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in publisher: "Hanford Atomic Products Operation"  
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open access

Status report of irradiated NPR fuel element rupture studies in the IRP

Description: The Irradiated Rupture Prototype (IRP) has been used for rupture testing irradiated NPR prototype fuel elements. Most of the tests have been made to determine the rupture effect of different reactor exposures, fuel element geometries and water cooldown rates following the start of the rupture. This report summarizes the results obtained to date, mentions where information is lacking and gives further tests scheduled for the IRP.
Date: September 9, 1963
Creator: Hayden, K.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Temperature Measurement in Operating Reactors: In-Reactor Temperature Measurement Associated With Fuel Element Testing

Description: The Fuel Development operation at Hanford uses a variety of in-reactor facilities to test experimental and prototypical fuel elements. High pressure-high temperature water loops in constant use are the 6 in. {times} 9 in. ETR core facility, the 3 in. {times} 3 in. ETR reflector facility and four front-to-rear loops in the 100-K East reactor at Hanford. Low pressure water cooled test facilities in use are located in the MTR the various Hanford reactors. Stainless steel sheathed the thermocouples… more
Date: December 9, 1959
Creator: Wheeler, R. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Design and fabrication of target elements for PT-645-D

Description: Target elements were designed and built to fit into 1.25% U{sup 235} driver elements. These targets had an aluminum -- 0.583% lithium alloy core enriched to 63.5% in Li. The targets had a coextruded aluminum jacket as a tritium barrier and a Zircaloy jacket as a corrosion barrier to the 300 C reactor water.
Date: March 9, 1964
Creator: Tverberg, J. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Critical mass control: Continuous neptunium

Description: During April 1962, equipment in both the main Redox Building (202-S) and the Plutonium Concentration Building (233-S) vas rearranged to allow the accumulation and recovery of neptunium without interference with the production of uranium and plutonium. In order to do this, the former rework column (1S) was put into continuous service as a neptunium recovery column, the Third Plutonium Cycle was converted to a neptunium decontamination cycle, and ion-exchange equipment was installed in the 233-S … more
Date: May 9, 1962
Creator: Barnes, R. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Conversion ratio consideration in the E-N fringe loading

Description: This document summarizes the requested study of theoretical factors influencing the expected conversion ratio of the fringe enrichment portion of an E-N loading. Exact calculation of the quantity is very complicated and will not be attempted here; however, it is possible, with simple geometric approximations, to derive relative conversion ratios. This present report summarizes the results of a study incorporating actual operating data from the present poisoned top and unpoisoned bottom fringe l… more
Date: January 9, 1961
Creator: Bowers, C. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Production test IP-416 horizontal rod calibrations, H Reactor

Description: The purpose of this test is to obtain data concerning the reactivity effect of horizontal control rods in the E-N loading at H Reactor. The accurate calibration of the control rods will then provide more accurate measurement of the other reactivity variables associated with the E-N loading.
Date: June 9, 1961
Creator: Vaughn, A. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

In-reactor corrosion: A paper presented at the 9th annual AEC Corrosion Symposium, Boston, Massachusetts, May 10--12, 1960

Description: Object of this paper is to present preliminary results of experiments in Hanford in-reactor loops to determine if exposure to neutrons will increase corrosion rates of Al alloys, Zy-2, and 304 stainless steel. Results were negligible or no corrosion.
Date: May 9, 1960
Creator: Larrick, A. P.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Use of control charts for analysis of plant rupture experience

Description: Goal exposure and power level planning and administration on either a short-term or long-term basis, is heavily dependent upon assessment of the level of metal performance. It is the purpose of this document to present a method of monitoring the metal performance level employing the concept of control charts, and to propose adoption of this method as the basis for detecting changes in the metal performance level of the three main types of production fuel elements, i.e., C-II-N, O-II-N, and K-II… more
Date: June 9, 1960
Creator: Bloomstrand, R. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Chemical Processing Department 200 West Area Tank Farm Inventory and Waste Reports

