gypsum INEL soil wasteforms have hydraulic conductivity values close to the regulatory limit. Wasteforms with soil and wastes have compressive strength greater than the regulatory minimum. Gypsum/iron oxide removes hazardous metals from solution by adsorption and would pass Toxicity Characteristic Leaching Procedure limits for most toxic metals. It appears to be chemically and physically inert with respect to the bulk of the waste materials likely to be found at INEL, and has properties conducive to jet grouting

An investigation of energy balances in palladium cathode electrolysis experiments

Science.gov (United States)

Longhurst, G. R.; Dolan, T. J.; Henriksen, G. L.

1990-09-01

A series of experiments was performed at the Idaho National Engineering Laboratory (INEL) to investigate mechanisms that may contribute to energy flows in electrolysis cells like those of Fleischmann and Pons. Ordinary water (H2O), heavy water (D2O), and a mixture of the two were used in the INEL experiments. Cathodes used include a 51-μm Pd foil and 1-mm diameter extruded wire Pd rods in straight and coiled configurations. Energy balances in these experiments revealed no significant net gain or net loss of energy. Cell overpotential curves were fit well with a Tafel equation, with parameters dependent on electrode configuration, electrolyte composition, and temperature. Water evaporation and interactions of hydrogen isotopes with the Pd cathode were evaluated and found not to be significant to energy balances. No ionizing radiation, tritium production, or other evidence of fusion reactions was observed in the INEL experiments.

Buried waste integrated demonstration FY 94 deployment plan

International Nuclear Information System (INIS)

Hyde, R.A.; Walker, S.; Garcia, M.M.

1994-05-01

The Buried Waste Integrated Demonstration (BWID) is a program funded by the U.S. Department of Energy Office of Technology Development. BWID supports the applied research, development, demonstration, testing, and evaluation of a suite of advanced technologies that together form a comprehensive remediation system for the effective and efficient remediation of buried waste. The fiscal year (FY) 1994 effort will fund thirty-eight technologies in five areas of buried waste site remediation: site characterization, waste characterization, retrieval, treatment, and containment/stabilization. This document is the basic operational planning document for deployment of all BWID projects. Discussed in this document are the BWID preparations for INEL field demonstrations, INEL laboratory demonstrations, non-INEL demonstrations, and paper studies. Each technology performing tests will prepare a test plan to detail the specific procedures, objectives, and tasks of each test. Therefore, information specific to testing each technology is intentionally omitted from this document

Alpha low-level stored waste systems design study

Energy Technology Data Exchange (ETDEWEB)

Feizollahi, F.; Teheranian, B. (Morrison Knudson Corp., San Francisco, CA (United States). Environmental Services Div.); Quapp, W.J. (EG and G Idaho, Inc., Idaho Falls, ID (United States))

1992-08-01

The Stored Waste System Design Study (SWSDS), commissioned by the Waste Technology Development Department at the Idaho National Engineering Laboratory (INEL), examines relative life-cycle costs associated with three system concepts for processing the alpha low-level waste (alpha-LLW) stored at the Radioactive Waste Management Complex's Transuranic Storage Area at the INEL. The three system concepts are incineration/melting; thermal treatment/solidification; and sort, treat, and repackage. The SWSDS identifies system functional and operational requirements and assesses implementability; effectiveness; cost; and demonstration, testing, and evaluation (DT E) requirements for each of the three concepts.

Alpha low-level stored waste systems design study

Energy Technology Data Exchange (ETDEWEB)

Feizollahi, F.; Teheranian, B. [Morrison Knudson Corp., San Francisco, CA (United States). Environmental Services Div.; Quapp, W.J. [EG and G Idaho, Inc., Idaho Falls, ID (United States)

1992-08-01

The Stored Waste System Design Study (SWSDS), commissioned by the Waste Technology Development Department at the Idaho National Engineering Laboratory (INEL), examines relative life-cycle costs associated with three system concepts for processing the alpha low-level waste (alpha-LLW) stored at the Radioactive Waste Management Complex`s Transuranic Storage Area at the INEL. The three system concepts are incineration/melting; thermal treatment/solidification; and sort, treat, and repackage. The SWSDS identifies system functional and operational requirements and assesses implementability; effectiveness; cost; and demonstration, testing, and evaluation (DT&E) requirements for each of the three concepts.

Refractory metal component technology for in-core sensor design

International Nuclear Information System (INIS)

Cannon, C.P.

1986-02-01

Within recent years, an increasing concern over reactor safety has prompted tests that characterize reactor core environments during transient conditions. Such tests include the Loss-of-Fluid-Tests (Idaho National Engineering Lab (INEL)), Severe Fuel Damage Tests (INEL), Core Debris Rubble Tests (Sandia National Laboratories (SNL)), and similar tests performed by foreign nations. The in-core sensors for these tests require refractory metal components to be compatible with electrical insulator materials as well as materials comprising highly corrosive service mediums. This paper presents the refractory metal technology utilized to provide basic sensor designs in the above mentioned reactor tests

Alpha low-level stored waste systems design study

International Nuclear Information System (INIS)

Feizollahi, F.; Teheranian, B.

1992-08-01

The Stored Waste System Design Study (SWSDS), commissioned by the Waste Technology Development Department at the Idaho National Engineering Laboratory (INEL), examines relative life-cycle costs associated with three system concepts for processing the alpha low-level waste (alpha-LLW) stored at the Radioactive Waste Management Complex's Transuranic Storage Area at the INEL. The three system concepts are incineration/melting; thermal treatment/solidification; and sort, treat, and repackage. The SWSDS identifies system functional and operational requirements and assesses implementability; effectiveness; cost; and demonstration, testing, and evaluation (DT ampersand E) requirements for each of the three concepts

ISOCELL trademark proof-of-concept for retrieval of wastes and contaminated soil

International Nuclear Information System (INIS)

Chatwin, T.D.; Krieg, R.K.

1992-01-01

ISOCELL TM cryogenic technology is designed to immobilize buried hazardous, radioactive, and mixed waste and contaminated soil by creating a block of frozen waste and soil that can be safely retrieved, stored, transported, and treated with a minimum of dust or aerosol production. A ''proof-of-concept'' test of the ISOCELL process was conducted in clean soil by RKK, Ltd., for the Idaho National Engineering Laboratory (INEL). Results indicate ISOCELL technology successfully froze moist soil into a solid block capable of being lifted and retrieved. Test conditions were compared to characteristics of possible buried waste sites in the INEL

Fusion Safety Program annual report, fiscal year 1983

International Nuclear Information System (INIS)

Crocker, J.G.; Holland, D.F.

