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Basalt near-surface test facility test plans

Description: The NSTF is under construction at Gable Mountain for in-situ testing, which will be conducted in two phases: Phase I, using electric heaters to simulate nuclear waste canisters in order to study the thermomechanical response of basalt; and Phase II, using spent fuel canisters. The tests planned for Phases I and II are described. (DLC)
Date: June 1, 1979
Creator: Krug, A.D.
Partner: UNT Libraries Government Documents Department

Basalt waste isolation project. Quarterly report, April 1, 1981-June 30, 1981

Description: This document reports progress made in the Basalt Waste Isolation Project during the third quarter of fiscal year 1981. Efforts are described for the following programs of the project work breakdown structure: systems; waste package; site; repository; regulatory and institutional; test facilities; in situ test facilities.
Date: August 1, 1981
Creator: Deju, R.A.
Partner: UNT Libraries Government Documents Department

Basalt Waste Isolation Program. Quarterly report, April 1, 1979-June 30, 1979

Description: During the quarter, progress was made in all areas of the Basalt Waste Isolation Program. In the Geosciences, Hydrology, and Engineered Barriers areas, work continued on schedule aimed at being able to make a site selection decision in 1981, as scheduled. Emphasis continued to be placed on geologic mapping studies, on hydrologic data gathering, and on definition of waste/basalt interactions and needed engineered barriers. Progress at the end of the quarter on the Near-Surface Test Facility was approximately on schedule and the rate of work was accelerating to better than scheduled due to some equipment improvements and tunnel design modifications. In the Engineering Testing area, design work, test planning, and fabrication of heaters and auxiliary equipment continued on schedule. In the Repository area, an Architect/Engineer Evaluation Board was formally designed by the US Department of Energy-Headquarters during October 1978. The evaluation board will select an architect/engineer for repository conceptual design with an option for follow-on Title I, Title II, and Title III engineering services. Selection will be completed by October 1979. Questionnaire information was received from a number of interested architect/engineer firms by the US Department of Energy-Richland Operations Office and has been evaluated. Onsite visits with the qualified firms were completed during April 1979. In addition, repository preconceptual design studies continued on schedule with emphasis on compilation of repository functional design criteria by July 1979, and the repository preconceptual design report in September 1979.
Date: July 1, 1979
Creator: Deju, R.A.
Partner: UNT Libraries Government Documents Department

Basalt waste isolation project. Quarterly report, October 1, 1980-December 31, 1980

Description: In September 1977, the National Waste Terminal Storage Program was restructured to support investigations of two US DOE sites - Hanford and Nevada. The Basalt Waste Isolation Project within Rockwell Hanford Operations has been chartered with the responsibility of conducting these investigations. The overall Basalt Waste Isolation Project is divided into the following principal work areas: systems integration, geosciences, hydrology, engineered barriers, near-surface test facility, engineering testing, and repository studies. Summaries of major accomplishments for each of these areas are reported in this document.
Date: February 1, 1981
Creator: Deju, R.A.
Partner: UNT Libraries Government Documents Department

Basalt Waste Isolation Project. Quarterly report, July 1, 1979-September 30, 1979

Description: Progress in various areas of the Basalt Waste Isolation Project during the last quarter is reported. Systems integration, licensing, geologic activities, hydrology, borehole studies, geophysical logging, engineered barriers, test facilities, testing of canisters, and selection process for architect-engineer services for repository conceptual design are discussed. (DC)
Date: October 1, 1979
Creator: Deju, R.A.
Partner: UNT Libraries Government Documents Department

Basalt stratigraphy - Pasco Basin

Description: The geologic history of the Pasco Basin is sketched. Study of the stratigraphy of the area involved a number of techniques including major-element chemistry, paleomagnetic investigations, borehole logging, and other geophysical survey methods. Grande Ronde basalt accumulation in the Pasco Basin is described. An illustrative log response is shown. 1 figure. (RWR)
Date: October 1, 1979
Creator: Waters, A.C.; Myers, C.W.; Brown, D.J. & Ledgerwood, R.K.
Partner: UNT Libraries Government Documents Department

Nuclear waste repository in basalt: preconceptual design guidelines

Description: The development of the basalt waste isolation program parallels the growing need for permanent, environmentally safe, and secure means to store nuclear wastes. The repository will be located within the Columbia Plateau basalt formations where these ends can be met and radiological waste can be stored. These wastes will be stored such that the wastes may be retrieved from storage for a period after placement. After the retrieval period, the storage locations will be prepared for terminal storage. The terminal storage requirements will include decommissioning provisions. The facility boundaries will encompass no more than several square miles of land which will be above a subsurface area where the geologic makeup is primarily deep basaltic rock. The repository will receive, from an encapsulation site(s), nuclear waste in the form of canisters (not more than 18.5 feet x 16 inches in diameter) and containers (55-gallon drums). Canisters will contain spent fuel (after an interim 5-year storage period), solidified high-level wastes (HLW), or intermediate-level wastes (ILW). The containers (drums) will package the low-level transuranic wastes (LL-TRU). The storage capacity of the repository will be expanded in a time-phased program which will require that subsurface development (repository expansion) be conducted concurrently with waste storage operations. The repository will be designed to store the nuclear waste generated within the predictable future and to allow for reasonable expansion. The development and assurance of safe waste isolation is of paramount importance. All activities will be dedicated to the protection of public health and the environment. The repository will be licensed by the US Nuclear Regulatory Commission (NRC). Extensive efforts will be made to assure selection of a suitable site which will provide adequate isolation.
Date: June 1, 1979
Partner: UNT Libraries Government Documents Department

