Resource Type
Serial/Series Title
GJBX
475
United States Department of Energy Grand Junction Office Reports
332
Atomic Energy Commission Reports
155
Argonne National Laboratory Reports
87
United States Geological Survey Reports
48
Water Resources Investigations Reports
44
NUREG/CR
34
Nuclear Regulatory Commission Reports
34
Minnesota Project
22
Aerial Radiometric and Magnetic Reconnaissance Survey of Portions of Arkansas, Illinois, Indiana, Kentucky, Missouri, and Tennessee, Dyersburg, Paducah, Poplar Bluff, and Rolla Quadrangles
20
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Construction of a Large Transverse Electromagnetic Cell
Report issued by the U.S. National Bureau of Standards discussing the construction of large electromagnetic cells. As stated in the introduction, "this instruction provides information and procedures necessary to fabricate a large transverse electromagnetic (TEM) cell to be used for experimental "electromagnetic interference" (EMI) evaluation studies" (p. 1). This report includes illustrations, and photographs.
Date:
February 1979
Creator:
Decker, W. F. & Wilson, W. A.
Object Type:
Report
System:
The UNT Digital Library
Unavailability Modeling and Analysis of Redundant Safety Systems
Analytical expressions have been developed to estimate the average unavailability of an m-out-of-n (m/n, 1 less than or equal to m less than or equal to n less than or equal to 4) standby safety system of a nuclear power plant. The expressions take into account contributions made by testing, repair, equipment failure, human error, and different testing schemes. A computer code, ICARUS, has been written to incorporate these analytical equations. The code is capable of calculating the average unavailability, optimum test interval, and relative contributions of testing, repair, and random failures for any of three testing schemes. After verification of the methodology and coding in ICARUS, a typical auxiliary feed-water system of a nuclear power plant was analyzed. The results show that the failure modes associated with testing and true demands contribute considerably to the unavailability and that diesel generators are the most critical components contributing to the overall unavailability of the system.
Date:
October 1979
Creator:
Argonne National Laboratory. Reactor Analysis and Safety Division.
Object Type:
Report
System:
The UNT Digital Library
A Quasi-Eulerian Method for Analyzing Slug Impact and Coolant Spillage in a Fast-Reactor Accident
This report describes a quasi-Eulerian method which has been incorporated into the ICECO code to study slug impact and coolant spillage problems in a fast-reactor accident. The quasi-Eulerian cells used in this method are located on the tops of the regular cells. The axial size of the quasi-Eulerian cells varies according to the gap generated at the reactor head-wall junction. Penetration holes on the cover head are modeled on the top center of the quasi-Eulerian cells. Fluid variables in these quasi-Eulerian cells also satisfy all the conservation equations. Since the boundary pressures above the quasi-Eulerian cells are determined by the movement of the moving grid, the velocity of the cover head is also included in the pressure iteration. Several examples are given to compare the results obtained by this quasi-Eulerian method with the existing experimental excursion data, as well as with the analytical and the other code solutions.
Date:
December 1979
Creator:
Chu, Han Y.
Object Type:
Report
System:
The UNT Digital Library
LIMBO Computer Code for Analyzing Coolant-Voiding Dynamics in LMFBR Safety Tests
The LIMBO (liquid metal boiling) code for the analysis of two-phase flow phenomena in an LMFBR reactor coolant channel is presented. The code uses a non-equilibrium, annular, two-phase flow model, which allows for slip between the phases. Furthermore, the model is intended to be valid for both quasi-steady boiling and rapid coolant voiding of the channel. The code was developed primarily for the prediction of, and the posttest analysis of, coolant-voiding behavior in the SLSF P-series in-pile safety test experiments. The program was conceived to be simple, efficient, and easy to use. It is particularly suited for parametric studies requiring many computer runs and for the evaluation of the effects of model or correlation changes that require modification of the computer program. The LIMBO code, of course, lacks the sophistication and model detail of the reactor safety codes, such as SAS, and is therefore intended to compliment these safety codes.
Date:
October 1979
Creator:
Bordner, G. L.
