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Water quality considerations - Project Travois

Description: The technical concept for Project Travois contains one simple analysis of the potential hazard of contaminating the Arrowrock Reservoir on the Boise River with some of the radionuclides produced. This previous analysis assumes homogeneous and prompt mixing of all the tritium and tungsten isotopes. This simple analysis is physically unrealistic sine there is no way of transporting all of these radionuclides to the reservoir, promptly. We shall in this paper reanalyze the contamination problem in such a way that we define the type of site geology and hydrology information that must be developed.
Date: July 1, 1968
Creator: Knox, J.B.
Partner: UNT Libraries Government Documents Department

Project Payette

Description: This is the concept for Project Payette, a nuclear event in the Seismic Detection Research Program. For this experiment, a nuclear explosive in the range of 5 to 10 kt will be detonated at a depth of 2000 to 3000 ft in an underground cavity of sufficient size that the walls of the cavity experience only elastic motion. The site will be located in a salt dome. Project Payette has been divided into three phases. Phase I will include site evaluation and engineering design of the construction of the cavity. It is estimated to require about 1 year. Phase II will include construction of the cavity and emplacement hole. It is estimated to require about 2 years. Phase III will include emplacement of instruments and the device, the detonation and the post-shot program including cavity re-entry. This is estimated to require about 1 year. The scope of this concept is intended to define Project Payette sufficiently will that Phase I work may proceed.
Date: August 1, 1966
Creator: Warner, D.
Partner: UNT Libraries Government Documents Department

Estimated long-term health effects

Description: Apart from the dramatic increase in thyroid cancer in those exposed as children, there is no evidence to date of a major public health impact of the radiation exposure from the Chernobyl accident in the three most affected countries. Although some increases in the frequency of cancer in exposed populations have been reported, these results are difficult to interpret, mainly because of differences in the intensity and method of follow-up between exposed populations and the general population to which they are compared. If the experience of atomic bomb survivors and of other exposed populations is applicable, the major radiological impact of the accident will be cancer and the total lifetime numbers of excess cancers will be greatest among the liquidators and among the residents of contaminated territories, of the order of 2,000 to 2,500. These increases would be difficult to detect epidemiologically against an expected background number of 41,500 and 433,000 respectively (size of the exposed populations: 200,000 and 3,700,000, respectively). It is noted, however, that the exposures received by populations exposed as a result of Chernobyl are different (in type and pattern) from those of atomic bomb survivors. Predictions derived from these populations are therefore uncertain. Indeed, the extent of the increase in thyroid cancer incidence in persons exposed as children was not foreseen. In addition, only ten years have passed since the accident. It is essential therefore that monitoring of the health of the population be continued in order to assess the public health impact of the accident, even if, apart from leukemia among liquidators, little detectable increase of cancers due to radiation from the Chernobyl accident is expected.
Date: April 1, 1996
Creator: Cardis, F.; Okeanov, A.E.; Likthariev, I.; Prisyazhniuk; Anspaugh, L.R.; Mabuchi, K. et al.
Partner: UNT Libraries Government Documents Department

Report of trip to YTS - C91 test projectile

Description: As a part of the RAIL feasibility study, Operation Dorothe (March 1961) was conducted to determine if a liquid explosive could survive the acceleration of launch from a 155 mm howitzer. This operation was successful, although some structural difficulty was experienced with the test round (C-90). Upon completion of that exercise, it was decided to design a test round that could be used with the more viscous slurry-type explosives, and to fire several of these new rounds with inert filler prior to their use with slurry High Explosives (H.E.), precluding the difficulty previously experienced. The C-91 projectile, is a modified M107 H.E. round. It has been reduced in weight, equipped with an obturator, and provided with a large fill orifice. The rotating band has been altered to eliminate rotation. Internally, a plastic plug is used to control column height. A piston-type `O` ring seal prevents gun gas from reaching the interior to the projectile. Four of these projectiles were fired from a 155 mm howitzer at 15,500 g`s, plus. They survived not only the launch, but also impact and repeated ricochet in sand, gravel, and small rock. No leakage of the inert filler (glycerin) occurred. All rounds were destroyed with explosives upon completion of the exercise. Test data and engineering drawings are provided.
Date: May 1, 1961
Creator: Mickel, L.
Partner: UNT Libraries Government Documents Department

Finite-element calculations of near-field transient horizontal temperature and thermal stress distributions for the Climax granite nuclear spent-fuel-storage experiment

Description: Calculations of near-canister temperature and thermal stress fields in a horizontal plane through a typical spent nuclear fuel canister in the Climax granite experiment are presented, assuming homogeneity of the rock mass. The methodology is described. Three different canister spacings were investigated. The resulting temperature and stress plots show that a row of canisters may be satisfactorily approximated by a distributed plane source for points of interest which are at greater distances from the row than the canister spacing. Further, the thermal tensile stress changes are trivial and very much less than the calculated residual horizontal geostatic compressive stresses. A listing of the mesh-generator input is given for use in additional analyses.
Date: March 1, 1980
Creator: Greenlaw, R.C.
Partner: UNT Libraries Government Documents Department

