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Investigation of Reactivity Anomalies in EBR-II
A data-collection and advisory team was formed to investigate observations of power reactivity decrement (PRD) and reactivity loss rate (RLR) obtained during EBR-II reactor run 74, because both the PRD and RLR were judged to be high during that run. This report describes the efforts to develop a realistic model explaining the reactivity observations for run 74 and presents recommendations for additional diagnostic information in the event of a recurrence of off-normal behavior of reactivity.
Date:
June 1976
Creator:
Walters, L. C.; Cutforth, D. C.; Forehand, H. M.; Hudman, G. D.; Larson, H. A.; MacFarlane, H. F. et al.
Object Type:
Report
System:
The UNT Digital Library
U-Pu-Zr Metal Alloy: a Potential Fuel for LMFBR's
This report critically reviews the available information pertinent to the potential use of uranium-plutonium-zirconium alloy fuels clad with stainless steel in LMFBR's. The areas considered include breeding potential, burnup potential, thermal performance, fuel fabricability, fuel reprocessing, and safety considerations. Because information on uranium-plutonium-zirconium alloys is limited, wide use is made of experience with EBR-II metallic driver fuel to infer advantages and limitations of uranium-plutonium-zirconium fuels. It is concluded that sufficient potential exists for the applicability of uranium-plutonium-zirconium fuels to LMBFR's to warrant additional analytical and experimental studies.
Date:
November 1975
Creator:
Walter, C. M.; Golden, G. H. & Olson, N. J.
Object Type:
Report
System:
The UNT Digital Library
Environmental Monitoring at Argonne National Laboratory, Annual Report: 1975
Annual report of the environmental monitoring program at Argonne National Laboratory, discussing activities and findings of the group.
Date:
March 1976
Creator:
Golchert, N. W.; Duffy, T. L. & Sedlet, J.
Object Type:
Report
System:
The UNT Digital Library
Plutonium Safety Training Course
This course seeks to achieve two objectives: to provide initial safety training for people just beginning work with plutonium, and to serve as a review and reference source for those already engaged in such work. Numerous references have been included to provide information sources for those wishing to pursue certain topics more fully. The first part of the course content deals with the general safety approach used in dealing with hazardous materials. Following is a discussion of the four properties of plutonium that lead to potential hazards: radioactivity, toxicity, nuclear properties, and spontaneous ignition. Next, the various hazards arising from these properties are treated. The relative hazards of both internal and external radiation sources are discussed, as well as the specific hazards when plutonium is the source. Similarly, the general hazards involved in a criticality, fire, or explosion are treated. Comments are made concerning the specific hazards when plutonium is involved. A brief summary comparison between the hazards of the trans-plutonium nuclides relative to plutonium-239 follows. The final portion deals with control procedures with respect to contamination, internal and external exposure, nuclear safety, and fire protection. The philosophy and approach to emergency planning are also discussed.
Date:
March 1976
Creator:
Moe, H. J.
Object Type:
Report
System:
The UNT Digital Library
Final Safety Analysis Addenda to Hazards Summary Report, Experimental Breeder Reactor II (EBR-II) : Upgrading of Plant Protection System, Volume 1
This report is a compilation of the formal Final Safety Analysis Addenda (FSAA's) to the EBR-II Hazard Summary Report and Addendum that have been prepared in support of certain modifications to the reactor-shutdown-system portion of the EBR-II plant protection system. Each major section is an edited version of the original FSAA for a particular modification and provides a description of the pre - and post -modification system, the rationale for the modification, and required supporting safety analysis.
Date:
March 1976
Creator:
Sackett, J. I. & Gale, N. L.
Object Type:
Report
System:
The UNT Digital Library
High-Performance Batteries for Off-Peak Energy Storage and Electric-Vehicle Propulsion, Progress Report: January-March 1976
Quarterly report describing the research and management effort of Argonne National Laboratory's program on lithium/metal sulfide batteries during the period January-March 1976. These batteries are being developed for energy storage on utility networks and for electric-vehicle propulsion. The present cells are vertically oriented, piismatic cells with a central positive electrode of FeS or FeS; and two facing negative electrodes of lithium-aluminum alloy, and an electrolyte of molten LiCl-KC1. The cell operating temperature is 400-450C.