1984-07-01

The Fusion Safety Program major activities for Fiscal Year 1983 are summarized in this report. The program was initiated in FY 1979, with the Idaho National Engineering Laboratory (INEL) designated lead laboratory, and EG and G Idaho, inc., named as prime contractor to implement this role. The report contains four sections: EG and G Idaho, Inc., activities at the INEL includes progress reports and portions of papers on the tritium implantation experiment, tritium control systems, tritium release from solid breeding blankets, plasma disruptions, risk assessment, transient code development, data base development, and a discussion of participation in the blanket comparison and selection study. The section outside contracts includes progress reports and portions of papers on lithium-lead reactions by Hanford Engineering Development Laboratory (HEDL) and the University of Wisconsin, magnet safety by the Francis Bitter Magnet Laboratory of the Massachusetts Institute of Technology (MIT) and Argonne National Laboratory (ANL), risk assessment by the University of California at Los Angeles (UCLA) and MIT, tritium retention by the University of Virginia, and effects of plasma disruptions by MIT. A list of publications and planned fiscal year 1984 activities are also included

Environmental Restoration and Waste Management Site-Specific Plan for Fiscal Year 1993

International Nuclear Information System (INIS)

1993-03-01

The Idaho National Engineering Laboratory (INEL) is a US Department of Energy (DOE) multiprogram laboratory whose primary mission has been to research nuclear technologies. Working with these technologies and conducting other types of research generates waste, including radioactive and/or hazardous wastes. While most of the waste treatment, storage, and disposal practices have been effective, some practices have led to the release of contaminants to the environment. As a result, DOE has developed (1) an Environmental Restoration (ER) Program to identify and, where necessary, cleanup releases from inactive waste sites and (2) a Waste Management (WM) Program to safely treat, store, and dispose of DOE wastes generated from current and future activities in an environmentally sound manner. This document describes the plans for FY 1993 for the INEL's ER and WM programs as managed by DOE's Idaho Field Office (DOE-ID)

Basalt features observed in outcrops, cores, borehole video imagery and geophysical logs, and basalt hydrogeologic study at the Idaho National Engineering Laboratory, Eastern Idaho

International Nuclear Information System (INIS)

Bennecke, W.M.

1996-10-01

A study was undertaken to examine permeable zones identified in boreholes open to the underlying basalt and to describe the vertical cross flows present in the boreholes. To understand the permeable zones in the boreholes detailed descriptions and measurements of three outcrops in the Snake River Plain, three cores at the Idaho Chemical Processing Plant (ICPP) at the INEL, and over fifty borehole TV logs from the INEL were carried out. Based on the observations made on the three outcrops an idealized basalt lava flow model was generated that used a set of nomenclature that would be standard for the basalt lava flows studied. An upper vesicular zone, a sometimes absent columnar zone, central zone, and lower vesicular zone make up the basalt lava flow model. The overall distinction between the different zones are based on the vesicle shape size, vesicularity, and fractures present. The results of the studies also indicated that the basalt lava flows at the INEL are distal to medial facies pahoehoe lava flows with close fitting contacts. The most permeable zones identified in these basalts are fractured vesiculated portions of the top of the lava flow, the columnar areas, and basalt-flow contacts in order of importance. This was determined from impeller flowmeter logging at the INEL. Having this information a detailed stratigraphy of individual basalt lava flows and the corresponding permeable units were generated. From this it was concluded that groundwater flow at the ICPP prefers to travel along thin basalt lava flows or flow-units. Flow direction and velocity of intrawell flows detected by flowmeter is controlled by a nearby pumping well

A data automation system at Los Alamos National Laboratory

International Nuclear Information System (INIS)

Betts, S.E.; Schneider, C.M.; Pickrell, M.M.

2001-01-01

Idaho National Engineering and Environmental Laboratory (INEEL) has developed an automated computer program, Data Review Expert System (DRXS), for reviewing nondestructive assay (NDA) data. DRXS significantly reduces the data review time needed to meet characterization requirements for the Waste Isolation Pilot Plant (WIPP). Los Alamos National Laboratory (LANL) is in the process of developing a computer program, Software System Logic for Intelligent Certification (SSLIC), to automate other tasks associa ted with characterization of Transuranic Waste (TRU) samples. LANL has incorporated a version of DRXS specific to LANL's isotopic data into SSLIC. This version of SSLIC was audited by the National Transuranic Program on October, 24, 2001. This paper will present the results of the audit, and discuss future plans for SSLIC including the integration on the INEELLANL developed Rule Editor.

BWR Refill-Reflood Program. Final report

International Nuclear Information System (INIS)

Myers, L.L.

1983-09-01

The BWR Refill-Reflood Program is part of the continuing Loss of Coolant Accident (LOCA) research in the United States which is jointly sponsored by the Nuclear Regulatory Commission, the Electric Power Research Institute, and the General Electric Company. The current program expanded the focus of this research to include full scale experimental evaluations of multidimensional and multichannel effects during system refill. The program has also made major contributions to the BWR version of the Transient Reactor Analysis Code (TRAC) which has been developed cooperatively with the Idaho National Engineering Laboratory (INEL) for application to BWR transients. A summary description of the complete program is provided including the principal findings and main conclusions of the program. The results of the program have shown that multidimensional and parallel channel effects have the potential to significantly improve the system response over that observed in single channel tests

TRAC-BD1: transient reactor analysis code for boiling-water systems

International Nuclear Information System (INIS)

Spore, J.W.; Weaver, W.L.; Shumway, R.W.; Giles, M.M.; Phillips, R.E.; Mohr, C.M.; Singer, G.L.; Aguilar, F.; Fischer, S.R.

1981-01-01

The Boiling Water Reactor (BWR) version of the Transient Reactor Analysis Code (TRAC) is being developed at the Idaho National Engineering Laboratory (INEL) to provide an advanced best-estimate predictive capability for the analysis of postulated accidents in BWRs. The TRAC-BD1 program provides the Loss of Coolant Accident (LOCA) analysis capability for BWRs and for many BWR related thermal hydraulic experimental facilities. This code features a three-dimensional treatment of the BWR pressure vessel; a detailed model of a BWR fuel bundle including multirod, multibundle, radiation heat transfer, leakage path modeling capability, flow-regime-dependent constitutive equation treatment, reflood tracking capability for both falling films and bottom flood quench fronts, and consistent treatment of the entire accident sequence. The BWR component models in TRAC-BD1 are described and comparisons with data presented. Application of the code to a BWR6 LOCA is also presented

The MiniBIOS model (version 1A4) at the RIVM

NARCIS (Netherlands)

Uijt de Haag PAM; Laheij GMH

1993-01-01

This report is the user's guide of the MiniBIOS model, version 1A4. The model is operational at the Laboratory of Radiation Research of the RIVM. MiniBIOS is a simulation model for calculating the transport of radionuclides in the biosphere and the consequential radiation dose to humans. The

Virginia Power and Department of Energy spent fuel transportation experience

International Nuclear Information System (INIS)

Ruska, M.D.; Schoonen, D.H.

