Search Results

Advanced search parameters have been applied.
open access

Final Safety Analysis Addendum to Hazard Summary Report, Experimental Breeder Reactor No. II (EBR-II): the EBR-II Cover-Gas Cleanup System

Description: This report evaluates abnormal and accident conditions postulated for the EBR-II cover-gas cleanup system (CGCS). Major considerations include loss of CGCS function with a high level of cover-gas activity, loss of the liquid-nitrogen coolant required for removing fission products from the cover gas, contamination of the cover gas from sources other than the reactor, and loss of system pressure boundary. Calculated exposures resulting from the maximum hypothetical accident (MHA) are less than 2%… more
Date: April 1979
Creator: Fryer, R. M.; Monson, L. R.; Price, C. C. & Hooker, D. W.
Partner: UNT Libraries Government Documents Department
open access

Chemical Engineering Division Sodium Technology Annual Report: July 1975-June 1976

Description: The Sodium Technology program currently comprises three parts. The first part is aimed at developing a model for accurately describing the behavior of tritium in LMFBRs from its formation in the core to its ultimate retention in the cold traps or release to the environment. Two important parts of this model are the behavior of the sodium cold traps and permeation of tritium through the steam-generator heat-transfer surfaces. A tritium monitor has been developed and installed on EBR-II to measur… more
Date: January 1977
Creator: McPheeters, C. C.; Jardine, L. J.; McKee, J. M.; Raue, D. J.; Renner, T. A.; Skladzien, S. B. et al.
Partner: UNT Libraries Government Documents Department
open access

An Overview of Pool-Type LMFBRs : General Characteristics

Description: This report describes the results of a study conducted by a "Pool Study Group" organized at ANL in mid-1975 to examine the present state of the air of design of pool-type LMFBRs. The study concentrated on examination of various design options used to date in the principle pool-type projects and design studies in this country and abroad, including the Phenix and Super-Phenix reactors (France), PFR and CFR (U.K.), RN-600 (U.S.S.R.) and EBR-II (U.S.A.). The objective of the report is to provide a … more
Date: May 1976
Creator: Amorosi, A.; Hutter, E.; Marciniak, T. J.; Monson, H. O.; Seidensticker, R. W. & Simmons, W. R.
Partner: UNT Libraries Government Documents Department
open access

Classified Progress Report of the Reactor Science and Engineering Department January 1 - March 31, 1950

Description: Technical report indicating the progress made in the first quarter of 1950 only for the classified projects in the Reactor Science and Engineering Department, including continuous processing breeder blanket studies, sub-critical experiments, and metallurgical experiments like fluid fuels, materials testing, reactor reconstruction, and reactor component testing and service.
Date: 1950
Creator: Brookhaven National Laboratory
Partner: UNT Libraries Government Documents Department
open access

Irradiation Testing of Fuel for Core B of the Enrico Fermi Fast Breeder Reactor

Description: Report issued by the Oak Ridge National Laboratory discussing irradiation testing of fast breeder reactors. As stated in the introduction, "it is the purpose of this report to describe the irradiation studies carried out in support of the Core B fuel element development program" (p. 3). This report includes tables, illustrations, and photographs.
Date: November 1964
Creator: Thurber, W. C.; McQuilkin, F. R.; Long, E. L., Jr. & Osborne, M. F.
Partner: UNT Libraries Government Documents Department
open access

Final Safety Analysis Addenda to Hazards Summary Report, Experimental Breeder Reactor II (EBR-II) : Upgrading of Plant Protection System, Volume 1

Description: 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 a… more
Date: March 1976
Creator: Sackett, J. I. & Gale, N. L.
Partner: UNT Libraries Government Documents Department
open access

Physical Research on Liquid-Metal Systems Annual Report: July 1975-June 1976

Description: Physicochemical and thermodynamic studies of liquid-lithium-containing systems have continued. Pressure-composition isotherms for the lithium-hydrogen system measured by a gravimetric technique are found to be in reasonably good agreement with earlier tensimetric results. Plateau-pressure studies of the lithium-hydrogen, lithium-deuterium, and lithium-tritium systems have been made at temperatures above and below the monotectic. The observed isotope effects were found to be near the predicted v… more
Date: January 1977
Creator: Maroni, V. A.; Calaway, W. F.; Veleckis, Ewald; Yonco, R. M.; Cafasso, F. A. & Burris, L.
Partner: UNT Libraries Government Documents Department
open access

Liquid Metal Fuel Reactor Experiment: Reference Design Report

Description: Report concerning preliminary designs of the Liquid Metal Fuel Reactor Experiment (LMFRE) facility. This includes descriptions of the reactor, degasser, and steam system, materials to be used, plant arrangement, building siting, and safety considerations.
Date: August 1957
Creator: Babcock & Wilcox Company
Partner: UNT Libraries Government Documents Department
open access

Final Report on the Small-Scale Vapor-Explosion Experiments Using a Molten NaCl-H2O System

Description: Vapor explosions were produced by injecting small quantities of water into a container filled with molten sodium chloride. Minimum explosion efficiencies, as evaluated from reaction-impulse measurements, were relatively large. Subsurface movies showed that the explosions resulted from a two-step sequence: an initial bulk-mixing phase in which the two liquids intermix on a large scale, but remain locally separated by an insulating gas-vapor layer; and a second step, immediately following breakdo… more
Date: April 1976
Creator: Anderson, R. P. & Bova, L.
Partner: UNT Libraries Government Documents Department
open access

Fast Breeder Reactor Studies

Description: This report is a compilation of Fast Breeder Reactor (FBR) resource documents prepared to provide the technical basis for the US contribution to the International Nuclear Fuel Cycle Evaluation. The eight separate parts deal with the alternative fast breeder reactor fuel cycles in terms of energy demand, resource base, technical potential and current status, safety, proliferation resistance, deployment, and nuclear safeguards. An Annex compares the cost of decommissioning light-water and fast br… more
Date: July 1980
Creator: Till, C. E.; Chang, Y. I.; Kittel, J. H.; Fauske, H. K.; Lineberry, M. J.; Stevenson, M. G. et al.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen