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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
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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
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Accidental Radiation Excursion at the Y-12 Plant, June 16, 1958: Final Report

Description: This report describes the circumstances leading to the accident, attempts to reconstruct the nuclear reactivity conditions, and reviews the dosimetric means and results which were used to help determine the exposure of affected employees.
Date: September 12, 1958
Creator: Patton, F. S.; Bailey, J. C.; Callihan, A. D.; Googin, J. M.; Jasny, G. R.; McAlduff, H. J. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Quasi-Eulerian Method for Analyzing Slug Impact and Coolant Spillage in a Fast-Reactor Accident

Description: 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… more
Date: December 1979
Creator: Chu, Han Y.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SACO-1: a Fast-Running LMFBR Accident-Analysis Code

Description: SACO is a fast-running computer code that simulates hypothetical accidents in liquid-metal fast breeder reactors to the point of permanent subcriticality or to the initiation of a prompt-critical excursion. In the tradition of the SAS codes each sub-assembly is modeled by a representative fuel pin with three distinct axial regions to simulate the blanket and core regions. However, analytic and integral models are used wherever possible to cut down the computing time and storage requirements. Th… more
Date: January 1980
Creator: Mueller, C. J.; Cahalan, J. E. & Vaurio, J. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ICECO-CEL: A Coupled Eulerian-Lagrangian Code for Analyzing Primary System Response in Fast Reactors

Description: This report describes a coupled Eulerian-Lagrangian code, ICECO-CEL, for analyzing the response of the primary system during hypothetical core disruptive accidents. The implicit Eulerian method is used to calculate the fluid motion so that large fluid distortion, two-dimensional sliding interface, flow around corners, flow through coolant passageways, and out-flow boundary conditions can be treated. The explicit Lagrangian formulation is employed to compute the response of the containment vesse… more
Date: February 1981
Creator: Wang, C. Y.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of the October 5, 1979 Lithium Spill and Fire in the Lithium Processing Test Loop

Description: On October 5, 1979, the Lithium Processing Test Loop (LPTL) developed a lithium leak in the electromagnetic (EM) pump channel, which damaged the pump, its surrounding support structure, and the underlying floor pan. A thorough analysis of the causes and consequences of the pump failure was conducted by personnel from CEN and several other ANL divisions. Metallurgical analyses of the elliptical pump channel and adjacent piping revealed that there was a significant buildup of iron-rich crystallit… more
Date: December 1981
Creator: Maroni, V. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PROSA-2: A Probabilistic Response-Surface Analysis and Simulation Code

Description: Response-surface techniques have been developed for obtaining probability distributions of the consequences of postulated nuclear reactor accidents. In these techniques, probability distributions are assigned to the system and model parameters of the accident analysis. A limited number of parameter values (called knot points) are selected and input to a deterministic accident-analysis code. The results of the deterministic analyses are used to generate analytical functions (called response surf… more
Date: May 1981
Creator: Vaurio, J. K. & Fletcher, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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POLYFAIL: A Program for Identification of Multiple Fuel Failures with Gas Tagging

Description: This report describes the development of the computer code POLYFAIL for identification of fuel failures in fast reactors or light-water reactors that use gas tagging. POLYFAIL implements a sophisticated numerical algorithm known as the method of barycentric coordinates. The code can treat problems involving up to four simultaneous tag releases in a tagging system characterized by three independent tag ratios. The sensitivity of the multiple-failure-resolution technique has been optimized by inc… more
Date: 1981
Creator: Gross, Kenny C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Theory and Use of GIRAFFE for Analysis of Decay Characteristics of Delayed-Neutron Precursors in an LMFBR

Description: The application of the computer code GIRAFFE (General Isotope Release Analysis For Failed Elements) written in FORTRAN IV is described. GIRAFFE was designed to provide parameter estimates of the nonlinear discrete-measurement models that govern the transport and decay of delayed-neutron precursors in a liquid-metal fast breeder reactor (LMFBR). The code has been organized into a set of small, relatively independent and well-defined modules to facilitate modification and maintenance. The program… more
Date: July 1980
Creator: Gross, Kenny C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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TRANS4 : a Computer Code Calculation of Solid Fuel Penetration of a Concrete Barrier

Description: The computer code, TRANS4, models the melting and penetration of a solid barrier by a solid disc of fuel following a core disruptive accident. This computer code has been used to model fuel debris penetration of basalt, limestone concrete, basaltic concrete, and magnetite concrete. Sensitivity studies were performed to assess the importance of various properties on the rate of penetration. Comparisons were made with results from the GROWS II code.
Date: July 1980
Creator: Ono, C. M.; Kumar, R. & Fink, J. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Summary of Treat Experiments on Oxide Core-Disruptive Accidents

Description: 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… more
Date: February 1979
Creator: Dickerman, Charles Edward; Rothman, Alan B.; Klickman, A. E.; Spencer, B. W. & DeVolpi, Alexander
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development of a Methodology for Analysis of Delayed-Neutron Signals

Description: Experimental and analytical techniques have been developed for analysis and characterization of delayed-neutron (DN) signals that can provide diagnostic information to augment data from cover-gas analyses in the detection and identification of breached elements in an LMFBR. Eleven flow-reduction tests have been run in EBR-II to provide base data support for predicting DN signal characteristics during exposed-fuel operation. Results from the tests demonstrate the feasibility and practicability o… more
Date: February 1980
Creator: Gross, K. C.; Strain, R. V. & Fryer, R. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Transient-Overpower Test E8 on FFTF-Type Low-Power-Irradiated Fuel