1986-12-01

Spent fuel assemblies for the Spent Fuel Storage Cask Testing Program conducted by EG and G Idaho, Inc., at the Idaho National Engineering Laboratory (INEL) were transported to the INEL. A total of 69 spent fuel assemblies (23 shipments) were shipped from Virginia Power's nuclear power plant at Surry, Virginia, to the INEL between July 1985 and June 1986 to fill and test three spent fuel storage casks. The shipments were made over the highway system in Transnuclear, Inc., TN-8L shipping casks on specially constructed trailers. The shipments were moved by diesel tractors owned and operated by Tri-State Motor Transit Company of Joplin, Missouri. The gross vehicle weight for each shipment was 112,000 lb, which was a major consideration when selecting routes for the shipments. Cooperative negotiations with officials for the 17 states involved obtained authorization to transport through their states. The shipping campaign was successfully completed through close communication and cooperation and careful planning and operation by all organizations involved

Lead use and recycling at the INEL

International Nuclear Information System (INIS)

Losinski, S.J.; Thurmond, S.M.

1995-08-01

As part of DOE's efforts to develop a Department-wide management strategy for the use, reuse, and recycle of lead, DOE has requested that each site provide site-specific management and use practices for lead, specifically management and use information that responds to four specific questions of interest. This report provides the Idaho National Engineering Laboratory's response to those areas of interest

System software for the NMFECC CRAY-1 version of GIFTS 4B

International Nuclear Information System (INIS)

Gray, W.H.; Baudry, T.V.

1981-01-01

The Oak Ridge National Laboratory (ORNL) maintains a version of the GIFTS system structural analysis computer programs. Executable modules are supported on two different types of computer hardware, a DECsystem-10 and a CRAY-1. Without external difference to the user, these modules execute equivalently upon both types of hardware. Presented herein are the local software enhancements for the ORNL version of GIFTS for the National Magnetic Fusion Energy Computer Center (NMFECC) CRAY-1 computer as well as a description of the ORNL implementation of the system-dependent portions of the GIFTS software library for the NMFECC CRAY-1

INEL BNCT Research Program Annual Report 1993

Energy Technology Data Exchange (ETDEWEB)

Venhuizen, J.R.

1994-08-01

This report is a summary of the progress and research produced for the Idaho National Engineering Laboratory Boron Neutron Capture Therapy Research Program for calendar year 1993. Contributions from all the principal investigators are included, covering chemistry (pituitary tumor studies, boron drug development including liposomes, lipoproteins, and carboranylalanine derivatives), pharmacology (murine screenings, toxicity testing, boron drug analysis), physics (radiation dosimetry software, neutron beam and filter design, neutron beam measurement dosimetry), and radiation biology (tissue and efficacy studies of small and large animal models). Information on the potential toxicity of borocaptate sodium and boronophenylalanine is presented. Results of 21 spontaneous-tumor-bearing dogs that have been treated with boron neutron capture therapy at the Brookhaven National Laboratory are updated. Boron-containing drug purity verification is discussed in some detail. Advances in magnetic resonance imaging of boron in vivo are discussed. Several boron-carrying drugs exhibiting good tumor uptake are described. Significant progress in the potential of treating pituitary tumors is presented. Measurement of the epithermal-neutron flux of the Petten (The Netherlands) High Flux Reactor beam (HFB11B), and comparison to predictions are shown.

Safety Research Experiment Facilities, Idaho National Engineering Laboratory, Idaho. Draft environmental statement

International Nuclear Information System (INIS)

1977-01-01

This environmental statement was prepared in accordance with the National Environmental Policy Act of 1969 (NEPA) in support of the Energy Research and Development Administration's (ERDA) proposal for legislative authorization and appropriations for the Safety Research Experiment Facilities (SAREF) Project. The purpose of the proposed project is to modify some existing facilities and provide a new test facility at the Idaho National Engineering Laboratory (INEL) for conducting fast breeder reactor (FBR) safety experiments. The SAREF Project proposal has been developed after an extensive study which identified the FBR safety research needs requiring in-reactor experiments and which evaluated the capability of various existing and new facilities to meet these needs. The proposed facilities provide for the in-reactor testing of large bundles of prototypical FBR fuel elements under a wide variety of conditions, ranging from those abnormal operating conditions which might be expected to occur during the life of an FBR power plant to the extremely low probability, hypothetical accidents used in the evalution of some design options and in the assessment of the long-term potential risk associated with wide-scale deployment of the FBR

Strontium-90 concentrations in pronghorn antelope bones near a nuclear fuel reprocessing plant

International Nuclear Information System (INIS)

Markham, O.D.; Halford, D.K.

1980-01-01

Metacarpal bones were collected from pronghorn antelope near a nuclear fuel reprocessing plant and adjacent areas on the Idaho National Engineering Laboratory (INEL) Site in Southeastern Idaho. Control bones were collected from offsite animals at higher elevations. Average concentrations in metacarpals were 9.6+-2.8(SE) pCi/g(ash) within 10 km of the Idaho Chemical Processing Plant (ICPP), 4.0+-0.9pCi/g for animals on the remainder of the INEL Site and 5.5+-1.0pCi/g for control animals. ICPP atmospheric releases of 90 Sr appeared to have caused a significant (P 90 Sr concentrations in antelope bones within 10 km of the ICPP as compared to bones of other INEL antelope. However, the ICPP antelope bone 90 Sr concentrations were not statistically different from that occurring in bones of the control animals from higher elevations. Antelope near the ICPP received approximately double the radiation dose to bone compared to doses received by other INEL antelope as a result of 90 Sr in bone. Strontium-90 in bone from both fallout and ICPP sources resulted in an estimated average radiation dose of 40 mrad/yr to edosteal cells and 20 mrad/yr to active bone marrow. (author)

Environmental evaluation of alternatives for long-term management of Defense high-level radioactive wastes at the Idaho Chemical Processing Plant

Energy Technology Data Exchange (ETDEWEB)

1982-09-01

The U.S. Department of Energy (DOE) is considering the selection of a strategy for the long-term management of the defense high-level wastes at the Idaho Chemical Processing Plant (ICPP). This report describes the environmental impacts of alternative strategies. These alternative strategies include leaving the calcine in its present form at the Idaho National Engineering Laboratory (INEL), or retrieving and modifying the calcine to a more durable waste form and disposing of it either at the INEL or in an offsite repository. This report addresses only the alternatives for a program to manage the high-level waste generated at the ICPP. 24 figures, 60 tables.

Environmental evaluation of alternatives for long-term management of Defense high-level radioactive wastes at the Idaho Chemical Processing Plant

International Nuclear Information System (INIS)

1982-09-01

The U.S. Department of Energy (DOE) is considering the selection of a strategy for the long-term management of the defense high-level wastes at the Idaho Chemical Processing Plant (ICPP). This report describes the environmental impacts of alternative strategies. These alternative strategies include leaving the calcine in its present form at the Idaho National Engineering Laboratory (INEL), or retrieving and modifying the calcine to a more durable waste form and disposing of it either at the INEL or in an offsite repository. This report addresses only the alternatives for a program to manage the high-level waste generated at the ICPP. 24 figures, 60 tables

Grout testing and characterization for shallow-land burial trenches at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Tallent, O.K.; Sams, T.L.; Tamura, T.; Godsey, T.T.; Francis, C.L.; McDaniel, E.W.

