Search Results

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
Partner: UNT Libraries Government Documents Department
open access

BOILING NUCLEAR SUPERHEATER (BONUS) POWER STATION. Supplementary Study. Extrapolation to Large Central Station Integral Nuclear Superheat Plant

Description: An evaluation was made of the maximum size plant for which the BONUS reactor plant could serve as a realistic prototype and the design changes required to increase the size and characteristics for the present BONUS design such that it could serve as a realistic prototype for the largest feasible integral-superheat reactor power plant. (M.C.G.)
Date: October 31, 1962
Partner: UNT Libraries Government Documents Department
open access

CHEMICAL ENGINEERING DIVISION SUMMARY REPORT, JULY, AUGUST, SEPTEMBER, 1961

Description: Development activities are reported on pyrometallurgical processes including melt refining and those using liquid metal solvents. Development of processing facilities for EBR II is also reported. In other work, laboratory- and engineering-scale investigations on fluoride volatility processes were condueted, and conversion of UF/sub 6/ to UO/sub 2/ was studied. Investigations are also reported concerning the kinetics of metal ignition and oxidation, and metalwater reactions. In work associated with reactor chemistry, data on nuclear constants are reported and developments in thermoelectricity and reactor decontamination are described. (J.R.D.)
Date: October 31, 1962
Partner: UNT Libraries Government Documents Department
open access

Chemical Processing Technology Quarterly Progress Report, January-March 1961

Description: Studies are reported on aqueous zirconium processing, dissolution of BeO- UO/sub 2/ ceramic fuel, the aqueous stainless steel process, the behavior of dibutyl phosphates, use of boron (boric acid) solution to assure critical safety, fluidized bed calcination, conversion of amorphous alumina to alpha alumina, the Demonstrational Waste Calcining Facility, removal of long-lived radioisotopes from waste solutions, separation of iron, nickel, and chromiun from stainless steel waste solutions, electrolytic dissolution, effects of stray currents, electrolytic disintegration of Zircaloy-2, corrosion evaluation of materials of construction, the ARCO process, a direct air pulsed extraction column, and large vessel criticality control. (M.C.G.)
Date: October 31, 1962
Creator: Bower, J. R.
Partner: UNT Libraries Government Documents Department
open access

Design and Development of Fast-Response Thermopile-Type Neutron-Flux- Sensitive Device. Final Report, Phase 2

Description: A program was directed toward development of a thermopile-type neutron- flux-sensitive meter of small physical size and having a fast response time (25 msec) and a high signal output. The meter configuration selected consists essentially of a metallic heat sink, a thermopile, and a thin layer of neutron- sensitive material in series. When the meter is exposed to a neutron environment, heat generated in the neutron-sensitive material flows across the thermopile unit to the heat sink. The signal output generated by the thermopile is proportional to the heat flow, which is in turn proportional to the neutron flux. Signal-output characteristics of meters of this configuration have been verified by experimental testing in the Battelle Research Reactor, the General Electric NTR Reactor, and the Materials Testing Reactor (Idaho Falls). A practical neutron meter, in which the sensing element measures approximately 1/8 in. x 1/2 in. x 1 in., with a time constant of less than 25 msec and a millivolt- level signal output at a thermal-neutron flux of 10i/sup 12/n/cm/sup 2/-sec was achieved, thus substantially fulfilling the program objectives. (J.R.D.)
Date: October 31, 1962
Creator: Gee, L. J.
Partner: UNT Libraries Government Documents Department
open access

DESIGN AND OPERATION OF 1800 F PUMPED BOILING RUBIDIUM LOOP SYSTEM AND DETERMINATION OF DENSITY AND VAPOR PRESSURE RUBIDIUM BETWEEN 174 AND 1800 F. Space Power Systems Technology Studies: Rubidium, Corrosion and Physical Properties Evaluation Program. Final Report (Report No. 16), February 1, 1960 through May 31, 1961

