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ARMY GAS-COOLED REACTOR SYSTEMS PROGRAM. INITIAL FULL POWER AND LIMITED ENDURANCE TESTS OF THE ML-1 NUCLEAR POWER PLANT. Final Test Report

Description: The evaluation of the data generated during the full power and limited endurance tests of the ML-1 mobile nuclear power plant indicates that the reactor performs in accordance with the design specifications. During the 101 hr test period, the reactor attained a maximum power of 3.44 Mw( and 247 kw(e) was measured at the output shaft of the turbine-compressor set. No operating limits were exceeded during these tests and all systems performed satisfactorily Except for the known performance deficiency of the turbinecompressor set, which prevented the attainment of design output power, no operational, stability, or control problems were encountered. All test objectives were achieved and the tests were considered completely successful. (auth)
Date: July 1, 1963
Creator: Kattchee, N.
Partner: UNT Libraries Government Documents Department

ARMY GAS-COOLED REACTOR SYSTEMS PROGRAM. Monthly Progress Report for April 1959

Description: The Army Gas Cooled Reactor System Program includes water moderated heterogeneous reactor (Gas Cooled Reactor Experiment I), a graphite moderated homogeneous reactor (Gas Cooled Reactor Experiment II), a mobile gas cooled reactor (ML-1), and the co ordination of thc Gas Turbine Test Facility. The progress of each project, the associated tests and data evaluation, the applicabie design criteria, and the fabrication of reactor components are briefly summarized. (For preceding period see IDO-28538.) (W.D.M.)
Date: May 25, 1959
Partner: UNT Libraries Government Documents Department

LID TANK SHIELDING FACILITY MEASUREMENTS BEHIND THE ML-1 MOCKUP

Description: An experimental evaluation of the shield design for the ML-1 mobile reactor was made at the Lid Tank Shielding Facility. Thermal-neutron fluxes, fast-neutron dose rates, and gamma-ray dose rates were measured behind slab mockups of the basic shield design and a number of possible variations. The designs embodied various combinations of lead, Hevimet, stainless steel, boral, water, and aqueous solutions of ammonium pentaborate at two concentrations. The after-shutdown decay characteristics of the basic design were determined, and data were obtained from a fairly accurate mockup of the stainless steel plenum and gas duct typical of the top and bottom regions of the ML-1 shield. Analysis of results and application to the final shield design are not reported. (auth)
Date: September 20, 1961
Creator: MacKellar, A.D.; Jung, L.; Mathews, D.R.; Muckenthaler, F.J.; Miller, J.M. & Sowards, N.K.
Partner: UNT Libraries Government Documents Department

ML-1-1A CORE STUDIES WITH THE GCRE CRITICAL ASSEMBLY

Description: Critical assembly studies were conducted tc provide physics and engineering data to aid in developing the Mobile Low-Power Reactor (ML-1). The ML-1-lA core was critical with 59 elements containing 17,906.71 g of U/sup 235/ and had an excess reactivity of 0.381 x 10/sup -2/ DELTA k/k at a moderator temperature of 24.91 deg C. The ratio of maximum element power to core-averaged power was approximately 1.09. The ratio of maximum to core-averaged thermal flux was approximately 1.10. At an 18-deg separation, the shutdown worth of the cadmium-covered control-blade mock-up was 1.14 x 10/sup -2/ DELTA k/k for a 69 element core. Radial and upper axial reflector-moderator void coefficients were - 0.59 plus or minus 0.07 and -0.36S plus or minus 0.015 x 10/sup -2/ DELTA k/ k.per in., respectively. Two lA production fuel elements were evaluated in the critical assembly core. The results predict that the production elements tested contained roughly the same fuel as the critical assembly element and an additional 772 g of stainless steel equivalent on the average. Radial power and neutron flux distributions were measured in a 19-pin lB fuel element. Fairly uniform distributions were observed. Data to evaluate the thermal utilization of this element were obtained. (auth)
Date: November 27, 1959
Creator: Egen, R.A.; Hogan, W.S.; Dingee, D.A. & Chastain, J.W.
Partner: UNT Libraries Government Documents Department