Basalt Waste Isolation Project. Drilling and testing quarterly report, January 1, 1983-March 31, 1983

Description: This document is a summary of dilling and testing results during the first calendar quarter (January through March 1983). The principal work during this period included the drilling and/or testing of boreholes RRL-2, RRL-6, RRL-14, DC-4/DC-5, DC-16A, DC-16B, and the McGee Well. Specific highlights of this work are summarized.
Date: April 1, 1983
Partner: UNT Libraries Government Documents Department

Site identification presentation: Basalt Waste Isolation Project

Description: The final step in the site identification process for the Basalt Waste Isolation Project is described. The candidate sites are identified. The site identification methodology is presented. The general objectives which must be met in selecting the final site are listed. Considerations used in the screening process are also listed. Summary tables of the guidelines used are included. (DMC)
Date: November 1, 1979
Partner: UNT Libraries Government Documents Department

Cover-gas seal program. Test report - sodium dip-seal wetting study. [at 450/sup 0/F]

Description: This report documents the tests conducted to find a reliable surface preparation method of treating the CRBRP dip seal blade (SA508 Class 2 steel) to insure its sodium wettability at 450F or less. Two techniques were established which depressed the sodium wetting temperature of SA 508, Class 2 dip seal blade material to 375F. These techniques were depositing an approx. 60 x 10/sup -6/ inch layer of tin on the blade surface by a brush-on plating process, and, by cleaning the blade surface with ultrasonics while it is immersed in sodium. The tin plating technique is recommended as the initial and primary surface preparation method and ultrasonics as a rewetting and backup technique. This work was conducted in support of the Sodium Dip Seal Feature Test, DRS 32.05.
Date: October 20, 1977
Creator: Carnevali, R.
Partner: UNT Libraries Government Documents Department

Cover-gas-seal component development: dynamic inflatable-plug seal improvement

Description: This report documents the 1) radial compliance and 2) low friction coating tests conducted on the CRBRP Rotating Plug Inflatable Seals per test plan N707TR810014. Test results show that narrowing the seal blade from 0.25 to 0.12 in. will effectively reduce dynamic drag from 30 to 20 lb/ft under nominal conditions and will increase seal radial compliance from 0.12 to 0.30 in. without an unacceptable rise in dynamic drag. Tests also demonstrated that application of a teflon coating to the seal wear surface reduced breakaway drag by 25% based on results of comparison dwells.
Date: September 15, 1977
Creator: Horton, P.H.
Partner: UNT Libraries Government Documents Department

Capsule calorimeter development report

Description: A capsule calorimeter has been designed, fabricated, and tested that is capable of measuring the rate of thermal energy generation of a capsule source with an accuracy of plus or minus five percent over a range of 300 watts to 1,000 watts of power. Three operating modes were investigated. The rate of temperature rise mode of operation was found to be the superior operating mode based on accuracy, time cycle, and simplicity of operation. This mode of operation is recommended for use in the encapsulation plant for performing calorimetric determinations on the strontium and cesium capsules that will be produced in the plant. The heat generation data collected by calorimetry will be used for isotopic assay of the capsule sources. The capsule calorimeter is specifically designed for installation into a remotely operated hot cell.
Date: October 2, 1972
Creator: Hall, J.C.
Partner: UNT Libraries Government Documents Department

Acceptance-test specifications for Test Number Four: process sensor and display test. [LMFBR]

Description: This document provides the general instructions for performing acceptance Test Number Four as indicated in the Acceptance Test Index (TI-022-130-003). Also indicated are the plant conditions and special equipment required to conduct the test. The acceptance criteria for each portion of the test are specified.
Date: May 9, 1975
Creator: Bell, C.R.
Partner: UNT Libraries Government Documents Department

Basalt Waste Isolation Project. Annual report, fiscal year 1979

Description: This project is aimed at examining the feasibility and providing the technology to design and construct a radwaste repository in basalt formations beneath and within the Hanford Site. The project is divided into seven areas: systems integration, geosciences, hydrologic studies, engineered barriers, near-surface test facility, engineering testing, and repository engineering. This annual report summarizes key investigations in these seven areas. (DLC)
Date: November 1, 1979
Partner: UNT Libraries Government Documents Department