Object Type:
Report
System:
The UNT Digital Library
Effects of Environment on the Low-Cycle Fatigue Behavior of Type 304 Stainless Steel
The low-cycle fatigue behavior of Type 304 stainless steel has been investigated at 593 degrees C in a dynamic vacuum of better than 1.3 x 10⁻⁶ Pa (10⁻⁸ torr). The results concerning the effects of strain range, strain rate and tensile hold time on fatigue life are presented and compared with results of similar tests performed in air and sodium environments. Under continuous symmetrical cycling, fatigue life is significantly longer in vacuum than in air; in the low strain range regime, the effect of sodium on fatigue life appears to be similar to that of vacuum. Strain rate (or frequency) strongly influences fatigue life in both air and vacuum. In compressive hold-time tests, the effect of environment on life is similar to that in a continuous-cycling test. However, tensile hold times are nearly as damaging in vacuum as in air. Thus, at least for austenitic stainless steels, the influence of the environment of fatigue life appears to depend on the loading waveshape.
Date:
December 1979
Creator:
Argonne National Laboratory. Materials Science Division.
Object Type:
Report
System:
The UNT Digital Library
New Radionuclide Generator Systems for Use in Nuclear Medicine
A current emphasis in nuclear medicine is to better match the physical lifetime of the radionuclides used in vivo for diagnosis and treatment to the biological lifetime of the diagnostic procedure or to minimize radiation dose to areas other than those to be treated. In many cases the biological lifetime is on the order of minutes. Since the direct production of radionuclides with half lives of minutes requires the user to be near a suitable reactor or accelerator, this study was undertaken to produce short-lived radionuclides indirectly. If a long-lived radionuclide decays into a short-lived radionuclide, quick separation of the daughter activity from the parent enables the user to have a short-lived daughter while freeing him from the constraint of proximity to a cyclotron. Systems where a short-lived daughter is separated from a long-lived parent are called radionuclide generators. Two generator systems were developed for use in nuclear medicine, one in diagnostic work and the other for therapeutic work. The yield and breakthrough characteristics were within the limits required to minimize unnecessary radiation exposure in patients. Two parent radionuclides were produced using the beams available from medium energy cyclotrons. The yield was high enough to produce generators that would be …
Date:
1979
Creator:
Atcher, Robert Whitehill
Object Type:
Report
System:
The UNT Digital Library
Sodium Hydride Precipitation in Sodium Cold Traps
A series of experiments have been performed to test a calculational model for precipitation of NaH in sodium cold traps. The calculational model, called ACTMODEL, is a computer simulation that uses the system geometry and operating conditions as input to calculate a mass-transfer coefficient and the distribution of NaH in a cold trap. The ACTMODEL was tested using an analytical cold trap (ACT) that is simple and essentially one-dimensional. The ACT flow and temperature profile can be controlled at any desired condition. The ACT was analyzed destructively after each test to measure the actual NaH distribution. Excellent agreement was obtained between the ACTMODEL simulations and the experiments. Mass-transfer coefficients ranging upward from 6 x 10/sup -5/ m/s were measured in both packless and packed traps. As much as a fourfold increase in precipitation surface area was observed with increasing amount of NaH deposited.
Date:
1979?
Creator:
Argonne National Laboratory. Chemical Engineering Division.
Object Type:
Report
System:
The UNT Digital Library
Design of a System using CPC Collectors to Collect Solar Energy and to Produce Industrial Process Steam
A system has been designed to use CPC collectors to collect solar energy and to generate steam for industrial process heat purposes. The system is divided into two loops with the collectors in the collector loop to operate a pre-heater and the collectors in the boiler loop to heat water to elevated pressures and temperatures. A flash boiler is used to throttle the heated water to steam. Two types of CPC collectors are chosen. In the collector loop the CPC collectors are fitted with concentric tube receivers. In the boiler loop the collectors employ heat pipes to transmit heat. This design is able to alleviate the scaling and plumbing problems. A fragile receiver tube can also be employed without rupture difficulties. The thermal processes in the collectors were analyzed using a computer modeling. The results were also used to develop a thermodynamic analysis of the total system. Calculations show that the design is technically feasible. The CPC collector is shown to have an efficiency that is very weakly dependent on its operating temperatures, which makes the collector particularly attractive in high temperature applications.
