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SNAP Programs: Task 6--Fuel Technology Development Program. Quarterly Progress Report No. 7, April 1 Through June 30, 1961

Description: Progress made in the development of isotope power sources for thermoelectric and thermionic conversion to electrical energy is reported. The Heavy Elements Processing Facility for processing americium and fabricating americium capsules for irradiation was opened and hot operation was begun. Modifications to the americium purification system were completed and checkout operations were begun. Process specifications were established for dissolution of the irradiated capsules and the major equipmen… more
Date: October 31, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Quarterly Status Report on LAMPRE Program for Period Ending May 20, 1962

Description: During the report period 110 Mw-hr of operation were completed by LAMPRE I at various power levels, and observations were made of control element performance and reactivity losses. Metallographic examination of a Core I capsule having 120 Mw-hr of irradiation exposure disclosed no major attack. Core II utilizes Ta alloy melts and 13 fuel melts. Starting materials for Core II capsules are tabulated. In research and development a gamma-ray conversion television was used to observe the flow of mol… more
Date: June 1, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

HRT-CHEMICAL PLANT RUN 21 SUMMARY

Description: The multiple hydroclone system removed l83 grams of corrosion product solids in l814 hours of operation during reactor run 2l. The low removal rate was attributed to plugging of multiclone feed ports that presumably occurred during the latter part of run 20. After modifications to the reactor core and removal of the multiclone unit at the end of run 21, the reactor core was backflushed with the flow direction in the core loop reversed. During this period, the single hydroclone removed 205 grams… more
Date: February 12, 1962
Creator: Yarbro, O.O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Spert I Destructive Test Program Safety Analysis Report

Description: The water-moderated core used for destructive experiments is mounted in the Spent I open-type reactor vessel, which has no provision for pressurization or forced coolant flow. The core is an array of highly enriched aluminum clad, plate-type fuel assemblies, using four bladetype, gang-operated control rods. Reactor transients are initiated at ambient temperature by step-insentions of reactivity, using a control rod which can be quickly ejected from the core. Following an initial series of stati… more
Date: June 15, 1962
Creator: Spano, A. H. & Miller, R. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Selection of Core Design No. 1 for Type 5 Replacement Cores in SM-1 and SM-1A

Description: Nuclear and thermal analyses were performed to determine the characteristics of the Type 5 core in the SM-1 and SM-1A reactor plants as a function of geometry and composition. The following nuclear properties were investigated: core energy release, maximum midlife reactivity, average fuel burnup fraction, B-10 reactivity coefficient, and power distribution. Thermal parameter surveys determined the effects of channel thickness and power distribution upon the DNBR, nominal and hot channel thermal… more
Date: July 1, 1962
Creator: Davidson, S. L. & Paluszkiewicz, S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

12-INCH SODIUM FLOW CONTROLLER. Technical Manual 20357

Description: A manual is presented for the Sodium Flow Controller used in controlling flow to regulate heat transfer in a liquid metal nuclear power plant. A description of the controller, general installation and operational pointers, installation instructions, instructions for dismantling of the Sodium Flow Controller, instructions for assembly of Sodium Flow Controller, list of special tools and fixtures, and repair parts list are given. (M.C.G.)
Date: October 31, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Bench-Scale Natural-Recirculation Dissolver

Description: A natural-recirculation dissolver closely approaching a stirred-tank reactor in behavior was developed, and its feasibility was demonstrated in the mercury-catalyzed dissolution of aluminum in nitric acid, It was designed to utilize the heat of reaction and evolution of gaseous reaction products for recirculation and mixing. The dissolvent was 5-molar nitric acid, containing mercury in concentrations from 10/sup -4/ to 10/sup -3/ molar as a catalyst. Dissolution rates for 1/7 scale, simulated M… more
Date: January 10, 1962
Creator: Erickson, E. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Organic Coolant Reactor Program Quarterly Report, January 1-March 31, 1962

Description: The possible effects of a hydrogen atmosphere in reducing film deposition were studied in the large circulating loop and in rocking cell and pyrolytic capsule tests. At H/sub 2/ pressures of 200 to 400 psig no reduction in film weight deposited was observed in the loop tests, and in the pyrolytic tests film deposits were doubled. Heat conductivity of the films was much higher however. ln these high ash films the inorganic constituent was found to be alpha -Fe rather than the usual magnetite, wh… more
Date: June 29, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

