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Title: HOMOGENEOUS REACTOR PROGRAM QUARTERLY PROGRESS REPORT FOR PERIOD ENDING JANUARY 31, 1960

Abstract

8 < @ M 6 A ? = < 7 8 8 : 7 operated continuously for 105 days and generated approximately 5600 Mwh(th). The major objective of the run was the investigation of fuel stability. The multiclone- hydroclone solids separation system was operated in two periods for a total of 410 hr in mn 21. Solids removal rates were a factor of 3 to 5 lower than in comparable periods in run 20, substantiating earller evidence that the malfunction which was indicated later in mn 20 was not corrected by replacement of the hydroclone with a spare prior to run 21. The nenon poisoning at 5 Mw was 0.95%. The Zircaloy wear rings of a test pump ignited while the pump was being operated as a steam-onygen blower with rubbing contact of the wear rings. A universal periscope manipulator which provides for gear-driven movements and smooth rotation of various optical core-inspection devices was designed, constructed, and tested. Tests of a Laud Electrcoaloric flowmeter revealed that the fluctuations in indicated flow rates observed were due to oscillutions produced by a large distance-velocity lag which is present at low flow rates. Radiation tests of a miniature television camera were reported bymore » using nonknowning lens; 9.6 x 10/sup 7/ r of gamma radiation was accumulated over a period of 248.5 hr. Reactor Analysis and Engineerin g Development. A two-group, two-dimensional criticallty calculation for cylindrical geometry was programmed for the IBM-704. The stator of the 20-cfm blower was examined and was found to have failed by the short to ground of a stator slot. Failures of the third-stage diaphragm of the oxygen compressor, for reoycllng contamnated gas, are reported. Calculations were made of the temperature distribution in a 4-by-12-ft cyllndrical core with strrightthrough flow. The preliminary mecharical design of a 380 Mw (thermal) two-region breeder reactor having a slurry blanket and solution core was completed. Effects of ThO/sub 2/ concentration, temperature, and flow rate on the homogeneity of slurry flowing in a horizontal 31/2-in. pipe are being studied. In order to investigate the caking and plugging observed with mixed U--Th oxide inrun 3B, nun 4B was iritiated with a pure 1600 deg C-fired ThO/ sub 2/ believed immune to caking and plugging. As pant of a program to test and evaluate electronic instrumentation systems for possible use in future reactor systems, a Foxboro model M/62 universal controller was tested. Sample coupons of Coors Porcelain Company Al/sub 2/O/sub 3/ wene tested in hightemperature oxygenated water to determine the suitability of Al/sub 2/O/sub 3/ for use as a liner material for magnetic flowmeters. A prototype flush-diaphragm differential- pressure transmitter was tested. Solution Fuels. The response of typical reactor fuel solutions to the sudden addition of H/sub 2/O/sub 2/ or solid uranium peronide was investigated. The maximum permissible power density for a homogeneous reactor solution was related to the uranyl ion concentration, the acidity the UO/sub 4/ solubility, and the equilibrium constant. Laboratory experiments to determine temperatures of immiscibility for synthetic HRT fuels and their concentrates were continued. Over-all aolubility data are presented for the system UO/sub 3/--CuO--NiO--SO/sub 3/--H/sub 2/O, its D/sub 2/O analog, and its included four- and three-component systems. The effect of the mole ratio, UO/sub 3//SO/sub 3/, on immiscibility temperatures of 0.02, 0.05, and 0.20 m SO/sub 3/ solutions was determined. The critical velocity for cast type CD4MCU stainless steel was shown to be about the same as that for cast type 347 stainless steel in 0.04 m UO/sub 2/SO/sub 4/, 0.025 m D/sub 2/SO/sub 4/, 0.002 m CuSO/sub 4/ at 250 deg C. Batch-type experiments were performed to study the sorption of U on hydrous zirconium oxide from UO/sub 2/SO/sub 4/ solutions at 250 deg C. Slurry Fuels. The rheological characteristics of two suspensions of spherical ThO/sub 2/ particles were detormined for comparison with earlier results on irregularly cnystalline ThO/sub 2/. The effects of slurry velocity and confining-metal surface on« less

Publication Date:
Research Org.:
Oak Ridge National Lab., Tenn.
OSTI Identifier:
4153041
Report Number(s):
ORNL-2920
NSA Number:
NSA-14-018647
DOE Contract Number:  
W-7405-ENG-26
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-60
Country of Publication:
United States
Language:
English
Subject:
REACTOR TECHNOLOGY; CAMERAS; FLUID FLOW; FUELS; HOMOGENEOUS REACTORS; HRT; INSPECTION; IRRADIATION; OPERATION; OPTICAL SYSTEMS; OSCILLATIONS; PLANNING; POISONING; POWER; PUMPS; REACTORS; REMOTE HANDLING; SEPARATION PROCESSES; SOLIDS; STABILITY; TELEVISION; TESTING; WEAR; XENON; ZIRCONIUM