Date:
May 1976
Creator:
Nelson, P. A.; Ivins, R. O.; Yao, N. P.; Battles, J. E.; Chilenskas, A. A.; Gay, E. C. et al.
Object Type:
Report
System:
The UNT Digital Library
Experimental Study of the Neutronics of the First Gas Cooled Fast Reactor Benchmark Assembly (GCFR Phase 1 Assembly)
The Gas Cooled Fast Reactor (GCFR) Phase I Assembly is the first in a series of ZPR-9 critical assemblies designed to provide a reference set of reactor physics measurements in support of the 300 MW(e) GCFR Demonstration Plant designed by General Atomic Company. The Phase I Assembly was the first complete mockup of a GCFR core ever built. A set of basic reactor physics measurements were performed in the assembly to characterize the neutronics of the assembly and assess the impact of the neutron streaming on the various integral parameters. The analysis of the experiments was carried out using ENDF/B-IV based data and two-dimensional diffusion theory methods. The Benoist method of using directional diffusion coefficients was used to treat the anisotropic effects of neutron streaming within the framework of diffusion theory. Calculated predictions of most integral parameters in the GCFR showed the same kinds of agreements with experiment as in earlier LMFBR assemblies.
Date:
December 1976
Creator:
Bhattacharyya, S. K.
Object Type:
Report
System:
The UNT Digital Library
One-Dimensional Cladding-Relocation Model for Fast-Reactor Loss-of-Flow Accidents
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 reversal, and eventual slumping down into liquid sodium at the lower end of the heated section. Freezing of the molten cladding at the unheated upper plenum region is possible; bottom freezing and blockage formation were also included in the analysis. A simple calculation has been made for the R-series seven-pin tests in the TREAT reactor. The agreement of the overall physical behavior of the cladding motion with the post-test observations is quite satisfactory.
Date:
March 1976
Creator:
Ishii, M.; Chen, W. L. & Grolmes, M. A.
Object Type:
Report
System:
The UNT Digital Library
ANL/HIWAY: an Air Pollution Evaluation Model for Roadways
This report describes a computer program, called ANL/HIWAY, for estimating air quality levels of nonreactive pollutants produced by vehicular sources. It is valid for receptors at distances of tens to hundreds of meters, at an angle, downwind of the roadway, in relatively uncomplicated terrain. It may be used by planners to analyze the effects of a proposed roadway on adjacent air quality. The ANL/HIWAY model expands the evaluation capabilities of the EPA/HIWAY dispersion model. This report also serves as a user's manual for running the ANL/HIWAY PROGRAM. All command structures are described in detail, with sample problems exemplifying their use.
Date:
December 1976
Creator:
Concaildi, George A.; Cohen, Alan S. & King, Richard F.
Object Type:
Report
System:
The UNT Digital Library
Simple Conduction Model with Phase Change for Fuel Pin
A simple conduction model with phase change has been developed for the transient analysis of a fuel pin based on average properties and lumped-parameter techniques. The transient behavior of fuel and cladding can be accurately described by simple analytical expressions that agree with conventional numerical approaches for under-cooling transient analysis. If it be assumed that the heat-transfer resistance between the fuel and cladding remains the same for both steady-state and transient periods, the phase-change problem for fuel and cladding melting can be significantly simplified. BY using the predetermined average overall heat-transfer coefficient across a fuel pin in the steady-state period, the average transient fuel and cladding temperatures can be formulated analytically. For loss of flow at constant power, the start of melting and complete melting for both the fuel and cladding can be estimated with considerable accuracy.
Date:
April 1976
Creator:
Chen, W. L.; Ishii, M. & Grolmes, M. A.