Description: A pumped boiling rubidium loop was designed, operated, and analyzed. The loop simulated some of the characteristics of a boiling rubidium space power conversion system. Such a system would involve either a reactor or heat exchanger as the power source, and a turbine and radiator as the power conversion and vapor condensing equipment. This loop was used to study instrumentation and control problems and effects of rubidium corrosion on containment materials, and to gain some rough physical property and heat transfer data on rubidium. The first loop operated with 316 stainless steels and was run for l72 hours at various temperatures, the maximum being 1550 deg F boiling. The 316 stainless steel loop was operated only a short period since it was intended as a system shakedown measure. The second loop was Nb-l Zr loop alloy operated for 455 hours total at l840 deg F and a vapor quality of 9%. ln the latter loop, the last 335 hours of operation were continuous. Stable boiling at this vapor quality level was achieved withont the use of special liquid vapor phase separaration devices. Operation of the loop was stable in all phases; however, overheating of the environmental chamber was observed due to insufficient insulation on the loop end resultant high heat losses from the loop heater and boiler. The niobium loop run was terminated by a cracked weld at the entrance to the condenser section in the hot portion of the loop/su Negligible corrosion by the rubidium on both loops was observed. Some carbide penetration on the outside of the niobium loop was observed which apparently was caused by carbonaceous impurities in the argon gas. The failure of the weld at the entrance to the condenser was believed to be caused by carbide penetration effects. The protective coating of zirconium foil …
Date: October 31, 1962
Partner: UNT Libraries Government Documents Department
open access

DEVELOPMENT OF CLAD CERAMIC FUEL PLATES BY SPRAY-COATING TECHNIQUES. Quarterly Technical Progress Report, April-June 1961

Description: Studies were made on the effects of spray-coating variables on coating characteristics in the development of plasma-jet spraying techniques for making clad UO/sub 2/ fuel plates. UO/sub 2/ coatings of up to 90% theoretical density and - O/U ratios of nearly 2.00 were deposited at efficiencies of 40%. Adherent UO/sub 2/ coatings up to 0.100 inch thick can be deposited on 0.030-inch thick stainless steel and Zircaloy-2 substrates. Studies of coated composite bends and coating adherence at room temperature indicate that, for best results, the coating temperature should be maintained below 870 deg C and the substrate below 450 deg C during deposition. A plasma spray torch was tested for spraying UO/sub 2/ at 40 kw and found to be equivalent to operation at 25 kw. A preliminary cost analysis indicated considerably lower fabrication costs using plasma jet sprayingn ~ 0/kg U as compared to ~ 0/kg U for oxide pellet-in-tube elements. (D.L.C.)
Date: October 31, 1962
Creator: Weare, N.E.; Buchanan, E. & Marchandise, H.
Partner: UNT Libraries Government Documents Department
open access

DEVELOPMENT OF CLAD CERAMIC FUEL PLATES BY SPRAY-COATING TECHNIQUES. Quarterly Tecnnical Progress Report, October-December 1960

Description: Activities in a ptogram concerned with development of plasma-jet spray- coating techniques suitable for production of clad ceramic fuel plates are described. Experiments on application of zirconia coatings are also described. A survey of UO/sub 2/ powder was conducted to determine its suitability for plasma spraying. Also conditions were established for spraying fused and milled UO/sub 2/. The effects of process variables on coating and deposition characteristics were found to correlate. Densities of UO/sub 2/ coatings of 75 to 80% were achieved. (J.R.D.)
Date: October 31, 1962
Creator: Weare, N.E.
Partner: UNT Libraries Government Documents Department
open access

DEVELOPMENT OF PLUTONIUM-BEARING FUEL MATERIALS. Progress Report, April 1 through June 30, 1962

Description: Progress in the development and testing of plutonium fuels is described. Topics covered include: project and facility administration, preparation and characterization of fuel materials, fabrication and evaluation of fuel shapes, fuel element fabrication and evaluation, radiation testing aad evaluation, and reactor physics and engineering parametric studies. (M.C.G.)
Date: October 31, 1962
Partner: UNT Libraries Government Documents Department
open access

DEVELOPMENT OF PLUTONIUM-BEARING FUEL MATERIALS. Progress Report for Period January 1 through March 31, 1962