1986-10-01

An investigation was conducted to develop grout formulations suitable for in situ stabilization of low-level and transuranic (TRU) waste in shallow-land burial trenches at Idaho National Engineering Laboratory (INEL). The acceptabilities of soil, ordinary particulate, and fine particulate grouts were evaluated based on phase separation, compressive strength, freeze/thaw, penetration resistance, rheological, water permeability, column, and other tests. Soil grouts with soil-to-cement weight ratios from 0.91 to 1.60 were found to be suitable for open trench or drum disposal. Ordinary particulate grouts containing type I,II Portland cement, class C fly ash, bentonite, water, and a fluidizer were formulated to fill large voids within the soil/waste matrix of a closed shallow-land burial trench. Fine particulate grouts containing fine (mean particle size, 9.6 m) cement and water were formulated to fill smaller voids and to establish a grout-soil barrier to prevent water intrusion into the grouted waste trench. Solution, or chemical grouts, were evaluated as possible substitutes for the fine particulate grouts

Three-dimensional chemical structure of the INEL aquifer system near the Idaho Chemical Processing Plant

International Nuclear Information System (INIS)

McCurry, M.; Estes, M.; Fromm, J.; Welhan, J.; Barrash, W.

1994-01-01

Sampling and analysis from the Snake River Plain aquifer using a stainless-steel and teflon constructed straddle-packer system has established detailed vertical profiles of aquifer chemistry from three wells near a major source of low-level waste injection at the Idaho Chemical Processing Plant. Multiple intervals, varying from 4.6 to 6.1 m in length, were sampled between the water table (140.5 mbls - meters below land surface), and approximately 200 mbls to obtain a wide spectrum of metals, anions, radiological and organic components analyses. Measurements were also made at the well sites of important transient parameters (T, Eh, Fe 3+ , Fe 2+ , DO and SC). The principal purpose of this ongoing work is to improve our understanding of the third (i.e. vertical) dimension of aquifer chemistry at the INEL as a basis for critically evaluating site-wide monitoring procedures, and, ultimately, for improving fate and transport models for aquifer contaminants within basalt-hosted aquifers. Chemical and radiological data indicates that substantial systematic vertical and lateral variations occur in the aquifer hydrochemistry - in particular for conservative radiological nuclide concentrations. Radiological data define a three-layered zonation. Ground water within upper and lower zones contain up to 10 times higher concentrations of H-3 and I-129 than in the middle zone. Sr-90 activity is decoupled from H-3 and I-129-relatively high activity was detected within the upper zone nearest the ICPP, but activities elsewhere are very low. 27 refs., 4 figs., 1 tab

Reliability on intra-laboratory and inter-laboratory data of hair mineral analysis comparing with blood analysis.

Science.gov (United States)

Namkoong, Sun; Hong, Seung Phil; Kim, Myung Hwa; Park, Byung Cheol

2013-02-01

Nowadays, although its clinical value remains controversial institutions utilize hair mineral analysis. Arguments about the reliability of hair mineral analysis persist, and there have been evaluations of commercial laboratories performing hair mineral analysis. The objective of this study was to assess the reliability of intra-laboratory and inter-laboratory data at three commercial laboratories conducting hair mineral analysis, compared to serum mineral analysis. Two divided hair samples taken from near the scalp were submitted for analysis at the same time, to all laboratories, from one healthy volunteer. Each laboratory sent a report consisting of quantitative results and their interpretation of health implications. Differences among intra-laboratory and interlaboratory data were analyzed using SPSS version 12.0 (SPSS Inc., USA). All the laboratories used identical methods for quantitative analysis, and they generated consistent numerical results according to Friedman analysis of variance. However, the normal reference ranges of each laboratory varied. As such, each laboratory interpreted the patient's health differently. On intra-laboratory data, Wilcoxon analysis suggested they generated relatively coherent data, but laboratory B could not in one element, so its reliability was doubtful. In comparison with the blood test, laboratory C generated identical results, but not laboratory A and B. Hair mineral analysis has its limitations, considering the reliability of inter and intra laboratory analysis comparing with blood analysis. As such, clinicians should be cautious when applying hair mineral analysis as an ancillary tool. Each laboratory included in this study requires continuous refinement from now on for inducing standardized normal reference levels.

Annotated bibliography of software engineering laboratory literature

Science.gov (United States)

Kistler, David; Bristow, John; Smith, Don

1994-01-01

This document is an annotated bibliography of technical papers, documents, and memorandums produced by or related to the Software Engineering Laboratory. Nearly 200 publications are summarized. These publications cover many areas of software engineering and range from research reports to software documentation. This document has been updated and reorganized substantially since the original version (SEL-82-006, November 1982). All materials have been grouped into eight general subject areas for easy reference: (1) The Software Engineering Laboratory; (2) The Software Engineering Laboratory: Software Development Documents; (3) Software Tools; (4) Software Models; (5) Software Measurement; (6) Technology Evaluations; (7) Ada Technology; and (8) Data Collection. This document contains an index of these publications classified by individual author.

Impact of the COBAS AmpliPrep/COBAS AMPLICOR HIV-1 MONITOR Test, Version 1.5, on Clinical Laboratory Operations▿

Science.gov (United States)

Germer, Jeffrey J.; Bendel, Jordan L.; Dolenc, Craig A.; Nelson, Sarah R.; Masters, Amanda L.; Gerads, Tara M.; Mandrekar, Jayawant N.; Mitchell, P. Shawn; Yao, Joseph D. C.

2007-01-01

The COBAS AmpliPrep/COBAS AMPLICOR HIV-1 MONITOR Test, version 1.5 (CAP/CA), and the COBAS AMPLICOR HIV-1 MONITOR Test, version 1.5, were compared. CAP/CA reduced and consolidated labor while modestly increasing assay throughput without increased failure rates or direct costs, regardless of batch size and assay format. PMID:17634308

Long-term management plan INEL transuranic waste

International Nuclear Information System (INIS)

McKinney, J.D.

1978-12-01

The Idaho National Engineering Laboratory stores large quantities of transuranic-contaminated waste at its Radioactive Waste Management Complex. This report presents a 10-year plan for management of this transuranic waste and includes descriptions of projects involving nuclear waste storage, retrieval, processing, systems analysis, and environmental science. Detailed project schedules and work breakdown charts are provided to give the reader a clear view of transuranic waste management objectives

NODC Standard Product: World Ocean Database 1998 version 2 (5 disc set) (NODC Accession 0098461)

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — Since the first release of WOD98, the staff of the Ocean Climate Laboratory have performed additional quality control on the database. Version 2.0 also includes...

Fusion safety program Annual report, Fiscal year 1995

International Nuclear Information System (INIS)

Longhurst, G.R.; Cadwallader, L.C.; Carmack, W.J.

