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Transport of solid commodities via freight pipeline: impact assessment. Volume V. First year final report

Description: The application of freight pipeline for the movement of solid goods offers a new option in the field of transportation. This volume examines impacts and their assessments. This study has only identified the areas where truck and/or rail substitution by pipeline may have impacts. It only can be said that pipeline, if it can substitute for surface traffic without correspondingly increasing it at another location, is inherently a more environmentally compatible mode of transport. Based on data pre… more
Date: July 1, 1976
Creator: Zandi, I. & Gimm, K.K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Analytical Investigation of Certain Aspects of LMFBR Subassembly-Failure Propagation

Description: An analytical investigation of certain problems in the area of subassembly-to-subassembly failure propagation in LMFBR's is described. Existing analyses of the response of the adjacent subassembly duct to mechanical loads are reviewed and summarized, and major uncertainties are identified. Additional analyses of the response of the adjacent subassembly to certain thermal loads are presented in two parts. In the first part, the effect of an external heat flux on duct melting and thermal stresses… more
Date: February 1976
Creator: Marr, William W.; Wang, P. Y.; Misra, B.; Padilla, A. & Crawford, R. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

One-Dimensional Cladding-Relocation Model for Fast-Reactor Loss-of-Flow Accidents

Description: The motion and location of the molten-cladding during an unprotected loss-of-flow accident in liquid metal fast breeder reactors are important because of the effects on the reactivity and the subsequent fuel motion. The present study analyzes the cladding-relocation problem based on a single-channel film-flow model and a simple thermal transient model for fuel pins. The motion of molten cladding induced by sodium-vapor streaming undergoes initial rapid upward acceleration, slowing down, flow re… more
Date: March 1976
Creator: Ishii, M.; Chen, W. L. & Grolmes, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Investigation of the chemical explosion of an ion exchange resin column and resulting americium contamination of personnel in the 242-Z building, August 30, 1976

Description: As a result of an explosion in the Waste Treatment Facility, 242-Z Building, 200 West Area of the Hanford Reservation on August 30, 1976, the Manager of the Richland Operations Office (RL), Energy Research and Development Administration (ERDA), appointed an ERDA Committee to conduct a formal investigation and to prepare a report on their findings of this occurrence. The Committee was instructed to conduct the investigation in accordance with ERDAMC 0502, insofar as circumstances would permit, t… more
Date: October 19, 1976
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Experiments on the response of rigid and flexible reactor vessel models to a simulated hypothetical core disruptive accident. [LMFBR]

Description: A simulated HCDA loading was applied in simple, thick-walled and thin-walled, 1/30-scale models of a fast breeder reactor vessel. The loading and resulting vessel response were measured to verify the modeling techniques used in the REXCO computer code. The sodium coolant is simulated by water, and the HCDA load is simulated by the expansion of the detonation products of a low-density explosive detonated in the vessel core. The detonation products expand from an initial pressure of 3700 psi down… more
Date: November 1, 1976
Creator: Cagliostro, D.J. & Romander, C.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Life Stress and Industrial Accidents

Description: Traditional personality research on accident behavior has produced conflicting opinions as to the traits that describe the "accident-prone" personality type. Other research has shown that psychosocial life stress, while partially determining the temporal onset of a variety of illnesses, may also be a factor contributing to increased accident liability. This study examined the role of temporary and stress-producing life changes in groups of accident-free and accident-involved industrial employee… more
Date: May 1976
Creator: Huddleston, Charles T.
Item Type: Refine your search to only Thesis or Dissertation
Partner: UNT Libraries
open access

Economic incentives for improved geothermal drilling motors

Description: The ways that reliable high temperature drilling motors could reduce geothermal drilling are reviewed. These are: faster drilling, increased bit footage, improved drilling of fractured rock, improved directional drilling, reduced hole deviation, reduced blowouts, reduced casing wear, reduced keyseating, reduced twist-offs, improved milling operations, improved sidetracking, improved slim hole drilling, reduced mud problems, reduced lost circulation, reduced drillstring corrosion, reduced drills… more
Date: December 8, 1976
Creator: Maurer, W.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
captions transcript

[News Clip: Accident]