Object Type:
Report
System:
The UNT Digital Library
Risk-assessment methodology for fast breeder reactors
The methods applied or proposed for risk assessment of nuclear reactors are reviewed, particularly with respect to their applicability for risk assessment of future commercial fast breeder reactors. All methods are based on the calculation of accident consequences for relatively few accident scenarios. The role and general impact of uncertainties in fast-reactor accident analysis are discussed. The discussion shows the need for improvement of the methodology. A generalized and improved risk-assessment methodology is outlined and proposed (accident-spectra-progression approach). The generalization consists primarily of an explicit treatment of uncertainties throughout the accident progression. The results of this method are obtained in form of consequence distributions. The width and shape of the distributions depend in part on the superposition of the uncertainties. The first moment of the consequence distribution gives an improved prediction of the ''average'' consequence. The higher-consequence moments can be used for consideration of risk aversion. The assessment of the risk of one or a certain number of nuclear reactors can only provide an ''isolated'' risk assessment. The general problem of safety risk assessment and its relation to public acceptance of certain modes of power production is a much broader problem area, which is also discussed.
Date:
April 1976
Creator:
Ott, Karl O.
Object Type:
Report
System:
The UNT Digital Library
Application of Frequency-Modified Life Approach to the Low-Cycle Fatigue Behavior of Type 304 Stainless Steel
The application of the frequency-modified life equation to fatigue life prediction has been critically examined using the extensive fatigue data generated for Type 304 stainless steel at 1100 degrees F under a variety of cyclic-loading conditions. The parameters that enter into the frequency-modified life equation vary with strain rate and show a transition coinciding with the frequency of cycling at which a change in the fracture appearance from predominantly transgranular to predominantly intergranular failure mode or vice versa occurs. The accuracy in life prediction is improved when the effect of strain rate on life-predictive parameters is considered. It is shown how the effect of compressive and symmetric hold time on fatigue life can be taken into account. A comparison between the frequency-modified life approach of Coffin and the damage-rate approach recently developed by Majumdar and Maiya is also made to show the importance of wave-shape on low-cycle fatigue life.
Date:
May 1976
Creator:
Maiya, P. S. & Majumdar, S.
Object Type:
Report
System:
The UNT Digital Library
Experimental and Analytical Study of the Sputtering Phenomena
An experimental apparatus was constructed to examine the heat-transfer characteristics of a sputtering front. In the present study, a heat source of sufficient intensity was located immediately below the sputtering front, which prevented its downward progress, thus permitting detailed measurements of steady-state surface temperatures throughout a sputtering front. A two-dimensional analytical model was developed to describe a stationary sputtering front where the wet-dry interface corresponds to a CHF phenomena and the dry zone is adiabatic. This model is nonlinear because of the temperature dependence of the heat-transfer coefficient in the wetted region and has yielded good agreement with data. A simplified one-dimensional approximation was developed which adequately describes these data. Finally, by means of a coordinate transformation and additional simplifying assumptions, this analysis was extended to analyze moving sputtering fronts, and reasonably good agreement with reported data was shown.
Date:
March 1976
Creator:
Howard, Paul A.
Object Type:
Report
System:
The UNT Digital Library
Reactor Physics Studies in the Engineering Mockup Critical Assembly of the Fast Test Reactor
Reactor physics studies in the Engineering Mockup Critical (EMC) assembly of the Fast Test Reactor (FTR) facility are reported. The study included measurements of the neutron spectrum, Doppler effect, sodium-void worth, reaction rates, subassembly worths, material replacement worths, and FTR control, safety and shim rod worths. Each of these physics studies were made in a clean plutonium (low-Pu-240) fuel composition environment and a dirty plutonium (high-Pu-240) fuel composition environment. The fuel studies were in support of determining the attendant effects of operation and safety of utilizing Light Water Reactor (LWR) plutonium fuel in the FTR. Comparison of the measured and calculated results are presented.
Date:
July 1976
Creator:
Pond, R. B.
Object Type:
Report
System:
The UNT Digital Library
Land Reclamation Program, Annual Report: July 1975-July 1976
Annual report of the Argonne National Laboratory Land Reclamation Program outlining the activities and research conducted during the year, various assessments and discussion, and related documentation.