Description: Test E8 simulated a hypothetical $3/s transient overpower accident in an LMFBR using seven (plutonium, uranium) oxide fuel elements of the FTR type. The test elements were pre-irradiated in the PNL-10 assembly in EBR-II to 5 at.% burnup at 30 kW/m. The pre-irradiation in EBR-II caused a fuel-restructuring range characteristic of a low-to-moderate power microstructure for FTR. Failure predictions indicated that fuel with this microstructural characteristic would fail at a lower energy deposition… more
Date: 1977?
Creator: Simms, R.; Murphy, W. F.; Stanford, G. S. & Rothman, Alan B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactor Physics Studies in the Steam Flooded GCFR-Phase 2 Critical Assembly

Description: A possible accident scenario in a Gas-Cooled Fast Reactor (GCFR) is the leakage of secondary steam into the core. Considerable analytical effort has gone into the study of the effects of such an accidental steam entry. The work described in this report represents the first full scale experimental study of the steam-entry phenomenon in GCFRs. The reference GCFR model used for the study was the benchmark GCFR Phase II assembly, and polyethylene foam was used to provide a very homogeneous steam si… more
Date: August 1978
Creator: Bhattacharyya, S. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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F1 Phenomenological Test on Fuel Motion : Final Report

Description: TREAT F-series tests are being conducted to provide data on fuel motion in an LMFBR during a hypothetical loss-of-flow accident. Fuel and fuel-boundary conditions in an LMFBR subassembly following sodium voiding and dryout under loss-of-flow conditions are simulated in each F-series test. Simulation is achieved with a single fuel element surrounded by an annular nuclear-heated wall in a dry (no sodium) test capsule. The area inside the heated wall was selected to represent the area inside the p… more
Date: May 1978
Creator: Argonne National Laboratory. Reactor Analysis and Safety Division.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PROSA-1 : a Probabilistic Response-Surface Analysis Code

Description: Techniques for probabilistic response-surface analysis have been developed to obtain the probability distributions of the consequences of postulated nuclear-reactor accidents. The uncertainties of the consequences are caused by the variability of the system and model input parameters used in the accident analysis. Probability distributions are assigned to the input parameters, and parameter values are systematically chosen from these distributions. These input parameters are then used in determ… more
Date: June 1978
Creator: Vaurio, J. K.; Mueller, C.; Kyser, J. M. & Sciaudone, D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Combined Motion of Fuel and Coolant Due to Fuel-Coolant Interactions under High Ramp Rate Reactivity Insertion

Description: An analysis has been made of the combined motion of fuel and coolant due to fuel-coolant interactions following a massive fuel failure in a high-ramp overpower transient. The motion of fuel and coolant was described using a two-fluid model formulation in which the mixture of sodium liquid and vapor and of fission gas, on the one hand, and the fuel particles, on the other, were treated as two superimposed continua. The method of solution employed a numerical procedure called the ACE method, a m… more
Date: July 1978
Creator: Chang, K. I. & Cho, D. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The FSTATE Code

Description: A transient, two-dimensional code has been developed to provide a detailed description of fuel-clad conditions during a TOP accident. Emphasis has been directed toward development of a framework within which fuel motion and ejection can be viewed following pin failure. All code modules have been rigorously verified. Illustrative application of the code, with the exercise of its many and varied features, have been included.
Date: August 1978
Creator: Meek, C. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Explosions of Ammonium Nitrate Fertilizer on Board the S. S. Grandcamp and S. S. High Flyer at Texas City, Texas, April 16, 17, 1947

Description: Report issued by the Bureau of Mines regarding explosions that took place on two separate cargo ships in 1947. The observations, data collected, and testing done during investigations of the disaster are presented. This report includes photographs, and illustrations.
Date: February 1948
Creator: Kintz, G. M.; Jones, G. W. & Carpenter, Charles B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Coal-Mine Fatalities in May, 1926

Description: Report issued by the U.S. Bureau of Mines on the coal-mining related deaths in May, 1926. The 126 accidents are documented and categorized. The accidents are analyzed in order to prevent future accidents, and to implement safety procedures. This report includes tables.
Date: June 1926
Creator: Adams, William Waugh
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Accident-Severity Rates For Certain Metal Mines

Description: Report issued by the U.S. Bureau of Mines on the severity of accidents in the metal-mine industry. 34 metal-mines documented the number and severity of all accidents over the course if one calendar year. This report includes tables.
Date: September 1926
Creator: Adams, William Waugh
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The National Safety Competition of 1929

Description: Report issued by the U.S. Bureau of Mines on the fifth annual national safety competition. The states represented in the competition are listed. Accident-frequency rates are presented as well. This report includes tables.
Date: May 1930
Creator: Adams, William Waugh
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Coal-Mine Fatalities in November, 1930

Description: Report issued by the U.S. Bureau of Mines on the fatalities of coal miners in November, 1930. The common causes of death, and the location of the mines that the fatalities occurred in are listed. This report includes tables.
Date: December 1931
Creator: Adams, William Waugh & Chenoweth, L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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