Description: Video footage from the KXAS-TV/NBC station in Fort Worth, Texas, to accompany a news story.
Date: December 30, 1976, 10:00 p.m.
Duration: 1 minute 42 seconds
Creator: KXAS-TV (Television station : Fort Worth, Tex.)
Item Type: Refine your search to only Video
Partner: UNT Libraries Special Collections
open access

Pseudo real-time imaging systems with nonredundant pinhole arrays. [LMFBR safety experiment diagnostics]

Description: Coded aperture techniques, because of their efficiency and three-dimensional information content, represent potentially powerful tools for LMFBR safety experiment diagnostics. These techniques should be even more powerful if the data can be interpreted in real time or in pseudo real time. For example, to satisfy the stated goals for LMFBR diagnostics (1-ms time resolution and 1-mm spatial resolution), it is conceivable that several hundred frames of coded data would be recorded. To unscramble a… more
Date: January 1, 1976
Creator: Han, K. S.; Berzins, G. J. & Roach, W. H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Survey of failure experience in existing superconducting magnet systems and its relevance to fusion power reactors

Description: Details of existing superconducting magnet failures are collected and evaluated with regard to future CTR superconducting magnet safety and reliability. Fourteen magnet systems with sixteen failures are presented. These failures are analyzed and categorized as to causative factors (e.g. hot spots, arcing, lead failures, and conductor movement). Responses of the instrumentation and protection systems during these accident situations are also presented. Repairs and present status of the magnets a… more
Date: August 17, 1976
Creator: Hsieh, S Y; Allinger, J; Danby, G; Keane, J; Powell, J & Prodell, A
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Pressure vessel fracture studies pertaining to a PWR LOCA-ECC thermal shock: experiments TSE-1 and TSE-2

Description: The LOCA-ECC Thermal Shock Program was established to investigate the potential for flaw propagation in pressurized-water reactor (PWR) vessels during injection of emergency core coolant following a loss-of-coolant accident. Studies thus far have included fracture mechanics analyses of typical PWRs, the design and construction of a thermal shock test facility, determination of material properties for test specimens, and two thermal shock experiments with 0.53-m-OD (21-in.) by 0.15-m-wall (6-in.… more
Date: September 1, 1976
Creator: Cheverton, R. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Disposal of coal preparation wastes: environmental considerations. [17 refs]

Description: The mineral wastes from coal preparation and mine development constitute a major environmental problem. Over 3-billion tons of these materials have accumulated in the U.S., and the current annual rate of waste production of 100 million tons/yr is expected to double within a decade. The total number of active and abandoned coal waste dumps is estimated to be between 3000 and 5000. About one-half of these pose some type of health, environmental, or safety problem. Structural weaknesses in coal re… more
Date: January 1, 1976
Creator: Wewerka, E. M.; Williams, J. M. & Vanderborgh, N. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Annotated bibliography of safety-related occurrences in pressurized-water nuclear power plants as reported in 1975

Description: The bibliography presented contains 100-word abstracts of reports to the U.S. Nuclear Regulatory Commission concerning operational events that occurred at pressurized-water reactor nuclear power plants in 1975. The report includes 1097 abstracts, arranged alphabetically by reactor name and then chronologically for each reactor, that describe incidents, failures, and design or construction deficiencies experienced at the facilities. Key-word and permuted-title indexes are provided to facilitate … more
Date: July 1, 1976
Creator: Scott, R. L. & Gallaher, R. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Physics of reactor safety. Quarterly report, April--June 1976. [LMFBR]

Description: Reports on reactor safety research and technical coordination of the RSR safety analysis program by members of the Reactor Safety Appraisals Group, Monte Carlo analysis of safety-related critical assembly experiments by members of the Theoretical Fast Reactor Physics Group, and planning of DEMO safety-related critical experiments by members of the Zero Power Reactor (ZPR) Planning and Experiments Group are presented.
Date: January 1, 1976
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

HTGR accident initiation and progression analysis status report. Volume VI. Event consequences and uncertainties demonstrating safety R and D importance of fission product transport mechanisms