HIGH-TEMPERATURE IRRADIATION OF UO$sub 2$-BeO BODIES

Description: As a part of the ML-1 reactor fuel evaluation program, UO/sub 2/-- BeO bodies containing two UO/sub 2/ compositions, 70 and 80 wt% UO/sub 2/, were irradiated to a burnup equivalent to 8750 hours of ML-1 reactor operation (8.5% U/ sup 235/). It was estimated that maximum cladding surface temperatures of 1710 nif- F were attained during irradiation. Reference design burnup for the ML-1 is 9.7% U/sup 235/, in 10,000 hours of operation at maximum clad surface temperatures of 1750 nif- F. Postirradiation examination of the test specimens revealed that the cladding of one of the 80 wt% UO/sub 2/-- BeO specimens had ruptured after severe swelling. All other specimens showed little external effect from the irradiation. Fission gas release from the fuel varied between 0.59 and 2.7% except for the failed specimen which released about 69%. Considerable change was observed in the microstructure of the irradiated specimens although subsequent x-ray diffraction examination did not indicate serious damage to the crystal structure of either the BeO or UO/sub 2/. The data obtained from this experiment are in substantial agreement with that determined in irradiation experiments performed at other facilities. The performance of 70 wt% UO/sub 2/--BeO was considered to be suitable for use in the ML-1 reactor. (auth)
Date: January 1, 1963
Creator: Titus, G.W. & Saling, J.H.
Partner: UNT Libraries Government Documents Department

Army Gas-Cooled Reactor Systems program: alternator final design report

Description: The development and testing of a demonstration brushless alternator for the ML-1 mobile nuclear power plant is described. The brushless concept was selected after it became apparent that a conventional power generator could not satisfy the ML-1 weight and size requirements. The demonstration alternator fabricated and tested under this program did not meet all performance specifications; the efficiency was low and the unit could not be operated for significant periods of time without overheating. However, a large body of useful data was accumulated during the extensive development program. Of special interest are data on the rotor and stator design, the cooling requirements and on the distribution of eddy current losses. Analysis of the data indicates that a brushless alternator, only slightly larger and heavier than was specified for the ML-1, could be developed with a modest additional effort.
Date: June 1, 1964
Partner: UNT Libraries Government Documents Department

PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING MARCH 1961

Description: Preparation of a gamma U/sub 3/O/sub 8/ single crystal for x ray examination is reported. Data from developmental work on binary Nb alloys are presented on stresses to produce deformation rates of 0.001, 0.01, and 0.1% per hr at 650, 800, and 1000 deg C. Developmental work on miniature heating elements for use in a power-balancing thermal-neutron flux sensor is reported for imbedded wire and film-conductance elements. In development of Th-- U alloys, chemical analysis data obtained from skull-cast samples are given. Results of a 1-month test on corrosion of Th-base compounds by NaK at 1200 deg F are tabulated. Data are given on mechanical and structural properties of Pu alloys being developed for high temperature propulsion uses. Continued studies of PuO/sub 2/ compatability with various stainless steels are reported. Efforts were devoted to characterizing sintered UO/sub 2/ bodies by quantitative metallography. Techniques were developed for fabrication of cermet fuels containing 80 vol.% UO/ sub 2/ and the remainder metals such as Cr, Mo, Nb or stainless steel. Fabrication studies on UN and UC fuels were conducted along with studies of gas pressure bonding methods. In development of UC, data on U--C systems at 1000 to 1500 deg C were obtained. Tests to determine the interdiffusion rates for C and U were completed. Irradiation of a capsule containing U--5 wt.% C was completed, and data are included. Experimental runs using the process-model system to study Mn removal from filtrates were completed. In graft polymerization studies, the effect of polymer structure on the efficiency of free-radical site formation was continued. In the joint U. S.-Euratom program, studies concenned obtaining information on void content and heat-transfer relations in forced-convection, two- phase flow, light-water systems. Development of UN as a fuel element is also in progress. Research is being conducted at HAPO on ...
Date: April 1, 1961
Creator: Dayton, R.W. & Tipton, C.R. Jr.
Partner: UNT Libraries Government Documents Department