Date:
August 1979
Creator:
Argonne National Laboratory. Solar Energy Group.
Object Type:
Report
System:
The UNT Digital Library
Nondestructive Evaluation Techniques for Silicon Carbide Heat-Exchanger Tubes : Second Annual Report, October 1978-September 1979
This report discusses the development of ultrasonic testing, acoustic microscopy, dye-enhanced radiography, holographic interferometry, and infrared scanning techniques for flaw detection in silicon carbide (SiC) heat-exchanger tubing. Both preservice and in-service testing requirements are discussed. An ultrasonic boreside probe and an acoustic microscope stage have been designed for continuous monitoring of SiC tubing. Preliminary results with these acoustic systems are presented. In addition, a novel technique for detecting small surface flaws using holographic interferometry is discussed. Fracture mechanics analysis suggests that detection of flaws on the order of 100 um is necessary to assure good reliability of ceramic heat exchangers. The acoustic and holographic techniques have been shown to be capable of detecting flaws of this size. However, the sensitivity of ultrasonic flaw detection in SiC is affected by the microstructure of the component. The practical considerations involved in the use of these techniques are discussed.
Date:
November 1979
Creator:
Kupperman, D. S.; Yuhas, D.; Deininger, W. & Sciammarella, Cesar A.
Object Type:
Report
System:
The UNT Digital Library
Finite-Element Method for Above-Core Structures
Three-dimensional finite-element models for the treatment of the nonlinear, transient response of a fast breeder reactor's above-core structures are described. For purposes of treating arbitrarily large rotations, node orientations are described by unit vectors and the deformable elements are treated by a corotational formulation in which the coordinate system is embedded in the elements. Deformable elements may be connected either to nodes directly or through rigid bodies. The time integration is carried out by the Newmark beta method. These features have been incorporated to form the finite-element program SAFE/RAS (Safety Analysis by Finite Elements/Reactor Analysis and Safety Division). Computations are presented for semianalytical comparisons, simple scoping studies, and Stanford Research Institute (SRI) test comparisons.
Date:
December 1979
Creator:
Kennedy, J. M. & Belytschko, Ted B.
Object Type:
Report
System:
The UNT Digital Library
Radiological and Environmental Research Division Annual Report: Part 1, Fundamental Molecular Physics and Chemistry, October 1978-September 1979
Annual report of the Argonne National Laboratory Radiological and Environmental Research Division regarding activities related to molecular physics and chemistry. This report summarizes work on the chemical physics of atoms and molecules, especially their interaction with external agents such as photons and electrons.
Date:
1979?
Creator:
Argonne National Laboratory. Radiological and Environmental Research Division.
Object Type:
Report
System:
The UNT Digital Library
Radiological and Environmental Research Division Annual Report: Part 2, Center for Human Radiobiology, July 1978-June 1979
Annual report of the Argonne National Laboratory Radiological and Environmental Research Division regarding activities related to the Center for Human Radiobiology. This report discusses studies on radium dial painters and other persons with industrial or medical exposure to intake of radium.
Date:
1979?
Creator:
Argonne National Laboratory. Radiological and Environmental Research Division.
Object Type:
Report
System:
The UNT Digital Library
Radiological and Environmental Research Division Annual Report: Part 3, Ecology, January-December 1979
TAnnual report of the Argonne National Laboratory Radiological and Environmental Research Division regarding activities related to ecology.
Date:
1979?
Creator:
Argonne National Laboratory. Radiological and Environmental Research Division.
Object Type:
Report
System:
The UNT Digital Library
Radiological and Environmental Research Division Annual Report: Part 4, Atmospheric Physics, January-December 1979
Annual report of the Argonne National Laboratory Radiological and Environmental Research Division regarding activities related to atmospheric physics. This report discusses programs involving air pollutants, and the dry deposition of airborne particles and trace gases.