Date:
December 1976
Creator:
Argonne National Laboratory. Land Reclamation Program.
Object Type:
Report
System:
The UNT Digital Library
Use of Krypton-85 for the Detection of Pinhole Failures in GCFR Cladding
Radioactive krypton-85 is used as a tracer to detect pinhole failures in GCFR cladding. High-purity helium (99.99% pure) that contains 0.3 ppm krypton-85 is used to pressurize the tubular test specimens, and a Geiger-Mueller counter is used to detect the krypton-85 in the helium environmental gas as it leaves the test chamber. Under the least favorable conditions of temperature and specimen pressure, it is estimated that the smallest pinhole failure that could be detected within 60 sec would have an orifice diameter of 0.0102 cm. Using lead shielding around the Geiger-Muller counter to reduce background radiation, the electronics associated with the krypton-85 detector will terminate a biaxial creep test at krypton-85 activity levels above 20 counts/minute.
Date:
May 1976
Creator:
Yaggee, F. L.; Purohit, A. & Poeppel, R. B.
Object Type:
Report
System:
The UNT Digital Library
Examination and Evaluation of in-Reactor Fracture of Shroud Tubes in Mixed-Oxide Fuel Experiment X159
During disassembly and subsequent visual examinations of X159 (a Mark A-19A type of subassembly containing mixed-oxide fuel), 11 of 19 shroud tubes were found fully or partially severed. Several of the capsules within their shroud tubes were distinctly kinked at axial locations near those at which the shroud tubes were severed. The examination also disclosed that the shroud-tube fractures occurred during reactor operations.
Date:
June 1977
Creator:
Flinn, J. E.
Object Type:
Report
System:
The UNT Digital Library
Development of Lithium/Metal Sulfide Batteries at Argonne National Laboratory : Summary Report
Overview of the battery program at Argonne National Laboratory being developed for use as energy storage devices for load-leveling on electric utilities and as power sources for electric automobiles.
Date:
May 1976
Creator:
Nelson, P. A.
Object Type:
Report
System:
The UNT Digital Library
Numerical Integration of Large Deflection Elastic-Plastic Axisymmetric Shells of Revolution
The improvement in the method of large deflection elastic-plastic analysis of shells and other structures appears to have continued interest. With the development in this work an improved numerical suppression scheme is now available for the large deflection elastic-plastic analysis of axisymmetric shells of revolution subjected to symmetric loadings. Quasi-linearization of Sander's non-linear shell equations is presented for the first time. With these quasi-linearized equations the suppression scheme has been developed to solve non-linear boundary-value problems. This suppression scheme has been used in conjunction with a Newton-Raphson method to improve a stable convergence process at the yield surface in elastic-plastic problems. Results presented indicate the accuracy of this numerical scheme. It appears to be possible to extend this method for more complicated situations.
Date:
December 1976
Creator:
Ahmed, Habib Uddin
Object Type:
Report
System:
The UNT Digital Library
Measurement of the Hydrogen Yield in the Radiolysis of Water by Dissolved Fission Products
Hydrogen from the radiolysis of water by dissolved fission products is stripped from the solution and collected by bubbling carbon dioxide through the solution. Quantitative measurements of the G value for hydrogen show that the yield is essentially the same as would be obtained by external gamma radiolysis of nonradioactive solutions of the same chemical composition. The hydrogen yield can be enhanced by addition of a hydrogen-atom donor, such as formic acid, to the solution. The yield of hydrogen from fission-waste solutions is discussed with respect to the question of whether it represents a significant energy source.
Date:
April 1976
Creator:
Sauer, M. C., Jr.; Hart, E. J.; Flynn, K. F. & Gindler, J. E.
