8 Matching Results

Search Results

Results: 1 - 8
open access

One-group xenon reactivity calculations

Description: A study was initiated in the Pile Physics Unit to evaluate current methods for prediction of xenon behavior in light of newer operating conditions, and thus possibly improve the critical prediction accuracy. Particular areas considered included: (1) validation and limitations of the flux-squared weighting technique for homogenizing localized xenon effects, (ii) effect of elevated graphite temperature on xenon poisoning, (iii) xenon poisoning in the dry lattice, (iv) xenon-control rod interactio… more
Date: March 2, 1964
Creator: Fredsall, J. R. & Bowers, C. E.
Partner: UNT Libraries Government Documents Department
open access

Results of thermal-hydraulic experiments with KVNS self-supported fuel in a Zircaloy tube -- K Reactors

Description: This document presents laboratory data pertaining to the heat-transfer and fluid-flow conditions within a K Reactor process channel using self-supported fuel and a ribless Zircaloy coolant tube. Data are included to show the steady-state hydraulic-demand characteristics during normal conditions and during conditions which simulate a slow flow reduction by plugging upstream of the Panellit pressure tap.
Date: March 2, 1964
Creator: Waters, E. D. & Shockley, M. E.
Partner: UNT Libraries Government Documents Department
open access

Fabrication of enriched hot die sized diffusion bonded fuel elements for Production Test IP-616-A

Description: Hot die sizing (HDS) is a process being investigated to replace the existing AlSi brazing process. Hot die sizing consists of sizing a nickel-plated core and aluminum can assembly with cold dies to produce a diffusion bonded aluminum clad fuel element. Upon completion of fabrication of the first natural uranium hot die sized fuel elements for production test IP-546-A, the next step in evaluation of the process was to assemble enriched fuel for further irradiation testing. This report summarizes… more
Date: October 2, 1964
Creator: Strand, C. A.
Partner: UNT Libraries Government Documents Department
open access

An Engineering Method for Calculating Protection Afforded by Structures Against Fallout Radiation

Description: From Introduction: "The purpose of the paper is to discuss the assumptions and the reasoning by which the calculations described in the Engineering Manual were derived from the data in [1]. The relevant curves from [1] are given in Appendix A and the technical charts from the Engineering Manual are given in appendix B."
Date: July 2, 1964
Creator: Eisenhauer, Charles
Partner: UNT Libraries Government Documents Department
open access

The Thermal Conductivity of Uranium Monocarbide

Description: Uranium carbide shows promise as a fuel material for reactors operating at relatively high temperatures based on its high melting point, high uranium density and high thermal conductivity. Before refined reactor designs can be made, however, good quantitative data on the thermal conductivity at temperatures in excess of 1000C is required. This technical report presents data gathered as part of a continuing study aimed at determining the thermal conductivity of refractory uranium fuels as a func… more
Date: April 2, 1964
Creator: Sobon, J. T.; Miller, A. D. & DeCrescente, M. A. (Michael A.)
Partner: UNT Libraries Government Documents Department
Back to Top of Screen