Date:
1979?
Creator:
Argonne National Laboratory. Radiological and Environmental Research Division.
Object Type:
Report
System:
The UNT Digital Library
Fuel Cycle Programs, Quarterly Progress Report: July-September 1979
Quarterly report of the Argonne National Laboratory Chemical Engineering Division regarding activities related to properties and handling of radioactive materials, operation of nuclear reactors, and other relevant research.
Date:
1979
Creator:
Steindler, M. J.; Couture, R. A.; Flynn, K. F.; Jardine, L. J.; Mecham, W. J.; Seitz, M. G. et al.
Object Type:
Report
System:
The UNT Digital Library
Physics Division Annual Review: 1 April 1979 -31 March 1980
The Physics Division's program in nuclear physics covers a broad span of activities within that discipline. The object of this research is to understand the properties of atomic nuclei, their structure and the mechanisms of nuclear reactions. Work is carried out under a variety of subprograis: theory, heavy-ion physics, medium-energy physics and nuclear research.
Date:
1979?
Creator:
Schiffer, John P.
Object Type:
Report
System:
The UNT Digital Library
Materials Technology for Coal-Conversion Processes Quarterly Report: April-June 1979
Quarterly report on the activities of the Argonne National Laboratory Materials Science Division regarding economical conversion of coal into clean and usable fuels through the use of durable materials systems. This project is designed to provide part of the materials information necessary for successful operation of coal-conversion systems.
Date:
November 1979
Creator:
Argonne National Laboratory. Materials Science Division.
Object Type:
Report
System:
The UNT Digital Library
Materials Technology for Coal-Conversion Processes Nineteenth Report July-December 1979
Analysis of refractories exposed to slag attack during the last 500-h test run shows that complex spinels formed at the slag-refractories.
Date:
1979
Creator:
Argonne National Laboratory. Materials Science Division.
Object Type:
Report
System:
The UNT Digital Library
An Analytical Study of the Feasibility of Irradiating U233/Th232 Metal Fuel Experiments in EBR-II
Recent concerns about the proliferation and diversion of plutonium have lead to reconsideration of Uranium-233/Thorium-232 fuel cycles. Although thorium fuels have been studied earlier, much of that work is incomplete; consequently, additional irradiation studies will be necessary.
Date:
1979?
Creator:
Foltman, A. J. & Meneghetti, D.
Object Type:
Report
System:
The UNT Digital Library
Migration of Uranium Process Wastes from the Uranium-233--Thorium-232 Cycle
With the advent of fuel loadings of uranium-233 in the Shippingport Reactor, it has become important to understand the migratory behavior of uranium. The purpose of this study is the determination of the parameters influencing the migration of uranium(VI), the most likely chemical form of uranium to be mobilized from a repository. Samples of rhyolite tuff were used to measure the absorption coefficients of solutions of uranium (VI) in ground waters. In addition, columns of tuff were used to measure the elution behavior of uranium (VI) at various conditions of pH, uranium (VI) concentration, and flow saturation. These results indicate that there are several elution peaks with values of Kd between 35 and 120. This behavior is not the same as that of Plutonium(VI) on tuff; and the experimental results to date have not revealed the reason for this difference. Values of Kd in this range imply that geological containment would be difficult in strata of this type. It may be possible to find more retentive strata than tuff. Rocks containing reducing components are the most likely candidates and further investigation is urgently needed if the uranium-233-thorium cycle is to be widely used.
Date:
1979?
Creator:
Fried, Sherman; Sabau, Carmen; Hines, John & Friedman, Arnold
Object Type:
Report
System:
The UNT Digital Library
Development of a MK-II Loop to Simulate Reactor Hydraulic Conditions
The Mk-IIC Integral Loop was modified to provide an in-pile experimental apparatus that would simulate the subassembly coolant flow rate and inlet pressure head of the Fast Test Reactor (FTR). There were two main design changes. First, the safety dump tanks were removed from the Mk-IIC loop and replaced by a second annular linear induction pump (ALIP). Second, a flow restricting orifice was sized so that the hydraulic requirements of prototypical test-section coolant velocity and pressure head would be achieved. The resulting redesigned loop was used for the in-pile TREAT transient over-power Test H6, which investigated fuel sweep-out and coolability following fuel-pin failure under hydraulic conditions typical of the FTR. The procedure reported here will help in the design of advanced TREAT vehicles such as the Mk-III loop.