Object Type:
Report
System:
The UNT Digital Library
Physical Parameters in Synthoil Process, Quarterly Report: January-March 1976
This work is being done in support of the development of processes for converting coal to liquid fuel of low sulfur content, suitable for use in power production. Most of the effort is intended to produce information applicable to the SYNTHOIL Process. In the SYNTHOIL Process for converting coal to a low-sulfur fuel oil, coal is liquefied and hydro-desulfurized in a turbulent-flow, catalytic packed-bed reactor. A slurry of coal in recycled oil is reacted with hydrogen at 450 degrees C and 2,000 to 4,000 psi in the presence of Co-MoSiO2-Al2O3 catalyst. The turbulent flow of fluid prevents the coal's mineral matter from settling and plugging the reactor. The gross liquid products are centrifuged to remove the unreacted solids. The centrifuged liquid product is a low-S, low-ash fuel. The following four tasks are included: (1) heat of reaction of hydrogen with coal slurries; (2) heat transfer coefficient; (3) additives to facilitate separation of solids from liquids; and (4) catalyst testing. These are now in the planning stage of development.
Date:
1976?
Creator:
Fischer, J.; Lo, R.; Nandi, S.; Fredrickson, D.; Bump, T. R.; Mulcahey, T. P. et al.
Object Type:
Report
System:
The UNT Digital Library
Analysis of a Cylindrical Shell Vibrating in a Cylindrical Fluid Region
Analytical and experimental methods are presented for evaluating the vibration characteristics of cylindrical shells such as the thermal liner of the Fast Flux Test Facility (FFTF) reactor vessel. The NASTRAN computer program is used to calculate the natural frequencies, mode shapes, and response to a harmonic loading of a thin, circular cylindrical shell situated inside a fluid-filled rigid circular cylinder. Solutions in a vacuum are verified with an exact solution method and the SAP IV computer code. Comparisons between analysis and experiment are made, and the accuracy and utility of the fluid-solid interaction package of NASTRAN is assessed.
Date:
August 1976
Creator:
Chung, Ho; Mulcahy, T. M.; Turula, P. & Jendrzejczyk, J. A.
Object Type:
Report
System:
The UNT Digital Library
Comparison of the AMDAHL 470V/6 and the IBM 370/195 Using Benchmarks
Six groups of jobs were run on the IBM 370/195 at the Applied Mathematics Division (AMD) of Argonne National Laboratory using the current production versions of OS/MVT 21.7 and ASP 3.1. The same jobs were then run on an AMDAHL 470V/6 at the AMDAHL manufacturing facilities in Sunnyvale, California, using the identical operating systems. Performances of the two machines are compared. Differences in the configurations were minimized. The memory size on each machine was the same, all software which had an impact on run times was the same, and the I/O configurations were as similar as possible. This allowed the comparison to be based on the relative performance of the two CPU's. As part of the studies preliminary to the acquisition of the IBM 195 in 1972, two of the groups of jobs had been run on a CDC 7600 by CDC personnel in Arden Hills, Minnesota, on an IBM 360/195 by IBM personnel in Poughkeepsie, New York, and on the AMD 360/50/75 production system in June, 1971.
Date:
March 1976
Creator:
Snider, D. R.; Midlock, J. L.; Hinds, A. R. & Engert, D. E.
Object Type:
Report
System:
The UNT Digital Library
Studies of Unprotected Loss-of-Flow Accidents for the Clinch River Breeder Reactor
Studies of unprotected loss-of-flow accidents in the CRBR for various rates of flow coast-down and with various options in the SAS 3A code did not lead to conditions for a violent disassembly. Maximum fuel temperatures using the SLUMPY module for disassembly were in the range 4000-4500 deg C. An approximate treatment of the LOF-driven TOP accident, not properly modeled by SAS 3A, indicates the possibility of some increase in accident severity. The effect of fission gas in dispersing fuel was not taken into account in these calculations. Parameter variations included the presence or absence of axial fuel expansion and of clad motion and use of the moving coolant film model versus the static film model. Study of severe pipe rupture accidents with scram indicated that pin power density and fuel-clad conductance were important parameters in determining what coolant flow rate was needed to prevent boiling after the rupture. It appears that for the CRBR when engineering hot channel factors are considered, this fraction would have to exceed 25 percent.
Date:
April 1976
Creator:
Hummel, Harry H.; Pizzica, P. A. & Kalimullah
Object Type:
Report
System:
The UNT Digital Library