1995-12-01

This report summarizes the major activities of the Fusion Safety Program in FY-95. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory, and Lockheed Idaho Technologies Company is the prime contractor for this program. The Fusion Safety Program was initiated in 1979. Activities are conducted at the INEL, at other DOE laboratories, and at other institutions. Among the technical areas covered in this report are tritium safety, beryllium safety, chemical reactions and activation product release, safety aspects of fusion magnet systems, plasma disruptions, risk assessment failure rate database development, and safety code development and application to fusion safety issues. Most of this work has been done in support of the International Thermonuclear Experimental Reactor (ITER). Also included in the report are summaries of the safety and environmental studies performed by the Fusion Safety Program for the Tokamak Physics Experiment and the Tokamak Fusion Test Reactor and the technical support for commercial fusion facility conceptual design studies. A final activity described is work to develop DOE Technical Standards for Safety of Fusion Test Facilities

Fusion Safety Program Annual Report, Fiscal Year 1996

International Nuclear Information System (INIS)

Longhurst, G.R.; Anderl, R.A.; Cadwallader, L.C.

1996-12-01

This report summarizes the major activities of the Fusion Safety Program in FY 1996. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory, and Lockheed Martin Idaho Technologies Company is the prime contractor for this program. The Fusion Safety Program was initiated in 1979. The objective is to perform research and develop data needed to ensure safety in fusion facilities. Activities include experiments, analysis, code development and application, and other forms of research. These activities are conducted at the INEL, at other DOE laboratories, and at other institutions. Among the technical areas covered in this report are tritium safety, chemical reactions and activation product release, risk assessment failure rate database development, and safety code development and application to fusion safety issues. Most of this work has been done in support of the International Thermonuclear Experimental Reactor (ITER). Work done for ITER this year has focused on developing the needed information for the Non- Site- Specific Safety Report (NSSR-1). A final area of activity described is development of the new DOE Technical Standards for Safety of Magnetic Fusion Facilities

Automating the Analytical Laboratories Section, Lewis Research Center, National Aeronautics and Space Administration: a feasibility study

International Nuclear Information System (INIS)

Boyle, W.G.; Barton, G.W.

1979-01-01

We studied the feasibility of computerized automation of the Analytical Laboratories Section at NASA's Lewis Research Center. Since that laboratory's duties are not routine, we set our automation goals with that in mind. We selected four instruments as the most likely automation candidates: an atomic absorption spectrophotometer, an emission spectrometer, an x-ray fluorescence spectrometer, and an x-ray diffraction unit. Our study describes two options for computer automation: a time-shared central computer and a system with microcomputers for each instrument connected to a central computer. A third option, presented for future planning, expands the microcomputer version. We determine costs and benefits for each option. We conclude that the microcomputer version best fits the goals and duties of the laboratory and that such an automated system is needed to meet the laboratory's future requirements

EPDL97: the evaluated photon data library, '97 version. Summary documentation

International Nuclear Information System (INIS)

Pronyaev, V.G.; McLaughlin, P.

1998-01-01

The Evaluated Photon Data Library, 1997 version (EPDL97), is designed for use in photon transport calculations at Lawrence Livermore National Laboratory. This library includes photon interaction data for all elements with atomic number between Z = 1 (hydrogen) and 100 (fermium), including: photoionization, photoexcitation, coherent and incoherent scattering, and pair and triplet production cross sections. For use in applications data is provided for all elements over the energy range 1 eV to 100 GeV. EPDL97 completely supersedes the earlier 1989 version of EPDL(89) (see IAEA-NDS-158, Summary documentation to the EPDL) and it is highly recommended that users only use the most recent version of this library. The Evaluated Atomic Data Library (EADL), Evaluated Electron Data Library (EEDL) an Evaluated Excitation Data Library (EXDL) are included to allow consistent coupled photon-electron transport calculations. The data package is available from the IAEA Nuclear Data Section on CD-ROM (12 files, 74.2 MB). (author)

A process for ensuring regulatory compliance at the INEL`s buried waste integrated demonstrations

Energy Technology Data Exchange (ETDEWEB)

Cannon, P.G.; Watson, L.R.; Blacker, P.B. [EG and G Idaho, Inc., Idaho Falls, ID (United States). Idaho National Engineering Lab.

1993-03-01

The Buried Waste Integrated Demonstration Program is funded by the Department of Energy Office of Technology Development. The mission of this Integrated Demonstration is to identify, evaluate, and demonstrate a suite of innovative technologies for the remediation of radioactive and hazardous waste buried throughout the DOE complex between 1950 and 1970. The program approach to development of a long-range strategy for improving buried waste remediation capabilities is to combine systems analysis with already identified remediation needs for DOE complex buried waste. The systems analysis effort has produced several configuration options (a top-level block diagram of a cradle-to-grave remediation system) capable of remediating the transuranic-contaminated waste pits and trenches at the Idaho National Engineering Laboratory. Technologies for demonstration are selected using three criteria: (a) the ability to satisfy a specific buried waste need, (b) the ability to satisfy functional and operational requirements defined for functional sub-elements in a configuration option, and (c) performance against Comprehensive Environmental Restoration and Compensation Liability Act selection criteria, such as effectiveness, implementability, and cost. Early demonstrations experienced problems with missed requirements, prompting the Buried Waste Integrated Demonstration Program Office to organize a Corrective Action Team to identify the cause and recommend corrective actions. The result of this team effort is the focus of this paper.

[External cephalic version].

Science.gov (United States)

Navarro-Santana, B; Duarez-Coronado, M; Plaza-Arranz, J

2016-08-01

To analyze the rate of successful external cephalic versions in our center and caesarean sections that would be avoided with the use of external cephalic versions. From January 2012 to March 2016 external cephalic versions carried out at our center, which were a total of 52. We collected data about female age, gestational age at the time of the external cephalic version, maternal body mass index (BMI), fetal variety and situation, fetal weight, parity, location of the placenta, amniotic fluid index (ILA), tocolysis, analgesia, and newborn weight at birth, minor adverse effects (dizziness, hypotension and maternal pain) and major adverse effects (tachycardia, bradycardia, decelerations and emergency cesarean section). 45% of the versions were unsuccessful and 55% were successful. The percentage of successful vaginal delivery in versions was 84% (4% were instrumental) and 15% of caesarean sections. With respect to the variables studied, only significant differences in birth weight were found; suggesting that birth weight it is related to the outcome of external cephalic version. Probably we did not find significant differences due to the number of patients studied. For women with breech presentation, we recommend external cephalic version before the expectant management or performing a cesarean section. The external cephalic version increases the proportion of fetuses in cephalic presentation and also decreases the rate of caesarean sections.

Development of IMPACTS-BRC, Version 2.1

International Nuclear Information System (INIS)

Rao, R.R.; Kozak, M.W.; Rollstin, J.A.

