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X-ray gauge monitoring of LLNL replica carbon production process

Description: This report contains results of a series of x-ray gauging measurements performed on bars tracked through the LLNL replica carbon production process. We were tasked with monitoring a few salt bars through the entire production process to identify any possible problem areas. The process consists of five major steps: pressing fine sodium chloride crystals into a uniform salt bar, sintering the salt bar, infusing the bar with a phenolic polymer solution and convection oven drying it to remove the a… more
Date: December 1, 1990
Creator: Lewis, D.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Thermal striping of a rod: Thermoelastic solution for sinusoidal fluid temperature

Description: A numerical solution is obtained for the one-dimensional temperature distribution in a rod which is assumed to be immersed in a fluid of sinusoidally-varying temperature. Readily available stress equations are combined with the thermal solution to perform a structural analysis in which all stresses are assumed to be within the elastic limit of the material. This leads to a parametric set of dimensionless curves which explain the interaction of the relevant parameters, such as the rod size and m… more
Date: January 1, 1990
Creator: Feldman, E. E.; Chang, L. K. & Lee, M. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Criticality experiments with fast flux test facility fuel pins

Description: A United States Department of Energy program was initiated during the early seventies at the Hanford Critical Mass Laboratory to obtain experimental criticality data in support of the Liquid Metal Fast Breeder Reactor Program. The criticality experiments program was to provide basic physics data for clean well defined conditions expected to be encountered in the handling of plutonium-uranium fuel mixtures outside reactors. One task of this criticality experiments program was concerned with obta… more
Date: November 1, 1990
Creator: Bierman, S.R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Reactor operation safety information document

Description: The report contains a reactor facility description which includes K, P, and L reactor sites, structures, operating systems, engineered safety systems, support systems, and process and effluent monitoring systems; an accident analysis section which includes cooling system anomalies, radioactive materials releases, and anticipated transients without scram; a summary of onsite doses from design basis accidents; severe accident analysis (reactor core disruption); a description of operating contract… more
Date: January 1, 1990
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Method of calculating test leakage rate for a spent fuel cask

Description: This report presents a method for calculating containment test leakage rates of radionuclides from an example spent fuel cask. Three releasable radioactive sources are considered: residual contamination in the cask cavity, crud on the fuel elements, and the radionuclides within the fuel rods. The ANSI N14.5 standard is used to calculate the test leakage rates from the maximum permissible releases determined from 10 CFR 71 containment requirements. 6 refs., 2 tabs.
Date: June 13, 1990
Creator: Fischer, L. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Results of the DF-4 BWR (boiling water reactor) control blade-channel box test

Description: The DF-4 in-pile fuel damage experiment investigated the behavior of boiling water reactor (BWR) fuel canisters and control blades in the high temperature environment of an unrecovered reactor accident. This experiment, which was carried out in the Annular Core Research Reactor (ACRR) at Sandia National Laboratories, was performed under the USNRC's internationally sponsored severe fuel damage (SFD) program. The DF-4 test is described herein and results from the experiment are presented. Importa… more
Date: October 1, 1990
Creator: Gauntt, R.O. & Gasser, R.D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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West Valley Facility Spent Fuel Handling, Storage, and Shipping Experience

Description: The result of a study on handling and shipping experience with spent fuel are described in this report. The study was performed by Pacific Northwest Laboratory (PNL) and was jointly sponsored by the US Department of Energy (DOE) and the Electric Power Research Institute (EPRI). The purpose of the study was to document the experience with handling and shipping of relatively old light-water reactor (LWR) fuel that has been in pool storage at the West Valley facility, which is at the Western New Y… more
Date: November 1, 1990
Creator: Bailey, W. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Requirements for Canisters Used for Delivery of Spent Nuclear Fuel and Associated Materials to DOE (Department of Energy) Under Standard Disposal Contracts