DESIGN REPORT FOR NMSR PRESSURIZED WATER LOOP AT ORR

Description: A pressurized water loop constructed in the Oak Ridge Research Reactor for use in the Maritime Reactor Program is described. irradiation testing of pressure vessel materinl specimens and several sets of fuel pins for the NS Savannah'' Nuclear Merchant Ship Reactor, NMSR, was completed. Operating conditions for the fuel tests nominally were 500 deg F and 1750 psig. The loop has capability for operation at 650 deg F, 2500 psig, with a maximum water flow rate of 80 gpm, and heat removal in excess … more
Date: January 1, 1962
Creator: Dudley, I.T.; Tidwell, D.E. & Trauger, D.B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

BOILING WATER REACTOR TECHNOLOGY STATUS OF THE ART REPORT. VOLUME I. HEAT TRANSFER AND HYDRAULICS

Description: >Information on heat transfer and hydraulics pertinent to the design and operation of boiling water reactor power plants is presented. The following areas of discussion are covered: heat transfer, two-phase density studies, twophase pressure drop, critical heat flux and burnout, boiling stability, calculation procedures for boiling systems, and thermal-hydraulic design procedures for boiling water reactors. (M.C.G.)
Date: February 1, 1962
Creator: Lottes, P.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Spiral Boiler Evaluation

Description: The results of the boiler optimization are as follows: Approximate boiler weight (filled with NaK and Hg under operating conditions), 102 lbs; tube length, 68 ft; tube ID, 0.587 in.; surface-to-volume ratio, 25 ft/sup -1/. The results of the boiler evaluation indicate that the centrifugal force produced by the spiraling effect is only 1/10 that produced by twisted strip turbulators. Published data indicate that twisted strips do not appreciably increase pressure drop for equivalent weight flow … more
Date: November 1, 1962
Creator: Wendt, J. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

CRYOGENIC TECHNOLOGY IN THE NUCLEAR ROCKET PROGRAM

Description: Nuclear rocket development problems have resulted primarily from the stringent operational requirements of designing a reactor with optimized parameters of core temperature, rapid start-up capability, ability to withstand extreme temperature gradients, and minimum weight. Disasterous consequences resulting from the entrance of appreciable amounts of liquid hydrogen in the reactor core during start up was feared. Efforts to program the start-up such as to increase the reactor power simuitaneousl… more
Date: January 1, 1962
Creator: Hammel, E.F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fuel Element Flow Blockage in the Engineering Test Reactor

Description: On December 12, 196l, the Engineering Test Reactor experienced fuel fission breaks which resulted from obstructions to the flow of cooling water through several fuel elements. A total of six fuel elements had breaks in from one to eight fuel plates. A discussion and description of damage to the fuel is presented. The reactor operating conditions preceding the break are described, including events immediately before the manual scram. Results of investigations conducted after the scram, including… more
Date: May 10, 1962
Creator: Keller, F. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Preliminary Stress and Fatigue Analysis of the SM-1 Primary System

Description: A preliminary analysis of the SM-1 primary system showed it-was safe from strain cycling damage with the possible exception of steam generator tube sheet and primary pump casing. These are recommended for further analysis. (auth)
Date: March 31, 1962
Creator: Chittum, R. A.; Knipe, R. K. & McLaughlin, D. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Chemical Processing Technology Quarterly Progress Report, July-September 1962

Description: Aqueous zirconium fuel processing studies, directed at adapting the hydrofluoric acid process to continuous dissolution-complexing in order to increase the capacity of the ICPP process, resulted in two successful approaches to the complexing-feed adjustment step. Continuous in-line adjustment (conversion of uranium(IV) to uranium(VI) necessary for extraction) was accomplished in one minute or less at approximately 90 deg C; surges of dissolver product from the operating dissolver up to 1.9 time… more
Date: December 28, 1962
Creator: Bower, J.R. ed.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

EOCR CONTROL ROD AND DRIVER FUEL HYDRAULIC TESTS

Description: The EOCR prototype control rod, control rod drive, and driver fuel assembly were extensively tested in 500 deg F Santowax and 132 deg F water. These tests not only established the operating characteristics of these assemblies but also revealed a number of deficiencies in the various components. The modifications required were tested to establish the satisfactory performance of the modified components. Flow versus pressure differential measurements were performed on the driver fuel and the contr… more
Date: October 19, 1962
Creator: Harrison, L. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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