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Design and Economic Evaluation of Mobile Blankets for Fast Reactors

Description: Report evaluating the design characteristics and limitations of mobile blankets for breeder reactors. This also includes economic considerations for each tested blanket. Appendices begin on page 40.
Date: March 10, 1964
Creator: Klickman, A. E.; Ball, G. L.; Edwards, J. J.; Jens, W. H.; Segal, B. M.; Amorosi, A. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactor Safety and Fuel Cycle Economics Considerations for Fast Reactors

Description: Abstract: A core design study of a 10 Mwe fast ceramic reactor is presented. Local reactivity coefficients, safety criteria, accident analyses, and economics are considered. An attempt is made to find a new balance of characteristics by purely geometric devices, i.e., by exploring the sodium : fuel ratio and varying the height : diameter ratio of the core. The use of BeO in the core was also investigated.
Date: November 11, 1963
Creator: Cohen, K. P.; Greebler, P.; McNelly, M. J.; Murphy, P. M.; Sherer, D. B. & Zebroski, E. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fluctuation Analysis of Fast Reactor Safety Experiments in TREAT

Description: Statistical fluctuations of measured signals about their mean are related to physical processes in fuel-failure experiments. Signal variance, correlation, and spectral density are shown to be sensitive measures to instrument response characteristics, of flow-blockage formation, and of boiling phenomena. This sensitivity is demonstrated by a series of examples that use test data from the E6, E7, and L5 experiments. A mathematical model of the Mark-II loop is developed to predict both the mean an… more
Date: November 1978
Creator: Doerner, R. C.; Meek, C. C.; Hurt, R. F. & Pekarsky, M. I.
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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Development of a MK-II Loop to Simulate Reactor Hydraulic Conditions

Description: 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 … more
Date: January 1979
Creator: Page, R. J. & Robinson, L. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Study of Fast Reactor Meltdown Accidents Using Simulant Materials

Description: Report issued by the APDA over studies conducted on reactor meltdown accidents. The studies incorporated the use of simulation materials. Methods and results of the studies are presented and discussed. This report includes tables, illustrations, and photographs.
Date: August 31, 1963
Creator: Huebotter, P. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Comparison of Long-Lived, Prolieration Resistant Fast Reactors

Description: Nuclear power is expected to play a significant role in meeting future electricity needs, and in significantly reducing emissions compared to fossil-fueled power plants. However, the next generation of nuclear power plants will be expected to demonstrate significant advancements in economics, safety, waste disposal, and proliferation resistance. Many reactor types have been proposed for “Generation IV”, some of which have been fast reactors. The work discussed in here is part of a larger effort… more
Date: September 1, 2001
Creator: Weaver, Kevan Dean; Herring, James Stephen & Mac Donald, Philip Elsworth
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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A Global Approach to the Physics Validation of Simulation Codes for Future Nuclear Systems

Description: This paper presents a global approach to the validation of the parameters that enter into the neutronics simulation tools for advanced fast reactors with the objective to reduce the uncertainties associated to crucial design parameters. This global approach makes use of sensitivity/uncertainty methods; statistical data adjustments; integral experiment selection, analysis and “representativity” quantification with respect to a reference system; scientifically based cross section covariance data … more
Date: September 1, 2008
Creator: Palmiotti, Giuseppe; Salvatores, Massimo; Aliberti, Gerardo; Hiruta, Hikarui; McKnight, R.; Oblozinsky, P. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Reactor Physics Studies in the Engineering Mockup Critical Assembly of the Fast Test Reactor

Description: 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. … more
Date: July 1976
Creator: Pond, R. B.
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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Carbide Fuels in Fast Reactors

Description: Abstract: Cladding and fuel material processing prospects are reviewed, and fuel system possibilities for near-term (~1 mill/kwh) and long-range (<0.5 mil/kmh) fuel cycles are described.
Date: September 15, 1965
Creator: Wheelock, C. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Neutron Spectrum from Fast Reactor

Description: The following report analyzes the spectrum of neutrons and the fast reactor they emerged from with the energy interval 0.4 to 15 Mev as seen through a Boron-steel collimator.
Date: 1957
Creator: Rosen, Louis
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Disassembly of the Los Alamos Fast Reactor

Description: The procedures used in the complete and permanent disassembly of the Los Alamos Fast Reactor are described.
Date: July 1953
Creator: Jurney, Edward Thornton, 1921-; Arnold, G. P.; Corpieri, E. F.; Leachman, R. B.; Pierce, E. H.; Montoya, J. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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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Neutron Energy Distributions Inside the Fast Reactor

Description: This technical report presents results of nuclear plate work carried out to determine the neutron energy distribution inside the Los Alamos fast reactor. Most of the distributions which were investigated are valid over the energy region from 0.4 to 6 Mev. The results show that at the center of the reactor pot about 65% of the neutrons are located below 1 Mev in a rather narrow energy region which has a maximum in the neighborhood of 0.5 to 0.6 Mev. Above 2 Mev the energy distribution is similar… more
Date: December 15, 1950
Creator: Nereson, Norris G., 1918-2007
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fast Reactor Core Design Parameter Study

Description: Report describing parametric studies of eleven fast reactor fuel systems undertaken to determine the design and economic factors for producing electricity. The methods used for making the parametric studies are described, as well as the results of these studies. Appendices begin on page 103.
Date: March 1960
Creator: Atomic Power Development Associates
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Technical Review of ZPR-1 Accidental Transient - the Power Excursion, Exposures, and Clinical Data

Description: On June 2, 1952, 15:52 hours, a large reactivity change was made manually in a ZPR-1 assembly causing a power excursion of about one kwh, which resulted in damage to the reactor core components and radiation exposure of some of the operating personnel to perhaps several rep. None of the contributing causes is reviewed here nor are the measures which were taken to reduce the probability of a recurrence discussed since these are considered administrative matters beyond the scope of this technical… more
Date: January 26, 1953
Creator: Brittan, R. O.; Hasterlik, R. J.; Marinelli, L. D. & Thalgott, F. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Comparison of Long-Lived, Proliferation Resistant Fast Reactors

Description: Various methods have been proposed to transmute and thus consume the current inventory of trans-uranic waste that exists in spent light-water-reactor fuel. These methods include both critical and sub-critical systems. The neutronics of metallic and nitride fuels loaded with 20-30wt% light-water-reactor plutonium plus minor actinides for use in a lead-bismuth and sodium cooled fast reactor are discussed, with an emphasis on the fuel cycle life and isotopic content. Calculations show that core li… more
Date: September 1, 2001
Creator: Weaver, Kevan Dean; Herring, James Stephen & Mac Donald, Philip Elsworth
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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