467 Matching Results

Search Results

Advanced search parameters have been applied.

Critical mass experiment using U-235 foils and lucite plates

Description: The main objective of this experiment was to show how the multiplication of the system increases as moderated material is placed between highly enriched uranium foils. In addition, this experiment served to demonstrate the hand-stacking techniques, and approach to criticality by remote operation. This experiment was designed by Tom McLaughlin in the mid seventies as part of the criticality safety course that is taught at Los Alamos Critical Experiment Facility (LACEF). The W-U-235 ratio for this experiment was 215 which is where the minimum critical mass for this configuration occurs.
Date: May 1, 1998
Creator: Sanchez, R.; Butterfield, K.; Kimpland, R. & Jaegers, P.
Partner: UNT Libraries Government Documents Department

ARGONAUT REACTOR DATA-BOOK. A compilation of experimental and theoretical results of work done with, or related to, the Argonaut Reactor to July 1960

Description: This compilation was prepared to provide a comprehensive unified summary of the principal elements of the design, operation and nuclear characteristics of the Argonaut Reactor. Its primary content is made up of the theoretical and experimental evaluations of basic reactor parameters, both static and kinetic, which have been made to this date. The Databook includes also some practical information on the reaativity worths of fuel, moderator, and absorbers, as well as some data on radiation in the reactor vicinity. A list of Argonaut type reactors in all countries and a bibliography of Argonaut work are included. (auth)
Date: January 1, 1961
Creator: Sturm, W.J. & Daavettila, D.A.
Partner: UNT Libraries Government Documents Department

NEUTRON MODERATION BY ACOUSTIC MODES OF METAL HYDRIDES

Description: >The excitation by nuclear collisions of the acoustic modes of a metal hydride crystal was investigated, using a model of the crystal based on experiments on ZrH/sub 2/, but slightly more general. It is found that these modes contribute little tc neutron moderation in ZrH/sub 2/. In the course of the discussion, a generalized form of the Wilkins equation, which determines the spectrum of neutrons thermalizing in a heavy moderator, is developed, applicable when the scattering cross section varies with energy. (auth)
Date: December 1, 1959
Creator: Vaughan, E.U.
Partner: UNT Libraries Government Documents Department

Neutron Cross Section Uncertainties in the Thermal and Resonance Regions

Description: In the 'Atlas of Neutron Resonances', special care was expended to ensure that the resonance parameter information reproduces the various measured thermal cross sections, as well as the infinite dilute resonance integrals for Z = 1-100. In contrast, the uncertainties of the recommended quantities do not match those generated from the uncertainties of the resonance parameters. To address this problem, the present study was initiated to achieve consistency for 15 actinides and 21 structural and coolant moderator materials. This is realized by assigning uncertainties to the parameters of the negative-energy resonances and changing, if necessary, significantly the uncertainties of the low-lying positive-energy resonances. The influence of correlations between parameters on the derived uncertainties is examined and discussed.
Date: June 24, 2008
Creator: Mughabghab,S.F. & Oblozinsky, P.
Partner: UNT Libraries Government Documents Department

International shock-wave database project : report of the requirements workshop.

Description: We report on the requirements workshop for a new project, the International Shock-Wave database (ISWdb), which was held October 31 - November 2, 2011, at GSI, Darmstadt, Germany. Participants considered the idea of this database, its structure, technical requirements, content, and principles of operation. This report presents the consensus conclusions from the workshop, key discussion points, and the goals and plan for near-term and intermediate-term development of the ISWdb. The main points of consensus from the workshop were: (1) This international database is of interest and of practical use for the shock-wave and high pressure physics communities; (2) Intermediate state information and off-Hugoniot information is important and should be included in ISWdb; (3) Other relevant high pressure and auxiliary data should be included to the database, in the future; (4) Information on the ISWdb needs to be communicated, broadly, to the research community; and (5) Operating structure will consist of an Advisory Board, subject-matter expert Moderators to vet submitted data, and the database Project Team. This brief report is intended to inform the shock-wave research community and interested funding agencies about the project, as its success, ultimately, depends on both of these groups finding sufficient value in the database to use it, contribute to it, and support it.
Date: March 1, 2012
Creator: Aidun, John Bahram (Institute of Problems of chemical Physics of Russian Academy of Sciences); Lomonosov, Igor V. (Institute of Problems of chemical Physics of Russian Academy of Sciences) & Levashov, Pavel R. (Joint Institute for High Temperatures of Russian Academy of Sciences)
Partner: UNT Libraries Government Documents Department

NUMERICAL RESULTS FOR EGCR MODERATOR-ELEMENT STRESS PROBLEMS

Description: A detailed presentation is made of the thermal stresses calculated for the moderater elements in the Experimental Gas-Cooled Reactor. These results are discussed and some conclusions are presented. This report complements a previous report, BMI-1503, which defines the problems and discusses the methods of solution. (auth)
Date: July 1, 1961
Creator: Hulbert, L.E. & Redmond, R.F.
Partner: UNT Libraries Government Documents Department

HOMOGENEOUS HIGH-FLUX REACTOR

Description: Maximum thermal-neutron fluxes obtainable for the case that maximum power density is limited to 100 w-/cm/sup 3/, and for the case that total reactor power is 100 Mw are listed for a homogeneous reactor, and for five moderators. (auth)
Date: March 31, 1958
Creator: Ergen, W.K.
Partner: UNT Libraries Government Documents Department

PLUTONIUM PLEXIGLAS ASSEMBLIES. PART II

Description: Neutron multiplication measurements were made on tamped and untamped cylindrical assemblies. The assemblies consisted of plutonium metal sheet mcderated with Plexiglas. Experiments were performed to evaluate the effects of inhomogeneity. This work is a continuation of RFP-178. (auth)
Date: April 1, 1960
Creator: Bidinger, G.H.; Schuske, C.L. & Smith, D.F.
Partner: UNT Libraries Government Documents Department

The Hemad Code

Description: Instructions on the use of HEMAD code are presented. This code is used to compute the energy spectrum of neutrons in an infinite, homogeneous lattice in the heavy moderator approximation and to average specified quantitics over such spectrum. (J.R.D.)
Date: August 1, 1959
Creator: Scott, B. L.
Partner: UNT Libraries Government Documents Department

A Thermal/Hydraulic Safety Assessment of the Blanket Conceptual Design for the Accelerator Production of Tritium Facility

Description: In support of the Accelerator Production of Tritium (APT) project, safety analyses for the blanket system have been performed based on the conceptual design for the Target/Blanket (T/B) Facility. During mitigated event sequences safety engineered features, such as the residual heat removal (RHR) and cavity flood systems, provide sufficient protection for maintaining the structural integrity of the blanket system and its components. During unmitigated (with beam shutdown only) event sequences, passive features such as natural circulation, thermal inertia, and boil-off provide significant time for corrective measures to be taken.
Date: September 1, 1998
Creator: Hamm, L.L.; Lee, S.Y.; Shadday, M.A. & Smith, F.G. III
Partner: UNT Libraries Government Documents Department