Stressmeter placement at spent fuel test in climax granite

Description: Vibrating wire stressmeters were installed in the Spent Fuel Facility at the Nevada Test Site. These stressmeters will measure the changes in in situ stress during the five-year spent fuel test. Before installation, laboratory tests were conducted to study reproducibility of placement and to develop a program hopefully to reduce corrosion of the stressmeters while in place at the Spent Fuel Facility. These laboratory tests are discussed along with the installation of the stressmeters at the Spent Fuel Facility.
Date: May 20, 1980
Creator: Abey, A.E. & Washington, H.R.
Partner: UNT Libraries Government Documents Department

Tory II-C performance as a function of flight mach number and inlet pressure recovery

Description: In a parameter study involving thrust vs. flight Mach number, M.D. Mintz has found that net jet thrust becomes a maximum at about Mach 3.66 if the Tory II-C design value of inlet pressure recovery is used at all Mach numbers. This is not a realistic situation, however, because the attainable pressure recovery decreases markedly with increasing Mach number. The effect of more realistic pressure recovery values are presented in this paper. Two sets of values were employed, which differ by two percent. Diffuser operation is always critical; i.e. we are using a ``rubber`` diffuser. Nozzle are has been optimized for each operating condition. Reactor parameters and nozzle area-thrust dependence information is also presented.
Date: January 1, 1963
Creator: Moyer, J. H.
Partner: UNT Libraries Government Documents Department

Preliminary evaluation of 30 potential granitic rock sites for a radioactive waste storage facility in southern Nevada

Description: Results of preliminary study are presented which was performed under subtask 2.7 of the NTS Terminal Waste Storage Program Plan for 1978. Subtask 2.7 examines the feasibility of locating a nuclear waste repository in a granitic stock or pluton in southern Nevada near the Nevada Test Site (NTS). It is assumed for the purposes of this study that such a repository cannot be located at NTS. This assumption may or may not be correct. This preliminary report does not identify a particular site as being a suitable location for a repository. Nor does it absolutely eliminate a particular site from further consideration. It does, however, answer the basic question of probable suitability of some of the sites and present a systematic method for site evaluation. Since the findings of this initial study have been favorable, it will be followed by more exhaustive and detailed studies of the original 30 sites and perhaps others. In future studies some of the evaluation criteria used in the preliminary study may be modified or eliminated, and new criteria may be introduced.
Date: February 15, 1978
Creator: Boardman, C.R. & Knutson, C.F.
Partner: UNT Libraries Government Documents Department

Waste isolation projects, FY 1977

Description: The technology and data base required to license a nuclear repository in a crystalline rock medium, located at or near the Nevada Test Site are being developed. The program consists of three related project areas: field and laboratory studies of the availability and migration of radionuclides in ground water; thermomechanical response of granite, through heater tests at the Climax stock of the Nevada Test Site; and laboratory measurements of physical properties of rocks at elevated temperatures and pressures, including physical/chemical factors that inhibit water transport in deep silicate rocks. Work accomplished in these areas is report. (LK)
Date: January 18, 1978
Creator: Ramspott, L.D. (ed.)
Partner: UNT Libraries Government Documents Department

Measuring the permeability of Eleana argillite from area 17, Nevada Test Site, using the transient method

Description: Using the transient method, we determine the permeability of high-quartz Eleana argillite from the Nevada Test Site as a function of effective pressure. By comparing calculated and observed pressure decay in the upstream reservoir, we have determined the permeability of intact and fractured specimens at effective pressures ranging from 1.0 to 24.0 MPa. Over this pressure range, Eleana argillite has a low permeability (10{sup -16} to 10{sup -19} cm{sup 2}) when intact and a higher permeability (10{sup -12} to 10{sup -17} cm{sup 2}) with one induced through-going fracture.
Date: December 11, 1978
Creator: Lin, W.
Partner: UNT Libraries Government Documents Department