Date:
January 1979
Creator:
Page, R. J. & Robinson, L. E.
Object Type:
Report
System:
The UNT Digital Library
HYCSOS : A Chemical Heat Pump and Energy Conversion System Based on Metal Hydrides
The current status of the HYCSOS chemical heat pump and energy conversion system based on metal hydrides is described. Heat transfer fluid loops were insulated and modified for isothermal operation. Software development for HYCSOS manual mode operation was completed. Routines to handle data acquisition, logging, compression, correction and plotting, using a Tektronix Graphics system with flexible disk data storage, provide a rapid and versatile means of presenting HYCSOS data for analysis. Advanced concept heat exchangers to improve the heat transfer of the hydride bed with the heat transfer fluid are discussed. Preliminary tests made with a LaNi5 loaded aluminum foam test unit showed that heat transfer properties are very markedly improved. Thermodynamic expressions are applied to the selection of alloys for use in HYCSOS. The substitution of aluminum for nickel in AB5 type alloys is shown to reduce hysteresis and permits the use of potentially lower cost materials with added flexibility for the optimization of engineering design and performance characteristics of the hydride heat pump system. Transient thermal measurements on hydride beds of CaNi5 and LaNi5 show no deterioration with cycling. Relatively slow heat transfer between the hydride beds and heat transfer fluid in the coiled tube heat exchangers is …
Date:
April 1979
Creator:
Sheft, Irving; Gruen, Dieter M. & Lamich, George
Object Type:
Report
System:
The UNT Digital Library
Evaluating Computer Program Performance on the CRAY-1
The Advanced Scientific Computers Project of Argonne's Applied Mathematics Division has two objectives: to evaluate supercomputers and to determine their effect on Argonne's computing workload. Initial efforts have focused on the CRAY-1, which is the only advanced computer currently available. Users from seven Argonne divisions executed test programs on the CRAY and made performance comparisons with the IBM 370/195 at Argonne. This report describes these experiences and discusses various techniques for improving run times on the CRAY. Direct translations of code from scalar to vector processor reduced running times as much as two-fold, and this reduction will become more pronounced as the CRAY compiler is developed. Further improvement (two- to ten-fold) was realized by making minor code changes to facilitate compiler recognition of the parallel and vector structure within the programs. Finally, extensive rewriting of the FORTRAN code structure reduced execution times dramatically, in three cases by a factor of more than 20; and even greater reduction should be possible by changing algorithms within a production code. It is concluded that the CRAY-1 would be of great benefit to Argonne researchers. Existing codes could be modified with relative ease to run significantly faster than on the 370/195. More important, the …
Date:
January 1979
Creator:
Rudsinski, Larry & Pieper, Gail W.
Object Type:
Report
System:
The UNT Digital Library
The Status and Development Potential of Plate-Type Fuels for Research and Test Reactors
A program of transient in-reactor experiments is being conducted by Argonne National Laboratory in the Transient Reactor Test (TREAT) facility to guide and support analyses of hypothetical core-disruptive accidents (HCDA) in liquid-metal fast breeder reactors (LMFBR). Test results provide data needed to establish the response of LMFBR cores to hypothetical accidents producing fuel failure, coolant boiling, and the movement of coolant, molten fuel, and molten cladding. These data include margins to fuel failure, the modes of failure and movements, and evidence for identification of the mechanisms which determine the failure and movements. A key element in the program is the fast-neutron hodoscope, which detects fuel movement as a function of time during experiments.
Date:
March 1979
Creator:
Stahl, D.
Object Type:
Report
System:
The UNT Digital Library