Description: Five accident conditions are considered in an analysis of their radiological consequences. The five accident conditions are core heatup resulting from loss of offsite power and earthquake; reheater tube leak; slow depressurization; rapid depressurization; and steam ingress from steam generator main bundle tube rupture. Consequence assessments are presented in the form of radiological doses in rem to representative site boundaries of 500m and 2500m and man-rem doses to the surrounding environmen… more
Date: January 1, 1976
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

LARC-1: a Los Alamos release calculation program for fission product transport in HTGRs during the LOFC accident

Description: The theoretical and numerical data base development of the LARC-1 code is described. Four analytical models of fission product release from an HTGR core during the loss of forced circulation accident are developed. Effects of diffusion, adsorption and evaporation of the metallics and precursors are neglected in this first LARC model. Comparison of the analytic models indicates that the constant release-renormalized model is adequate to describe the processes involved. The numerical data base fo… more
Date: October 1, 1976
Creator: Carruthers, L. M. & Lee, C. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fusion reactor wastes

Description: The potential waste releases for commercial fusion power plants were estimated by use of standard environmental analysis procedures incorporating a high degree of speculation. The analytical procedure is presented. A description was obtained for each of the ten fusion power plant concepts currently being developed. These concepts were then analyzed to determine the general characteristics and probable waste releases. (MOW)
Date: September 1, 1976
Creator: Young, J R
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Containment and recovery system for fuel-reprocessing plants

Description: Tritium containment and removal problems in a fuel-reprocessing plant are identified and conceptual process designs for reducing emissions to the environment to below 1 Ci/day are studied. The conceptual design recommended would allow an air atmosphere in the reprocessing-plant hall and would use a continuous-catalytic-oxidizer/molecular-sieve-adsorber cleanup system to maintain a 40-..mu..Ci/m/sup 3/ tritium level (5 ..mu..Ci/m/sup 3/ HTO) against 180 Ci/day leakage from components and process… more
Date: August 25, 1976
Creator: Galloway, T. R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Thermal response of core and central-cavity components of a high-temperature gas-cooled reactor in the absence of forced convection coolant flow. [NATCON code]

Description: A means of determining the thermal responses of the core and the components of a high-temperature gas-cooled reactor after loss of forced coolant flow is discussed. A computer program, using a finite-difference technique, is presented together with a solution of the confined natural convection. The results obtained are reasonable and demonstrate that the computer program adequately represents the confined natural convection.
Date: September 1, 1976
Creator: Whaley, R. L. & Sanders, J. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Annotated bibliography of safety-related occurrences in boiling-water nuclear power plants as reported in 1975

Description: The bibliography presented contains 100-word abstracts of reports to the U.S. Nuclear Regulatory Commission concerning operational events that occurred at boiling-water reactor nuclear power plants in 1975. The report includes 1169 abstracts, arranged alphabetically by reactor name and then chronologically for each reactor, that describe incidents, failures, and design or construction deficiencies that were experienced at the facilities. Key-word and permuted-title indexes are provided to facil… more
Date: July 1, 1976
Creator: Scott, R. L. & Gallaher, R. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

HEATUP: a computer program for the thermal anaysis of a LOFC accident in an HTGR

Description: The HEATUP code, a modification of the general, time-dependent, one-, two-, and three-dimensional program HEATING5, was designed for the thermal analysis of a Loss of Forced Circulation accident in a High Temperature Gas-Cooled Reactor. This report contains a description of the computational model which includes: a description of the basic problem; a short review of preliminary results related to the choice of thermal properties, boundary conditions and initial conditions; a full description of… more
Date: November 1, 1976
Creator: Siman-Tov, I. I. & Turner, W. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

LOFT data acquisition and visual display system (DAVDS) presentation program

Description: The Data Acquisition and Visual Display System (DAVDS) at the Loss-of-Fluid Test Facility (LOFT) has 742 data channel recording capability of which 576 are recorded digitally. The purpose of this computer program is to graphically present the data acquired and/or processed by the LOFT DAVDS. This program takes specially created plot data buffers of up to 1024 words and generates time history plots on the system electrostatic printer-plotter. The data can be extracted from two system input devic… more
Date: March 1, 1976
Creator: Bullock, M. G. & Miyasaki, F. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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