Description: The Department of Energy (DOE) is studying prospective changes to the waste acceptance criteria contained in the Standard Contract which involve consideration of the possible acceptance of failed fuel, consolidated fuel rods, compacted structural parts resulting from at reactor consolidation operations, and other non-fuel bearing materials on the same scheduling basis as used for standard fuel under the existing Standard Contract. During the course of these studies it has become clear that all … more
Date: June 1, 1990
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

TREAT (Transient Reactor Test Facility) reactor control rod scram system simulations and testing

Description: Air cylinders moving heavy components (100 to 300 lbs) at high speeds (above 300 in/sec) present a formidable end-cushion-shock problem. With no speed control, the moving components can reach over 600 in/sec if the air cylinder has a 5 ft stroke. This paper presents an overview of a successful upgrade modification to an existing reactor control rod drive design using a computer model to simulate the modified system performance for system design analysis. This design uses a high speed air cylind… more
Date: January 1, 1990
Creator: Solbrig, C. W. & Stevens, W. W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Analysis and evaluation of ZPPR (Zero Power Physics Reactor) critical experiments for a 100 kilowatt-electric space reactor

Description: ZPPR critical experiments were used for physics testing the reactor design of the SP-100, a 100-kW thermoelectric LMR that is being developed to provide electrical power for space applications. These tests validated all key physics characteristics of the design, including the ultimate safety in the event of a launch or re-entry accident. Both the experiments and the analysis required the use of techniques not previously applied to fast reactor designs. A few significant discrepancies between th… more
Date: January 1, 1990
Creator: McFarlane, H. F.; Collins, P. J.; Carpenter, S. G.; Olsen, D. N.; Smith, D. M.; Schaefer, R. W. (Argonne National Lab., Idaho Falls, ID (USA)) et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Fuel Consolidation Demonstration: Consolidation Concept Development

Description: EPRI, Northeast utilities Service Company (NUSCO), DOE, Baltimore Gas Electric Company, and Combustion Engineering, Inc. (C-E) are engaged in a program to develop a system for consolidating spent fuel, in which the consolidated fuel will be licensable by NRC for storage in the spent-fuel storage pool. Fuel consolidation offers a means of substantially increasing the capacity of spent-fuel storage pools. Consolidation equipment design, development, construction, and testing are being performed b… more
Date: February 1, 1990
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fuel Consolidation Demonstration Program: Final Report

Description: EPRI, Northeast Utilities, Baltimore Gas and Electric, the US Department of Energy and Combustion Engineering are engaged in a program to develop a system for consolidating spent fuel and a method of storing the consolidated fuel in the spent fuel storage pool which is licensable by the US Nuclear Regulatory Commission. Fuel consolidation offers a means of substantially increasing the capacity of spent fuel storage pools. This is a final report of the Fuel Consolidation Demonstration Program. I… more
Date: June 1, 1990
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Criticality Experiments With Neutron Flux Traps Containing Voids

Description: A research program was initiated for the US Department of Energy (DOE) by the Sandia National Laboratory Transportation Systems Development Department in 1982 to provide benchmark type experimental criticality data in support of the design and safe operations of nuclear fuel transportation systems. The overall objective of the program is to identify and provide the experimental data needed to form a consistent, firm, and complete data base for verifying calculational models used in the critical… more
Date: April 1, 1990
Creator: Bierman, S.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Finite element models to predict the structural response of 120-mm sabot/rods during launch

Description: Numerical modeling techniques in two- and three-dimensions were used to predict the structural and mechanical behavior of sabot/rod systems while inbore and just after muzzle exit. Three-dimensional transient numerical simulations were used to predict the rod deformations and states of stress and strain caused by axial and lateral accelerations during launch. The numerical models include the launch tube, recoil motion, and sabot/rod system modeled as it transits the launch tube and exits. The s… more
Date: January 1, 1990
Creator: Rabern, D. A. (Los Alamos National Lab., NM (USA)) & Bannister, K. A. (Army Armament Research and Development Command, Aberdeen Proving Ground, MD (USA). Ballistics Research Lab.)
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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