1991-01-01

IMPACTS-BRC is a computer program developed to conduct scoping analyses for use in supporting rulemaking on petitions for exemption of waste streams from multiple producers. It was not initially intended for use on individual license applications for specific sites. However, the Federal Register, Volume 51, Number 168, specifies that IMPACTS-BRC be used to evaluate incoming license applications. This creates a problem since IMPACTS-BRC is not being used for its intended purpose. It is a generic code that is now being used for site specific applications. This is only a valid procedure if it can be shown that generic results from IMPACTS-BRC are conservative when compared to results from site specific models. Otherwise, IMPACTS-BRC should not be used. The purpose of this work was to verify that IMPACTS-BRC works as specified in its user's guide. In other words, Sandia National Laboratories (SNL) has determined that the mathematical models given in the user's guide are correctly implemented into the computer code. No direct work has been done to verify that the mathematical models used in the code are appropriate for the purpose that they are being used. In fact, scrutiny of the groundwater transport models in IMPACTS-BRC has led us to recommend that alternate geosphere models should be used. Other work carried out for this project included verifying that the input data for IMPACTS-BRC is correct and traceable. This was carried out, and a new version of the data with these qualities was produced. The new version of the data was used with the verified IMPACTS-BRC, Version 2.0 to produce IMPACTS-BRC, Version 2.1

The electromagnetic integrated demonstration at the Idaho National Engineering Laboratory cold test pit

International Nuclear Information System (INIS)

Pellerin, L.; Alumbaugh, D.L.; Pfeifer, M.C.

1997-01-01

The electromagnetic integrated demonstration (EMID) is a baseline study in electromagnetic (EM) exploration of the shallow subsurface (< 10 m). Eleven distinct EM systems, covering the geophysical spectrum, acquired data on a grid over the Idaho National Engineering Laboratory (INEL) Cold Test Pit (CTP). The systems are investigated and evaluated for the purpose of identifying and reviewing existing geophysical characterization instrumentation (commercial and experimental), integrating those technologies with multi-dimensional interpretational algorithms, and identifying gaps in shallow subsurface EM imaging technology. The EMID data, are valuable for testing and evaluating new interpretational software, and developing techniques for integrating multiple datasets. The experimental field techniques shows how the acquisition of data in a variety of array configurations can considerably enhance interpretation. All data are available on the world wide web. Educators and students are encouraged to use the data for both classroom and graduate studies. The purpose of this paper is to explain why, where, how and what kind of data were collected. It is left to the reader to assess the value of a given system for their particular application. Information about the EMID is organized into two general categories: survey description and system evaluation

Laboratory Guide for Residual Stress Sample Alignment and Experiment Planning-October 2011 Version

Energy Technology Data Exchange (ETDEWEB)

Cornwell, Paris A [ORNL; Bunn, Jeffrey R [ORNL; Schmidlin, Joshua E [ORNL; Hubbard, Camden R [ORNL

2012-04-01

The December 2010 version of the guide, ORNL/TM-2008/159, by Jeff Bunn, Josh Schmidlin, Camden Hubbard, and Paris Cornwell, has been further revised due to a major change in the GeoMagic Studio software for constructing a surface model. The Studio software update also includes a plug-in module to operate the FARO Scan Arm. Other revisions for clarity were also made. The purpose of this revision document is to guide the reader through the process of laser alignment used by NRSF2 at HFIR and VULCAN at SNS. This system was created to increase the spatial accuracy of the measurement points in a sample, reduce the use of neutron time used for alignment, improve experiment planning, and reduce operator error. The need for spatial resolution has been driven by the reduction in gauge volumes to the sub-millimeter level, steep strain gradients in some samples, and requests to mount multiple samples within a few days for relating data from each sample to a common sample coordinate system. The first step in this process involves mounting the sample on an indexer table in a laboratory set up for offline sample mounting and alignment in the same manner it would be mounted at either instrument. In the shared laboratory, a FARO ScanArm is used to measure the coordinates of points on the sample surface ('point cloud'), specific features and fiducial points. A Sample Coordinate System (SCS) needs to be established first. This is an advantage of the technique because the SCS can be defined in such a way to facilitate simple definition of measurement points within the sample. Next, samples are typically mounted to a frame of 80/20 and fiducial points are attached to the sample or frame then measured in the established sample coordinate system. The laser scan probe on the ScanArm can then be used to scan in an 'as-is' model of the sample as well as mounting hardware. GeoMagic Studio 12 is the software package used to construct the model from the point cloud the

Laboratory Guide for Residual Stress Sample Alignment and Experiment Planning-October 2011 Version

International Nuclear Information System (INIS)

Cornwell, Paris A.; Bunn, Jeffrey R.; Schmidlin, Joshua E.; Hubbard, Camden R.

2012-01-01

The December 2010 version of the guide, ORNL/TM-2008/159, by Jeff Bunn, Josh Schmidlin, Camden Hubbard, and Paris Cornwell, has been further revised due to a major change in the GeoMagic Studio software for constructing a surface model. The Studio software update also includes a plug-in module to operate the FARO Scan Arm. Other revisions for clarity were also made. The purpose of this revision document is to guide the reader through the process of laser alignment used by NRSF2 at HFIR and VULCAN at SNS. This system was created to increase the spatial accuracy of the measurement points in a sample, reduce the use of neutron time used for alignment, improve experiment planning, and reduce operator error. The need for spatial resolution has been driven by the reduction in gauge volumes to the sub-millimeter level, steep strain gradients in some samples, and requests to mount multiple samples within a few days for relating data from each sample to a common sample coordinate system. The first step in this process involves mounting the sample on an indexer table in a laboratory set up for offline sample mounting and alignment in the same manner it would be mounted at either instrument. In the shared laboratory, a FARO ScanArm is used to measure the coordinates of points on the sample surface ('point cloud'), specific features and fiducial points. A Sample Coordinate System (SCS) needs to be established first. This is an advantage of the technique because the SCS can be defined in such a way to facilitate simple definition of measurement points within the sample. Next, samples are typically mounted to a frame of 80/20 and fiducial points are attached to the sample or frame then measured in the established sample coordinate system. The laser scan probe on the ScanArm can then be used to scan in an 'as-is' model of the sample as well as mounting hardware. GeoMagic Studio 12 is the software package used to construct the model from the point cloud the scan arm creates. Once

LEAN LABORATORY APPROACHES FOR QUALITY ASSURANCE IN FOOD

Directory of Open Access Journals (Sweden)

Laxmana Naik

2011-09-01

Full Text Available A lean laboratory is one which is focused on testing products and materials to deliver results in the most efficient way in terms of cost or speed or both; primarily focused on improving measurable performance and reducing costs. The goal of a lean laboratory is to use less effort, less resources and less time to test incoming samples. Laboratories have a critical role to play in establishing and improving process capability and key performance indicator (KPI of the organization. There are inevitably many opinions as to what a lean lab actually is; here is one version fr om. Quality assurance laboratories are crucial to the success of organization and this effectiveness needs to be measurable and demonstrable. To facilitate this, a method of measuring a laboratory's progress towards complete deployment has been created by lean tools. These tools allow laboratories to conduct gap analysis and identify opportunities for improvement.