Citation Formats

. HOMOGENEOUS REACTOR PROGRAM QUARTERLY PROGRESS REPORT FOR PERIOD ENDING JANUARY 31, 1960. United States: N. p., 1960. Web.
. HOMOGENEOUS REACTOR PROGRAM QUARTERLY PROGRESS REPORT FOR PERIOD ENDING JANUARY 31, 1960. United States.
. 1960. "HOMOGENEOUS REACTOR PROGRAM QUARTERLY PROGRESS REPORT FOR PERIOD ENDING JANUARY 31, 1960". United States.
@article{osti_4153041,
title = {HOMOGENEOUS REACTOR PROGRAM QUARTERLY PROGRESS REPORT FOR PERIOD ENDING JANUARY 31, 1960},
author = {},
abstractNote = {8 < @ M 6 A ? = < 7 8 8 : 7 operated continuously for 105 days and generated approximately 5600 Mwh(th). The major objective of the run was the investigation of fuel stability. The multiclone- hydroclone solids separation system was operated in two periods for a total of 410 hr in mn 21. Solids removal rates were a factor of 3 to 5 lower than in comparable periods in run 20, substantiating earller evidence that the malfunction which was indicated later in mn 20 was not corrected by replacement of the hydroclone with a spare prior to run 21. The nenon poisoning at 5 Mw was 0.95%. The Zircaloy wear rings of a test pump ignited while the pump was being operated as a steam-onygen blower with rubbing contact of the wear rings. A universal periscope manipulator which provides for gear-driven movements and smooth rotation of various optical core-inspection devices was designed, constructed, and tested. Tests of a Laud Electrcoaloric flowmeter revealed that the fluctuations in indicated flow rates observed were due to oscillutions produced by a large distance-velocity lag which is present at low flow rates. Radiation tests of a miniature television camera were reported by using nonknowning lens; 9.6 x 10/sup 7/ r of gamma radiation was accumulated over a period of 248.5 hr. Reactor Analysis and Engineerin g Development. A two-group, two-dimensional criticallty calculation for cylindrical geometry was programmed for the IBM-704. The stator of the 20-cfm blower was examined and was found to have failed by the short to ground of a stator slot. Failures of the third-stage diaphragm of the oxygen compressor, for reoycllng contamnated gas, are reported. Calculations were made of the temperature distribution in a 4-by-12-ft cyllndrical core with strrightthrough flow. The preliminary mecharical design of a 380 Mw (thermal) two-region breeder reactor having a slurry blanket and solution core was completed. Effects of ThO/sub 2/ concentration, temperature, and flow rate on the homogeneity of slurry flowing in a horizontal 31/2-in. pipe are being studied. In order to investigate the caking and plugging observed with mixed U--Th oxide inrun 3B, nun 4B was iritiated with a pure 1600 deg C-fired ThO/ sub 2/ believed immune to caking and plugging. As pant of a program to test and evaluate electronic instrumentation systems for possible use in future reactor systems, a Foxboro model M/62 universal controller was tested. Sample coupons of Coors Porcelain Company Al/sub 2/O/sub 3/ wene tested in hightemperature oxygenated water to determine the suitability of Al/sub 2/O/sub 3/ for use as a liner material for magnetic flowmeters. A prototype flush-diaphragm differential- pressure transmitter was tested. Solution Fuels. The response of typical reactor fuel solutions to the sudden addition of H/sub 2/O/sub 2/ or solid uranium peronide was investigated. The maximum permissible power density for a homogeneous reactor solution was related to the uranyl ion concentration, the acidity the UO/sub 4/ solubility, and the equilibrium constant. Laboratory experiments to determine temperatures of immiscibility for synthetic HRT fuels and their concentrates were continued. Over-all aolubility data are presented for the system UO/sub 3/--CuO--NiO--SO/sub 3/--H/sub 2/O, its D/sub 2/O analog, and its included four- and three-component systems. The effect of the mole ratio, UO/sub 3//SO/sub 3/, on immiscibility temperatures of 0.02, 0.05, and 0.20 m SO/sub 3/ solutions was determined. The critical velocity for cast type CD4MCU stainless steel was shown to be about the same as that for cast type 347 stainless steel in 0.04 m UO/sub 2/SO/sub 4/, 0.025 m D/sub 2/SO/sub 4/, 0.002 m CuSO/sub 4/ at 250 deg C. Batch-type experiments were performed to study the sorption of U on hydrous zirconium oxide from UO/sub 2/SO/sub 4/ solutions at 250 deg C. Slurry Fuels. The rheological characteristics of two suspensions of spherical ThO/sub 2/ particles were detormined for comparison with earlier results on irregularly cnystalline ThO/sub 2/. The effects of slurry velocity and confining-metal surface on},
doi = {},
url = {https://www.osti.gov/biblio/4153041}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1960},
month = {4}
}

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