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Thermal analysis of a SNAP-8 type reactor system during atmospheric reentry. Thermo-physics technical note No. 76
A thermal analysis was carried out to determine the temperature distribution in a SNAP-8 type reactor system during atmopsheric reentry. Of particular interest are the temperature distributions in the reactor upper head, the upper grid plate, and the vessel wall. The time and altitude were determined at which the upper head falls away from the reactor core due to having a portion of its wall melted through. The time and altitude of the melting of the upper grid plate and vessel wall were also determined. The effects of reentry attitude or equivalent angle of attack and initial temperature on the thermal behavior of the system were investigated. The computer programs used in various phases of the analysis were NEWTON (drag coefficient), RESTORE (reentry trajectory), and TAP (thermal model).
Date:
July 12, 1966
Creator:
Montgomery, L. D. & Mouradian, E. M.
Object Type:
Report
System:
The UNT Digital Library
Thermo-Physics Technical Note No. 60: thermal analysis of SNAP 10A reactor core during atmospheric reentry and resulting core disintegration and fuel element separation
A thermal analysis is carried out to determine the temperature distribution throughout a SNAP 10A reactor core, particularly in the vicinity of the grid plates, during atmospheric reentry. The transient temperatue distribution of the grid plate indicates when sufficient melting occurs so that fuel elements are free to be released and continue their descent individually.
Date:
February 16, 1966
Creator:
Mouradian, E. M.
Object Type:
Report
System:
The UNT Digital Library
Geologic section and hydrologic observations at station 1A, Tatum salt dome, Lamar County, Mississippi
Station 1A was the emplacement hole for the nuclear device used in the Advanced Research Project Agency's and U.S. Atomic Energy Commission's 5-kT nuclear Salmon Event of October 22, 1964. The hole penetrated the Pascagoula and Hattiesburg Formations, undifferentiated, and the Catahoula Sandstone, all of Miocene age, before entering the caprock at a depth of 882 feet. In continued through the calcite, gypsum, and anhydrite units of the caprock, which extend to a depth of 1,469.5 feet, and terminated in the salt stock at a depth of 2,802 feet. Five sand aquifer units lie above the caprock, whereas one sand aquifier lies within the calcite unit of the caprock. Drilling activities did not cause noticeable water-level fluctuations in the sand aquifers; however, during drilling in the calcite caprock, drilling fluid losses twice caused significant but temporary rises in water level in three observation wells that monitor the calcite limestone aquifer. The microscopic examination of drill cuttings collected at 10-foot intervals to a depth of 1,220 feet in Station 1A is presented. 2 figures, 1 table.
Date:
February 25, 1966
Creator:
Taylor, R.E.
Object Type:
Report
System:
The UNT Digital Library
04 nuclear safety: pressure piping crack monitoring detection of metal overstress by acoustic emission. Progress report, July-September 1966
The three main areas of effort have been: (1) definition of the general acoustic response pattern related to the gross aspects of forming and extending a crack in various materials, (2) development of a monitor system prototype concept exclusive of transducers and (3) development of a suitable, high temperature transducer. Tests using double cantilever beam (DCB) specimens of various materials to establish conditions of crack formation and growth have indicated that material ductility is a major controlling factor in the acoustic response pattern. It appears to effect both acoustic emission intensity and the point in the crack formation-growth sequence at which the main emission occurs. A concept has been developed for the prototype of a full scale monitor system. Hardware development is being limited to the analyzer portion of the system at this time because it is the part most significant to demonstrating feasibility of the intended application. Signal level and signal rate are both being investigated as possible parameters for evaluating acoustic emission data. Of the various transducers for potential high temperature application, the capacitive or electrostatic transducer now looks most promising. A significant improvement in sensitivity has been achieved and a trial model used during recent tests produced …
Date:
October 28, 1966
Creator:
Hutton, P H
Object Type:
Report
System:
The UNT Digital Library
Review of effluent disposal practices in N Reactor Department
A survey has been conducted of current methods of disposal of radioactive, chemical, and sanitary wastes used both at the 100 Area and 300 Area sites of N Reactor Department Operations. In addition, liquid storage facilities have been surveyed for situations which might result in river water pollution. The survey and this report have been prepared in response to the request of the Manager, Richland Operations Office of the Atomic Energy Commission in accordance with Executive Order 11258. An audit of N Reactor Department waste disposal procedures and practices was recently made. The audit report provides detailed data on effluent streams, methods,d and sampling points. Therefore, this report does not include that information and instead provides a summary of experimental and analytical data which have become available since the audit. It also includes information developed in response to specific provisions set forth in the Executive Order.
Date:
February 28, 1966
Creator:
Stepnewski, D. D. & Hendrickson, M. M.
Object Type:
Report
System:
The UNT Digital Library
Chemical Processing Division monthly report, May 1966
This report, from the Chemical Processing Department at HAPO for May 1966, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; and employee-relations, and waste management.