Impact of surface water recharge on the design of a groundwater monitoring system for the Radioactive Waste Management Complex, Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Wood, T.R.

1990-01-01

Recent hydrogeologic studies have been initiated to characterize the hydrogeologic conditions at the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering Laboratory (INEL). Measured water levels in wells penetrating the Snake River Plain aquifer near the RWMC and the corresponding direction of flow show change over time. This change is related to water table mounding caused by recharge from excess water diverted from the Big Lost River for flood protection during high flows. Water levels in most wells near the RWMC rise on the order of 10 ft (3 m) in response to recharge, with water in one well rising over 60 ft (18 m). Recharge changes the normal south-southwest direction of flow to the east. Design of the proposed groundwater monitoring network for the RWMC must account for the variable directions of groundwater flow. 11 refs., 9 figs., 2 tabs

Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Draft Environmental Impact Statement. Volume 1, Appendix C, Savannah River Site Spent Nuclear Fuel Mangement Program

Energy Technology Data Exchange (ETDEWEB)

1994-06-01

The US Department of Energy (DOE) is engaged in two related decision making processes concerning: (1) the transportation, receipt, processing, and storage of spent nuclear fuel (SNF) at the DOE Idaho National Engineering Laboratory (INEL) which will focus on the next 10 years; and (2) programmatic decisions on future spent nuclear fuel management which will emphasize the next 40 years. DOE is analyzing the environmental consequences of these spent nuclear fuel management actions in this two-volume Environmental Impact Statement (EIS). Volume 1 supports broad programmatic decisions that will have applicability across the DOE complex and describes in detail the purpose and need for this DOE action. Volume 2 is specific to actions at the INEL. This document, which limits its discussion to the Savannah River Site (SRS) spent nuclear fuel management program, supports Volume 1 of the EIS. Following the introduction, Chapter 2 contains background information related to the SRS and the framework of environmental regulations pertinent to spent nuclear fuel management. Chapter 3 identifies spent nuclear fuel management alternatives that DOE could implement at the SRS, and summarizes their potential environmental consequences. Chapter 4 describes the existing environmental resources of the SRS that spent nuclear fuel activities could affect. Chapter 5 analyzes in detail the environmental consequences of each spent nuclear fuel management alternative and describes cumulative impacts. The chapter also contains information on unavoidable adverse impacts, commitment of resources, short-term use of the environment and mitigation measures.

Laboratory Information Management System (LIMS): A case study

Science.gov (United States)

Crandall, Karen S.; Auping, Judith V.; Megargle, Robert G.

1987-01-01

In the late 70's, a refurbishment of the analytical laboratories serving the Materials Division at NASA Lewis Research Center was undertaken. As part of the modernization efforts, a Laboratory Information Management System (LIMS) was to be included. Preliminary studies indicated a custom-designed system as the best choice in order to satisfy all of the requirements. A scaled down version of the original design has been in operation since 1984. The LIMS, a combination of computer hardware, provides the chemical characterization laboratory with an information data base, a report generator, a user interface, and networking capabilities. This paper is an account of the processes involved in designing and implementing that LIMS.

Global Precipitation Climatology Project (GPCP) - Monthly, Version 2.2 (Version Superseded)

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — Version 2.2 of the dataset has been superseded by a newer version. Users should not use version 2.2 except in rare cases (e.g., when reproducing previous studies...

Solid Waste Projection Model: Database (Version 1.3)

International Nuclear Information System (INIS)

Blackburn, C.L.

1991-11-01

The Solid Waste Projection Model (SWPM) system is an analytical tool developed by Pacific Northwest Laboratory (PNL) for Westinghouse Hanford Company (WHC). The SWPM system provides a modeling and analysis environment that supports decisions in the process of evaluating various solid waste management alternatives. This document, one of a series describing the SWPM system, contains detailed information regarding the software and data structures utilized in developing the SWPM Version 1.3 Database. This document is intended for use by experienced database specialists and supports database maintenance, utility development, and database enhancement

Pilot-scale testing of refining process for decontamination of lead

International Nuclear Information System (INIS)

Davis, M.V.

1991-01-01

Lead at the Idaho National Engineering Laboratory (INEL) is predominantly used for radiation shielding. Lead is a hazardous material. When it becomes radioactively contaminated and can no longer be used as shielding, it becomes a mixed/hazardous radioactive waste. It is then subject to Environmental Protection Agency (EPA) regulations. The regulations require that lead be treated prior to disposal. There is no treatment process that will render lead nonhazardous nor is there a disposal site that will accept lead as a mixed waste. Decontamination of lead is the only alternative. Therefore, DOE-ID has initiated a lead management program to minimize the amount of lead waste generated at the INEL and to decontaminate existing inventories of contaminated lead

IBM-PC-based reactor neutronics analysis package

International Nuclear Information System (INIS)

Nigg, D.W.; Wessol, D.E.; Grimesey, R.A.; Parsons, D.K.; Wheeler, F.J.; Yoon, W.Y.; Lake, J.A.

1985-01-01

Technical advances over the past few years have led to a situation where a wide range of complex scientific computations can now be done on properly configured microcomputers such as the IBM-PC (personal computer). For a number of reasons, including security, economy, and user convenience, the development of a comprehensive system of reactor neutronics codes suitable for operation on the IBM-PC has been undertaken at the Idaho National Engineering Laboratory (INEL). It is anticipated that a PC-based code system could also have wide applicability in the nuclear engineering education community since conversion of software generated by national laboratories and others to college and university mainframe hardware has historically been a time-consuming process that has sometimes met with only limited success. This paper discusses the philosophy behind the INEL reactor neutronics PC code system and describes those parts of the system that are currently complete, those that are now under development, and those that are still in the planning stage

Historical summary of the Three Mile Island Unit 2 core debris transportation campaign

Energy Technology Data Exchange (ETDEWEB)

Schmitt, R.C.; Tyacke, M.J. [EG and G Idaho, Inc., Idaho Falls, ID (United States); Quinn, G.J. [Wastren, Inc., Germantown, MD (United States)

1993-03-01

Transport of the damaged core materials from the Unit 2 reactor of the Three Mile Island Nuclear Power Station (TMI-2) to the Idaho National Engineering Laboratory (INEL) for examination and storage presented many technical and institutional challenges, including assessing the ability to transport the damaged core; removing and packaging core debris in ways suitable for transport; developing a transport package that could both meet Federal regulations and interface with the facilities at TMI-2 and the INEL; and developing a transport plan, support logistics, and public communications channels suited to the task. This report is a historical summary of how the US Department of Energy addressed those challenges and transported, received, and stored the TMI-2 core debris at the INEL. Subjects discussed include preparations for transport, loading at TMI-2, institutional issues, transport operations, receipt and storage at the INEL, governmental inquiries/investigations, and lessons learned. Because of public attention focused on the TMI-2 Core Debris Transport Program, the exchange of information between the program and public was extensive. This exchange is a focus for parts of this report to explain why various operations were conducted as they were and why certain technical approaches were employed. And, because of that exchange, the program may have contributed to a better public understanding of such actions and may contribute to planning and execution of similar future actions.