Description: This document lists all tanks which were active during each month by Waste Farm, which includes all tanks to which additions or subtractions were made. Each type of waste was indicated in each case, along with the nature of transfer and any pertinent remarks. Also reported are gallonage and inches of liquid in each tank.
Date: September 9, 1964
Creator: Bayless, M. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Design criteria for coolant backup three remaining smaller reactors. Revision 1

Description: This document defines the objectives, bases, and functional requirements that shall govern the preparation of design of the coolant backup system for the three remaining smaller reactors. This project will increase the reliability of the coolant backup facility at B Area by providing an independent last-ditch coolant system to B and C Reactors. The reliability of the last-ditch system for D Reactor will also be improved in that the present F and H leg of the export system will no longer be a pa… more
Date: June 9, 1964
Creator: Brinkman, L. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Production test IP-477-A, irradiation of N Reactor fuel elements in KER Loops 3 and 4

Description: The objective of this production test is to evaluate the irradiation behavior of N Reactor fuel elements at conditions equivalent to or more severe than those expected in N Reactor. N Reactor fuel elements are authorized for irradiation in KER Loops 3 and 4 to exposures no greater than 3000 MWD/T. Tubular steel spacers, per steel spacers, solid steel dummies, and a flow channel temperature measuring thermocouple train are authorized for use in KER loops 3 and 4 to permit positioning the fuel el… more
Date: January 9, 1962
Creator: Kratzer, W. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

PT IP-205-A: Irradiation of Zircaloy-2 jacketed rod-and-tube elements in the KER Loops

Description: The objective of the production test is detailed in this report is to obtain information about the behavior of Zircaloy-2 jacketed rod-and-tube fuel elements during irradiation at high coolant temperatures specifically, this test should provide information about fuel element dimensional stability, suitability of the rod and tube support system, and behavior of the uranium--Zircaloy-2 bond. Four co-extended Zircaloy-2 jacketed rod-and-tube elements, two with welded tube end closure and two with … more
Date: October 9, 1958
Creator: Kratzer, W. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Irradiation performance of enriched uranium clad in stainless steel: PT-IP-123-A. Final report

Description: Early in the development of an extended surface fuel element for use in the NPR, several 7-rod cluster fuel elements were irradiated to determine the dimensional stability of such geometries at high burnups. These elements were fabricated from small diameter uranium rods clad unbonded in stainless steel tubes and assembled in a rod cluster geometry by various support devices. Zircaloy clad fuel rods were not yet available, the stainless steel clad rods therefore served as a suitable material wh… more
Date: June 9, 1959
Creator: Claudson, T. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Empirical plutonium constants 7090 program

Description: The current-revision of the Process Optimization Program contains two empirical plutonium-exposure expressions. One relates total Pu conversion to exposure and the other, Pu-240 buildup to exposure. The former was incorporated to save computer time and the latter to provide product quality data. Both of these relationships, in addition to a third which relates Pu-241 buildup to exposure, are used in PULP-3, the data generator for LP-90. EMCON-3, a 7090 computer program which determines arbitrar… more
Date: December 9, 1963
Creator: Jensen, R. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Venturi throat diameter and process tube connector cavitation analysis CG-654

Description: When a ``K`` type process tube is operated without a slug column, damage may take place in the connector because of the cavitation that originates in the venturi. Reported here is a study of this cavitation problem as related to CG-654 operating conditions. A series of curves were developed to present the effect of the venturi diameter on the venturi {Delta}P for instrument operation and on the cavitation problem at the higher flows which are experienced when the tube is operated without a slug… more
Date: July 9, 1956
Creator: Morris, W. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Composition of Purex dissolver off-gas

Description: The composition of dissolver off-gas was determined for seven different dissolvings of uranium in nitric acid (both with one and two dissolvers in operation) at irregular intervals during February, March, and April, 1958. Samples were taken at the Purex 293-A facility absorber inlet, scrubber inlet, and scrubber discharge. The absorber was operated with and without reflux, and the scrubber was operated with water or with approximately 10% sodium hydroxide. This memorandum describes the sampling… more
Date: June 9, 1958
Creator: Facer, J. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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