Date:
June 20, 1966
Creator:
Reed, P. E.
Object Type:
Report
System:
The UNT Digital Library
Chemical Disposal to the Columbia River by 100-N Area
As a result of an AEC directive, a review has been made of the disposal of chemicals to the Columbia River by 100-N to determine if any water pollution hazards exist. The search revealed that no chemicals are released continuously in hazardous concentrations; that three cases exist where hazardous concentrations might be released intermittently under worst-case conditions; that two cases exist where intermittent releases result in questionable conditions; and that two cases exist where accidental release from storage might result in hazardous conditions. Recommendations for corrective action are given in all cases.
Date:
March 4, 1966
Creator:
Bainard, W. D.
Object Type:
Report
System:
The UNT Digital Library
Status of special reactor process tube loadings, April 1, 1966
The attached pages show the status of production test control tube loadings in reactor process tubes containing significant amounts of SS materials. For further description of column headings and the current discharge goal exposure plan the reader is referred elsewhere.
Date:
April 11, 1966
Creator:
Bown, R. W.
Object Type:
Report
System:
The UNT Digital Library
Clad thickness variation N-Reactor fuel elements
The current specifications for the cladding on {open_quotes}N{close_quotes} fuels were established early in the course of process development and were predicted on several basic considerations. Among these were: (a) a desire to provide an adequate safety factor in cladding thickness to insure against corrosion penetration and rupture from uranium swelling stresses; (b) an apprehension that the striations in the zircaloy cladding of the U/zircaloy interface and on the exterior surface might serve as stress-raisers, leading to untimely failures of the jacket; and (c) then existing process capability - the need to maintain a specified ratio between zircaloy and uranium in the billet assembly to effect satisfactory coextrusion. It now appears appropriate to review these specifications in an effort to determine whether some of them may be revised, with attendant gains in economy and/or operating smoothness.
Date:
May 12, 1966
Creator:
Smith, E. A.
Object Type:
Report
System:
The UNT Digital Library
Chemical Processing Division monthly report, January 1966
This report, from the Chemical Processing Department at HAPO for January 1966, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; and employee relations.
Date:
February 21, 1966
Creator:
Reed, P. E.
Object Type:
Report
System:
The UNT Digital Library
Chemical Processing Division monthly report, June 1966
This report for June 1966, from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance: Financial operations; facilities engineering; research; and employee relations.
Date:
January 1, 1966
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Chemical Processing Division monthly report, August 1966
This report, from the Chemical Processing Department at HAPO for August 1966, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; and employee-relations, and waste management.
Date:
December 31, 1966
Creator:
Reed, P. E.
Object Type:
Report
System:
The UNT Digital Library
Status of irradiations performed by testing for BNW as of December 13, 1966
This report itemizes the irradiations performed by Testing for Battelle-Northwest Laboratories. It lists the material being irradiated, awaiting disposition and material shipped during the report period.
Date:
December 21, 1966
Creator:
DeMers, A. E.
Object Type:
Report
System:
The UNT Digital Library
Chemical Processing Division monthly report, February 1966
This report, from the Chemical Processing Department at HAPO for February 1966, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; and employee relations.
Date:
March 21, 1966
Creator:
Reed, P. E.
Object Type:
Report
System:
The UNT Digital Library
Outer annulus imbalance study: Mark I fuel
Results of an investigation of fuel element outer annulus enthalpy imbalance are reported and analytical results of suggested methods to limit this imbalance are presented. Also included are comparisons of calculated and experimental enthalpy imbalance ratios along with other quantities. Results indicate that tightening fuel tolerances and clearances can substantially reduce the present outer annulus imbalance thereby increasing power capability. A basic pre-requisite to reduction of clearance between fuel support diameter and process tube diameter is a test establishment of the minimum allowable clearance compatible with charging requirements. Matching fuel elements to process tube diameters will also reduce the imbalance but is in general not feasible at the present time.
Date:
April 26, 1966
Creator:
Long, J. W.
Object Type:
Report
System:
The UNT Digital Library
Thoria target element failures
The thoria program at Hanford was initiated in response to an order placed by the Atomic Energy Commission for the production of uranium-233 from the irradiation of thorium or thorium oxide (thoria). The initial orders called for approximately 130 kg U-233 and subsequent orders have since increased this figure. This report provides a brief history of the thoria program, an analysis of the thoria target element failures which occurred during the irradiation phase, and the significant changes in the fabrication methods and inspection criteria and techniques which were made in response to the large number of failures that occurred in the early stages of the program. The thoria program has sustained 25 thoria target element failures. Eighteen of these failures are believed to have been caused as a result of water entry through fabrication defects in the closure weld. Two of the failures were attributable to water entry through the cladding as a result of charging machine damage, and the remaining five failures were caused by water entry in some undetermined manner. The majority of thoria element failures occurred in the early stages of the program. Upon determining the cause of failure, Production Fuels Section initiated programs to upgrade the …
Date:
April 15, 1966
Creator:
Bowles, K. C. & Schmidt, J. P.