Thermal analysis for a spent reactor fuel storage test in granite

Description: A test is conducted in which spent fuel assemblies from an operating commercial nuclear power reactor are emplaced in the Climax granite at the US Department of Energy`s Nevada Test Site. In this generic test, 11 canisters of spent PWR fuel are emplaced vertically along with 6 electrical simulator canisters on 3 m centers, 4 m below the floor of a storage drift which is 420 m below the surface. Two adjacent parallel drifts contain electrical heaters, operated to simulate (in the vicinity of the storage drift) the temperature fields of a large repository. This test, planned for up to five years duration, uses fairly young fuel (2.5 years out of core) so that the thermal peak will occur during the time frame of the test and will not exceed the peak that would not occur until about 40 years of storage had older fuel (5 to 15 years out of core) been used. This paper describes the calculational techniques and summarizes the results of a large number of thermal calculations used in the concept, basic design and final design of the spent fuel test. The results of the preliminary calculations show the effects of spacing and spent fuel age. Either radiation or convection is sufficient to make the drifts much better thermal conductors than the rock that was removed to create them. The combination of radiation and convection causes the drift surfaces to be nearly isothermal even though the heat source is below the floor. With a nominal ventilation rate of 2 m{sup 3}/s and an ambient rock temperature of 23{sup 0}C, the maximum calculated rock temperature (near the center of the heat source) is about 100{sup 0}C while the maximum air temperature in the drift is around 40{sup 0}C. This ventilation (1 m{sup 3}/s through the main drift ...
Date: September 1, 1980
Creator: Montan, D.N.
Partner: UNT Libraries Government Documents Department

Spent fuel handling system for a geologic storage test at the Nevada Test Site

Description: The Lawrence Livermore Laboratory is conducting a test of the geologic storage of encapsulated spent commercial reactor fuel assemblies in a granitic rock at the Nevada Test Site. The test, known as the Spent Fuel Test-Climax (SFT-C), is sponsored by the US Department of Energy, Nevada Operations Office. Eleven pressurized-water-reactor spent fuel assemblies are stored retrievably for three to five years in a linear array in the Climax stock at a depth of 420 m.
Date: May 1, 1980
Creator: Duncan, J.E.; House, P.A. & Wright, G.W.
Partner: UNT Libraries Government Documents Department

Program Plan: field radionuclide migration studies in Climax granite

Description: This Program Plan describes the field radionuclide migration studies we plan to conduct in the Climax granite at the Nevada Test Site. Laboratory support studies are included to help us understand the geochemical and hydrologic processes involved in the field. The Program Plan begins with background information (Section 1) on how this program fits into the National Waste Terminal Storage Program Plan and discusses the needs for field studies of this type. The objectives stated in Section 2 are in direct response to these needs, particularly the need to determine whether laboratory studies accurately reflect actual field conditions and the need for field testing to provide a data base for verification of hydrologic and mass transport models. The technical scope (Section 3) provides a work breakdown structure that integrates the various activities and establishes a base for the technical approach described in Section 4. Our approach combines an interactive system of field and laboratory migration experiments with the use of hydrologic models for pre-test predictions and data interpretation. Section 5 on program interfaces identifies how information will be transferred to other related DOE projects. A schedule of activities and major milestones (Section 6) and the budget necessary to meet the project objectives (Section 7) are included in the Program Plan. Sections 8 and 9 contain brief descriptions of how the technical and program controls will be established and maintained and an outline of our quality assurance program. This program plan is an initial planning document and provides a general description of activities. An Engineering Test Plan containing detailed experimental test plans, an instrumentation plan and equipment design drawings will be published as a separate document.
Date: November 1, 1980
Creator: Isherwood, D.; Raber, E.; Coles, D. & Stone, R.
Partner: UNT Libraries Government Documents Department

Progress report - bonding of DATB - progress report

Description: DATB (diaminotrinitrobenzine) pressings were made in an effort to find the most suitable binder. After successfully pressing ball milled DATB at 110 C,it was found that normal DATB (fine powder) could also be hot pressed at this temperature and 20,000 psi. Bulk density might vary from batch to batch.
Date: August 1, 1958
Creator: Archibald, P.
Partner: UNT Libraries Government Documents Department

Climax granite test results

Description: The Lawrence Livermore Laboratory (LLL), as part of the Nevada Nuclear Waste Storage Investigations (NNWSI) program, is carrying out in situ rock mechanics testing in the Climax granitic stock at the Nevada Test Site (NTS). This summary addresses only those field data taken to date that address thermomechanical modeling for a hard-rock repository. The results to be discussed include thermal measurements in a heater test that was conducted from October 1977 through July 1978, and stress and displacement measurements made during and after excavation of the canister storage drift for the Spent Fuel Test (SFT) in the Climax granite. Associated laboratory and field measurements are summarized. The rock temperature for a given applied heat load at a point in time and space can be adequately modeled with simple analytic calculations involving superposition and integration of numerous point source solutions. The input, for locations beyond about a meter from the source, can be a constant thermal conductivity and diffusivity. The value of thermal conductivity required to match the field data is as much as 25% different from laboratory-measured values. Therefore, unless we come to understand the mechanisms for this difference, a simple in situ test will be required to obtain a value for final repository design. Some sensitivity calculations have shown that the temperature field is about ten times more sensitive to conductivity than to diffusivity under the test conditions. The orthogonal array was designed to detect anisotropy. After considering all error sources, anisotropic efforts in the thermal field were less than 5 to 10%.
Date: January 15, 1980
Creator: Ramspott, L.D.
Partner: UNT Libraries Government Documents Department