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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
open access

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
open access

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
open access

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
open access

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
open access

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
open access

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
open access

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
open access

Pathogenesis and Regeneration of Radiation Induced Bone Marrow Injury, and Therapeutic Implications

Description: This report reviews aspects of experimental and clinical research performed in the investigation on the pathogenesis and recovery of bone marrow injury caused by total body irradiation.
Date: April 23, 1962
Creator: Fliedner, T. M., (Theodor M.), 1929-; Cronkite, Eugene P. & Bond, Victor P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Reactor Safety Study: An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants, Appendix 1

Description: From introduction: In conventional safety analyses, a suitable design basis, including redundancy, is specified to assure a minimum level of operability of ESFs, and the likelihood or consequences of total failure of ESFs are not considered further. In this study all failures are considered possible, but appropriate probabilities are assigned to them. Thus, many potential accident sequences are described in the following discussions as if they will surely occur, with no reservations expressed a… more
Date: October 1975
Creator: U.S. Nuclear Regulatory Commission
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Reactor Safety Study: An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants, Appendices 3 and 4

Description: From section 1: In the quantitative system probability estimates performed in this study, component behavior data in the form of failure rates and repair times are required as inputs to the system models. Since the goal of this study is risk assessment, as opposed to reliability analysis, larger errors (e.g. order of magnitude type accuracy) can be tolerated in the quantified results. This has important implications on the treatment of available data. In standard reliability analysis, point val… more
Date: October 1975
Creator: U.S. Nuclear Regulatory Commission
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Proceedings of the Third Post-Accident Heat Removal Information Exchange November 2-4, 1977, Argonne National Laboratory, Argonne, Illinois

Description: Papers presented at the third Post-Accident Heat Removal Information Exchange concerning heat distribution and criticality considerations, particulate-bed phenomena, pool heat transfer and melt-front phenomena, behavior of heated concrete and sodium-concrete interactions, design-related studies, gas bubbling and boiling effects, and materials interactions at high temperatures and experimental methods.
Date: 1978?
Creator: Baker, Louis, Jr. & Bingle, James D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Final Report of Fuel Dynamics Test E7

Description: Test data from an in-pile failure experiment of high-power LMFBR-type fuel pins in a simulated $3/s transient-overpower (TOP) accident are reported and analyzed. Major conclusions are that (1) a series of cladding ruptures during the 100-ms period preceding fuel release injected small bursts of fission gas into the flow stream; (2) gas release influenced subsequent cladding melting and fuel release (there were no measurable FCI's (fuel-coolant interactions), and all fuel motion observed by the … more
Date: April 1977
Creator: Doerner, R. C.; Murphy, W. F.; Stanford, G. S. & Froehle, P. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Design Review and Safety Analysis of Experiments in ORNL Research Reactors

Description: Since 1943 when the oak Ridge Graphite Reactor was put into operation, literally thousands of individual irradiation have been performed in this reactor and in other ORNL research reactors. Over the years there have been many minor incidents caused by experiments. Such incidents have provided a basis cor continued improvement in experiment design review and safety-analysis procedures. The reports lists the Design Review and Safety Analysis (1) objectives, (2) principles and rules of design, a… more
Date: October 1963
Creator: Stanford, L. E. & Costner, R. A., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Neutron Burst from a Cylindrical Untamped OY Assembly

Description: A neutron burst from an untamped cylindrical Oy assembly occurred at the Pajarito Remote Control Laboratory at 1800 hours on 18 April 1952. The circumstances causing the burst and a description of the assembly involved are given There was no personnel hazard. Normal operations could have been resumed on other assemblies withing two or three hours after the burst. No evidence of damage to the oy was observed. It was determined that the burst resulted in 1.5 x 10(16) fissions in the oy. Also repo… more
Date: July 22, 1952
Creator: Mallary, E. C.; Hansen, G. E.; Linenberger, G. A. & Wood, D. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

LOCA Analyses Annual Report: 1977

Description: Discussing sensitivity studies of the response surface developed for a seven-variable, sparsely-noded set of RELAP calculations.
Date: 1978
Creator: U.S. Nuclear Regulatory Commission. Division of Systems Safety.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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