AI-MSG modification work plan. [LMFBR]

Description: This document contains the Work Plan for the modification of the AI Steam Generator for tests in Large Leak Test Rig. This Work Plan describes the objectives, scope of work, schedule and manpower, end items, and meetings and reports required for the modification.
Date: August 20, 1973
Creator: Page, J.P.
Partner: UNT Libraries Government Documents Department

MAGNUM-2D computer code: user's guide

Description: Information relevant to the general use of the MAGNUM-2D computer code is presented. This computer code was developed for the purpose of modeling (i.e., simulating) the thermal and hydraulic conditions in the vicinity of a waste package emplaced in a deep geologic repository. The MAGNUM-2D computer computes (1) the temperature field surrounding the waste package as a function of the heat generation rate of the nuclear waste and thermal properties of the basalt and (2) the hydraulic head distribution and associated groundwater flow fields as a function of the temperature gradients and hydraulic properties of the basalt. MAGNUM-2D is a two-dimensional numerical model for transient or steady-state analysis of coupled heat transfer and groundwater flow in a fractured porous medium. The governing equations consist of a set of coupled, quasi-linear partial differential equations that are solved using a Galerkin finite-element technique. A Newton-Raphson algorithm is embedded in the Galerkin functional to formulate the problem in terms of the incremental changes in the dependent variables. Both triangular and quadrilateral finite elements are used to represent the continuum portions of the spatial domain. Line elements may be used to represent discrete conduits. 18 refs., 4 figs., 1 tab.
Date: January 1, 1985
Creator: England, R.L.; Kline, N.W.; Ekblad, K.J. & Baca, R.G.
Partner: UNT Libraries Government Documents Department

Field nondestructive assay measurements as applied to process inventories

Description: An annual process equipment holdup inventory measurement program for a plutonium processing plant was instituted by Rockwell Hanford Operations (Rockwell) at Richland, Washington. The inventories, performed in 1977 and 1978, were designed to improve plutonium accountability and control. The inventory method used field nondestructive assay (NDA) measurement techniques with portable electronics and sodium iodide detectors. Access to and movement of plutonium in work areas was curtailed during the inventory process using administrative controls. Comparison of the two annual inventories showed good reproducibility of results within the calculated error ranges. For items where no plutonium movement occurred and which contained greater than 20 grams plutonium, the average measurement difference between the two inventories was 22%. The procedures and equipment used and the operational experience from the inventories are described.
Date: August 1, 1979
Creator: Westsik, G.A.
Partner: UNT Libraries Government Documents Department

First-year evaluation of low-level waste-management stabilization techniques

Description: The first year of observation for effectiveness of biobarriers and herbicides in revegetation efforts demonstrated that certain practices will result in successful site stabilization: proper orientation of burial trench to reduce erosion; utilization of mulches to conserve moisture; seeding mixed perennial or annual grass species at the proper time for optimization of establishment and growth; and applying 2,4-D amine/Dicamba selective herbicide at the optimum time for enhancement of disirable grasses and reduction of competition from other species. The ultimate success or failure of a revegetation operation depends in part on the availability of equipment and manpower, weather conditions, and engineering feasibility. The data indicated that perennial grasses offered advantages over annual grasses and that the 2,4-D amine/Dicamba herbicide spray program was successful and should be expanded for next year. However, programmatic decisions should not be based on the data for 1 year, but should be based on data gathered over the full 3 years of the project.
Date: December 1, 1981
Creator: Cox, G.R.
Partner: UNT Libraries Government Documents Department

Interim report on cold trap alternatives, sodium technology

Description: This is an interim report on the modifications which are being made to an existing sodium loop so that a new method of removing hydrogen from sodium can be evaluated in a flowing sodium system. Some preliminary results on the performance of this type of cold trap alternative in a static sodium system are reported. Some tentative reactor design parameters for this type of getter device are presented based on the static test results. The life of such a unit is calculated to be substantially greater than that of a cold trap of equal volume.
Date: September 18, 1978
Creator: Hill, E.F.
Partner: UNT Libraries Government Documents Department

Functional design criteria additional high-level waste handling and storage facilities

Description: Four one-million-gallon underground tanks will be constructed for safe and reliable containment and storage of high-level radioactive wastes. Transfer facilities and encased, insulated, and heat traced piping will provide transport connections to the existing evaporator-crystallizer and storage tank systems. Flushing facilities and associated utilities will be provided for tank farm operation. The tank, pumping, and ventilation equipment and controls will be provided with instrumentation and alarms. Instrumentation will monitor the waste and facilities to detect high temperatures, waste levels, radiation, and process leakages. Gaseous radioactive containment will be provided by the high efficiency ventilation filtration. The tank farm facilities will provide personnel radiation protection.
Date: March 1, 1976
Creator: Tanaka, K.H.
Partner: UNT Libraries Government Documents Department