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Description: A method is sought for predicting reactivity differences between fuel elements attached to control absorbers and fixed fuel elements. The approach described is based on a logic that is approximate, and which should be subjected to experimental check. (auth)
Date: January 19, 1959
Creator: Murray, R.L.
Partner: UNT Libraries Government Documents Department

Hydraulic and Heat Transfer Transients During Power Ramp - Mark VII-AL Tests at Columbia University

Description: Transient tests were run at Columbia University on a Mark VII-AL mockup to reproduce the hydraulics and heat transfer in a single fuel assembly during a power ramp resulting from the accidental withdrawal of control rods from a reactor. This document presents results of those tests.
Date: January 6, 2003
Creator: Durant, W.S.
Partner: UNT Libraries Government Documents Department

Physics study of the TRADE : TRIGA accelerator driven experiment.

Description: This report deals with the validation of an ADS dynamic behavior through the TRADE program. We first describe the motivations behind the TRADE project. This includes the types of ADS experiments to be performed and their necessity, beam trips issues, representativity of the experiment, and steps to be taken in the validation procedure. Then we perform the characterization of the TRADE core using deterministic methods. The general core description is given. A number of results related to the core criticality and modeling with different geometries are presented. Finally we report the experimental results of the recent critical measurements including the control rod calibration, determination of the critical configurations and fluxes in the core.
Date: January 13, 2004
Creator: Naberejnev, D.; Imel, G.; Palmiotti, G. & Salvatores, M.
Partner: UNT Libraries Government Documents Department

Mark 22 Reactivity

Description: Calculations for reactivity held in control rods have underpredicted the observed Mark 22 reactivity. Reactivity predictions by charge designers have accounted for this by including large biases which change with exposure and reactor region. The purpose of this study was to thoroughly investigate the methods and data used in the reactivity calculations. The goal was to identify errors and improvements and make necessary corrections.
Date: July 2, 2001
Creator: Buckner, M.R.
Partner: UNT Libraries Government Documents Department

The Marvel-Schebler Control Rod Drive System Design Review. Final Report

Description: The results and conclusions of a design review of the Marvel-Schebler control rod drive system are presented. The review included studies of mechanical design, electem reliability, system logic, component and logic failures, and system relationship to reactor safety. Work was not completed on the fault analysis, system packaging, and test recommendations. (auth)
Date: September 1, 1963
Partner: UNT Libraries Government Documents Department

Physics Calculations for Control Rods in the First Yankee Core

Description: BS>The calculation of control rod worths in light water moderated reactors is presented. Considerable experimental information from the Yankee critical experiments is discussed and applied to improve the theory. The calculation system thus deduced from theory and experiment is then applied to the final design of the first Yankee core to provide a prediction of the shutdown available in its control rods. These calculations show that the 24 control rods presently provided are sufficient to shut the hot, clean, zero power first core down by 3%. (auth)
Date: September 1, 1959
Creator: Arnold, W. H., Jr.
Partner: UNT Libraries Government Documents Department


Description: S>A program will be required for controlling the wall temperature of a pot calciner during calcination in order to prevent an excessive temperature rise from internal heat generation while assuring complete calcination of the cake at 1650 deg F. A linear approximation to a pot wall temperature program indicates that this can be accomplished by holding the wall temperature at 1650 deg for 0.8 to 1.0 hrs and then cooling the wall at rates dependent upon the cake internal heat generation rate and average thermal conductivity. A similar study indicates that if it is necessary to reheat the cake for complete calcination, the wall heating time must be limited to prevent excessive temperature rise in the cake. Reheating times are also dependent upon the cake internal heat generation and thermal conductivity. (auth)
Date: May 31, 1962
Creator: Holmes, J M
Partner: UNT Libraries Government Documents Department


Description: Experimental data and observations of the design parameters and physical configurations which lead to faster-release cylindrical flat-faced electromagnets are given. Detailed drawings and operating characteristics are presented for an electromagnet suited to the requirements of a pool-type research reactor using either gravity drop or additional accelerating force. This electromagnet embodies the experimentally developed techniques for attaining fast release. (auth)
Date: February 14, 1958
Creator: Michelson, C.
Partner: UNT Libraries Government Documents Department


Description: Equipment and procedures uscd in testing Army Package Power Reactor control rod drive mechanisms are described. Photographs of mechanism components taken before and after testing are included. (D.E.B.)
Date: August 15, 1957
Creator: Tully, J.P.; Connolly, T.F. & Anderson, R.E.
Partner: UNT Libraries Government Documents Department


Description: The magnetic jack is a device for positioning the control rods In a nuclear reactor, especially in a reactor containing water under pressure. Magnetic actuation precludes the need for shaft seals and eliminates the problems associated with mechanisms operating in water. It consists of a pressure shell, four sets of external stationary magnet coils (hold, grip, lift, pull down), and one Internal moving part (ammature) that impants linear motion to a cluster of rods. (W.L.H.)
Date: November 1, 1959
Creator: Young, J.N.
Partner: UNT Libraries Government Documents Department


Description: An analytical prediction of the burnout distributions in particular SM-1 fuel elements and absorber sections after 10.5 MWYR of core energy release is given. The distributions are based on the results of a one-shot, non-uniform burnout calculation, and are pre sented for both fuel and boron -10 depletion. Particular emphasis is placed on those elements removed from the SM-1 core in March 1959, since their subsequent burnup analysis by ORNL should provide a valuable check on the analytical models employed. (auth)
Date: June 1, 1959
Creator: McElligott, P.E.
Partner: UNT Libraries Government Documents Department

Implementation of nodal equivalence parameters in DIF3D-VARIANT for core analysis of prismatic Very High Temperature Reactor (VHTR).

Description: The VARIANT module of the DIF3D code has been upgraded to utilize surface-dependent discontinuity factors. The performance of the new capability is verified using two-dimensional core cases with control rods in reflector and fuel blocks. Cross sections for VHTR components were generated using the DRAGON and HELIOS codes. For rodded block cross sections, the DRAGON calculations used a single-block model or the multi-block models combined with MCNP4C flux solutions, whereas the HELIOS calculations utilized multi-block models. Results from core calculations indicate that multiplication factor, block power, and control rod worth are significantly improved by using surface-dependent discontinuity factors.
Date: March 15, 2007
Creator: Lee, C. H.; Joo, H. K.; Yang, W. S. & Taiwo, T. A.
Partner: UNT Libraries Government Documents Department