Object Type:
Report
System:
The UNT Digital Library
Transfer measurement statistic derived from Purex processing measurements` quality control program, second half of 1965
This report gives an analysis of the audit data obtained during the last half of 1965 at eight transfer stations: L9 plutonium product, K6 uranium product, F15 salt waste, D5 dissolved feed, F18 utility waste, G8 organic wash waste, R8 organic wash waste, and U3 laboratory waste. Two ways of improving the Purex quality control program are described.
Date:
March 31, 1966
Creator:
Hough, C. G.
Object Type:
Report
System:
The UNT Digital Library
Probability of film boiling burnout
The power of some SRP fuel assemblies is limited by the burnout safety factor (BOSF) in some applications. This power limitation is unnecessarily restrictive, because the current conservatism in predicting film boiling burnout is unusually large compared to that in predicting unstable flow in fuel assemblies. In the past, most SRP fuel assemblies operated at the flow instability limit and were far enough removed from burnout that a convenient and very conservative burnout limit system could be used. If the same degree of safety was used for both burnout and flow instability, the power of BOSF-limited assemblies could be increased. This memorandum, which is part of the program to improve the system for protection against burnout, evaluates the probability and consequences of burnout at various BOSF levels.
Date:
June 15, 1966
Creator:
Towell, R. H.
Object Type:
Report
System:
The UNT Digital Library
Invention Report Process for Separation of Uranium Isotopes
A new concept for separation of the isotopes of uranium has been developed. The invention consists of a new process with essentially no moving parts. The new process is called the Ionized Vapor Process and is described in this report.
Date:
June 7, 1966
Creator:
Brownell, L. E.
Object Type:
Report
System:
The UNT Digital Library
Chemical Processing Division monthly report, October 1966
October performance of the plant production facilities was outstanding (915.2 tons U processed by Purex; 625.4 kg Pu separated by Redox/Purex). Redox processed three types of feed. Operation of incinerator furnace was resumed in Pu finishing processes. Capital cost estimates were prepared for several schemes for power reactor fuel reprocessing in Redox. Redox encased waste lines and line support system were found to be in good condition. H concentration in Redox dissolver off-gases occasionally exceeded lower flammable limits while sodium nitrate from high level waste storage tanks was used to suppress hydrogen.
Date:
November 21, 1966
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Radioactive contamination in liquid wastes discharged to ground at the separations facilities through December, 1965
This document summarizes the amounts of radioactive contamination discharged to ground from chemical separations and laboratory facilities through December 1965. Detailed data for individual disposal sites are presented on a month-to-month basis for the period of January through December 1965. Previous publications of this series are listed in the bibliography and may be referred to for specific information on measurements and radioactivity totals prior to January 1965. Several changes in crib nomenclature were made during 1965. These changes are noted on the individual tables so reference may be made to them in previous reports.
Date:
February 15, 1966
Creator:
McMurray, B. J.
Object Type:
Report
System:
The UNT Digital Library
Comparison of upstream and downstream river temperatures, 1964--1965
Heat discharged to the Columbia River in reactor cooling water is one of the more important pollutants from Hanford operations. The effect of this heat on river temperatures has been studied for several years, primarily because of the potential effect on the Columbia River fisheries. This document presents a summary of recent river temperature experience, with comparison data for a better perspective.
Date:
April 8, 1966
Creator:
Corley, J. P.
Object Type:
Report
System:
The UNT Digital Library
Pacific Northwest Laboratory monthly activities report, August 1966
This document reports on: direct AEC sponsored programs (mainly Columbia River studies and exposure mechanisms), assistance to Douglas United Nuclear (production reactors), assistance to General Electric N-Reactor department, assistance to Isochem (processing), assistance to Hanford occupational health foundation, and technical assistance to Hanford Plant (environment, dosimetry).
Date:
September 1, 1966
Creator:
Paul, R. S.
Object Type:
Report
System:
The UNT Digital Library
WSEP 30-Ton Liquid Transfer Cask: Design Criteria and Performance Tests
Shipment of radioactive wastes in shielded transfer casks is a continuing practice between the 300 Area and the 200 Areas. However, the Waste Solidification Engineering Prototypes (WSEP) located in 324 Building, 300 Area, require the transfer of significant quantities of radioactive wastes. Two new 30-ton casks are being placed in service to accommodate the increased number of shipments. The purpose of this report is to document the design criteria, tests and calculations performed on the casks and modifications to the original cask design to insure its safe use. The design criteria was developed in January 1963 by an ad hoc committee comprised of representatives of the Chemical Processing Department, Hanford Laboratories, and Construction Engineering and Utilities of General Electric Company. The various tests, calculations and modifications of the cask were conducted by the Chemistry Department of Pacific Northwest Laboratory.
Date:
March 30, 1966
Creator:
Cooley, C. R. & Spaeth, M. E.
Object Type:
Report
System:
The UNT Digital Library