Historical summary of the Three Mile Island Unit 2 core debris transportation campaign

International Nuclear Information System (INIS)

Schmitt, R.C.; Tyacke, M.J.; Quinn, G.J.

1993-03-01

Transport of the damaged core materials from the Unit 2 reactor of the Three Mile Island Nuclear Power Station (TMI-2) to the Idaho National Engineering Laboratory (INEL) for examination and storage presented many technical and institutional challenges, including assessing the ability to transport the damaged core; removing and packaging core debris in ways suitable for transport; developing a transport package that could both meet Federal regulations and interface with the facilities at TMI-2 and the INEL; and developing a transport plan, support logistics, and public communications channels suited to the task. This report is a historical summary of how the US Department of Energy addressed those challenges and transported, received, and stored the TMI-2 core debris at the INEL. Subjects discussed include preparations for transport, loading at TMI-2, institutional issues, transport operations, receipt and storage at the INEL, governmental inquiries/investigations, and lessons learned. Because of public attention focused on the TMI-2 Core Debris Transport Program, the exchange of information between the program and public was extensive. This exchange is a focus for parts of this report to explain why various operations were conducted as they were and why certain technical approaches were employed. And, because of that exchange, the program may have contributed to a better public understanding of such actions and may contribute to planning and execution of similar future actions

Field application of innovative grouting agents for in situ stabilization of buried waste sites

International Nuclear Information System (INIS)

Loomis, G.G.; Farnsworth, R.K.

1997-01-01

This paper presents field applications for two innovative grouting agents that were used to in situ stabilize buried waste sites, via jet grouting. The two grouting agents include paraffin and a proprietary iron oxide based cement grout called TECT. These materials were tested in specially designed cold test pits that simulate buried transuranic waste at the Idaho National Engineering Laboratory (INEL). The field demonstrations were performed at the INEL in an area referred to as the Cold Test Pit, which is adjacent to the INEL Radioactive Waste Management Complex (RWMC). At the RWMC, 56,000 m 3 of transuranic (TRU) waste is co-mingled with over 170,000 m 3 of soil in shallow land burial. Improving the confinement of this waste is one of the options for final disposition of this waste. Using jet-grouting technology to inject these materials into the pore spaces of buried waste sites results in the creation of buried monolithic waste forms that simultaneously protect the waste from subsidence, while eliminating the migratory potential of hazardous and radioactive contaminants in the waste

Program plan for shipment, receipt, and storage of the TMI-2 core. Revision 1

International Nuclear Information System (INIS)

Quinn, G.J.; Reno, H.W.; Schmitt, R.C.

1985-01-01

This plan addresses the preparation and shipment of core debris from Three Mile Island Unit 2 (TMI-2) to the Idaho National Engineering Laboratory (INEL) and receipt and storage of that core debris. The Manager of the Nuclear Materials Evaluation Programs Division of EG and G Idaho, Inc. will manage two separate but integrated programs, one located at TMI (Part 1) and the other at INEL (Part 2). The Technical Integration Office (at TMI) is responsible for developing and implementing Part 1, TMI-2 Core Shipment Program. The Technical Support Branch (at INEL) is responsible for developing and implementing Part 2, TMI-2 Core Receipt and Storage. The plan described herein is a revision of a previous document entitled Plan for Shipment, Storage, and Examination of TMI-2 Fuel. This revision was required to delineate changes, primarily in Part 2, Core Activities Program, of the previous document. That part of the earlier document related to core examination was reidentified in mid-FY-1984 as a separate trackable entity entitled Core Sample Acquisition and Examination Project, which is not included here

Environmental Restoration and Waste Management Site-Specific Plan (SSP) for fiscal year 1992 (FY92)

International Nuclear Information System (INIS)

1991-09-01

The FY-92 Site-Specific Plan (FY-92 SSP) for environmental restoration and waste management at the Idaho National Engineering Laboratory (INEL) is designed to provide the reader with easy access to the status of environmental restoration and waste management activities at INEL. The first chapter provides background on INIEL's physical environment, site history and mission, and general information about the site and its facilities. In addition, this chapter discusses the inter-relationships between the Site Specific Plan, the Environmental Restoration and Waste Management Five-Year Plan, the environmental restoration and waste management prioritization systems, and the Activity Data Sheets (ADSs) for environmental restoration and waste management. This discussion should help readers understand what the SSP is and how it fits into the environmental restoration and waste management process at INEL. This understanding should provide the reader with a better context for understanding the discussions in the SSP as well as a better feel for how and what to comment on during the public comment period that will be held from the first of September through the end of October 1991

Characteristics of severely damaged fuel from PBF tests and the TMI-2 accident

International Nuclear Information System (INIS)

Osetek, D.J.; Cook, B.A.; Dallman, R.J.; Broughton, J.M.

1986-01-01

As a result of the TMI-2 reactor accident, the US Nuclear Regulatory Commission initiated a research program to investigate phenomena associated with severe fuel damage accidents. This program is sponsored by several countries and includes in-pile and out-of-pile experiments, separate effects studies, and computer code development. The principal in-pile testing portion of the program includes four integral severe fuel damage (SFD) tests in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory (INEL). The INEL is also responsible for examining the damaged core in the Three Mile Island-Unit 2 (TMI-2) reactor, which offers the unique opportunity to directly compare the findings of an experimental program to those of an actual reactor accident. The principal core damage phenomena which can occur during a severe accident are discussed, and examples from the INEL research programs are used to illustrate the characteristics of these phenomena. The preliminary results of the programs are presented, and their impact on plant operability during severe accidents is discussed

Special Analysis for the Disposal of the Idaho National Laboratory Unirradiated Light Water Breeder Reactor Rods and Pellets Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada

Energy Technology Data Exchange (ETDEWEB)

None

2014-08-31

The purpose of this special analysis (SA) is to determine if the Idaho National Laboratory (INL) Unirradiated Light Water Breeder Reactor (LWBR) Rods and Pellets waste stream (INEL103597TR2, Revision 2) is suitable for disposal by shallow land burial (SLB) at the Area 5 Radioactive Waste Management Site (RWMS). The INL Unirradiated LWBR Rods and Pellets waste stream consists of 24 containers with unirradiated fabricated rods and pellets composed of uranium oxide (UO2) and thorium oxide (ThO2) fuel in zirconium cladding. The INL Unirradiated LWBR Rods and Pellets waste stream requires an SA because the 229Th, 230Th, 232U, 233U, and 234U activity concentrations exceed the Nevada National Security Site (NNSS) Waste Acceptance Criteria (WAC) Action Levels.