Description: During this reporting period, particular effort was of aced on powder blending and pellet sintering studies prior to irradiation sample fabrication, and, subsequently, the production and characterization of the pellets slated for irradiation. Also, PuO/sub 2/ and UO/sub 2/-PuO/sub 2/ characterization studies were continued, and new techniques are being developed. Specifically, dynamic moisture pickup determinations on PuO/sub 2/ were made in moist air, N, and CO/ sub 2/ atmospheres using a recording thermogravimetric balance; the Sharples Micromerograph was committed to Pu, and powder particle size distributions were measured and compared with previous determinations made with air-permeability equipment; and the suitability and reliability of analytical chemistry assaying procedures such as x-ray-fluorescence and gamma spectrometry are being evaluated. Prototype work on UO/sub 2/ for the direct precipitation of PuO/sub 2/ and PuO/ sub 2/-UO/sub 2/ feed materials for swaging, vibratory compaction, and dispersion fabrication was also continued. In addition, investigation of PuO/sub 2/ spherical particle formation by mechanical buildup and by plasma torch fusion was extended. Associated reactor physics studies were concentrated on the further comparison of Pu and U/sup 235/ in near-thermal converter reactors. In preparation for the fabrication of irradiation test specimens to be prepared by the mechanical blending of individuaI PuO/sub 2/ and UO/sub 2/ powders, bIending studies were initiated to develop methods required for the attainment of desired homogeneity. Sintering studies were carried out on PuOs/sub 2/ to study the effects of compaction pressure, firing temperature, firing time, and firing atmosphere. It was determined that 1400 to 1500 deg C is the best firing temperature to obtain maximum pellet density, and that sintering in air yields higher densities than sintering in a N/sub 2/--H/sub 2/ atmosphere. Further, it was noted that the degree of Pu/sub 2/O/sub 3/ formation while sintering in an N/ sub 2/--H/sub 2/ atm osphere …
Date: October 31, 1962
Partner: UNT Libraries Government Documents Department
open access

DEVELOPMENT OF PLUTONIUM BEARING FUEL MATERIALS. Progress Report for period July 1 through September 30, 1961

Description: Data are tabulated for the characteristic parameters of PuO/sub 2/ powders prepared by the continuous oxalate precipitation process. The results show that the PuO/sub 2/ surface area decreases almost linearly with calcination hold times at 760 deg C. A thermogravimetric study of the decomposition of Pu oxalate indicate the formation of an initial stable compound at ~ l00 deg C and a stable intermediate at ~ 300 deg C. Characteristic data are tabulated for UO/sub 2/ -5% PuO/sub 2/ and UO/sub 2/-20% PuO/sub 2/ powders prepared by coprecipitation. Preliminary blending studies giving a final UO/sub 2/ -0.5% PuO/ sub 2/ powder show that a more homogeneous product is obtained if two powders of the same surface area are used. Results are given for preliminary studies of the direct preparation of high-density coarse particles. A study was made of the simultaneous determination of Pu and U by differential spectrophotometry. Sintering studies were made on PuO/sub 2/ and on both mechanically mixed and coprecipitated PuO/sub 2/UO/sub 2/; the results indicate that the blending and mixing procedures are unsatisfactory. The eutectoid-like microstructure observed in sintered PuO/sub 2/ pellets appear to be Pu/sub 2/O/sub 3/. Preliminary preparations of sintered PuO/sub 2/ spheres coated with Ni are rcpcrted. (D.L.C.)
Date: October 31, 1962
Partner: UNT Libraries Government Documents Department
open access

DEVELOPMENT OF PLUTONIUM-BEARING FUEL MATERIALS. Progress Report, October 1-December 31, 1961

Description: Continued effort is reported on preparation and characterization of PuO/ sub 2/ and UO/sub 2/-- PuO/sub 2/ mixtures. Sintering and characterization of pellets for irradiation tests was emphasized, and efforts were also devoted to plasma torch production of spherical PuO /sub 2/ and coating of oxide materials. PuO/sub 2/ produced by the oxalate process from low concentration feed contains agglomerates which are not readily broken down, while that produced from normal feed contains larger agglomerates which are easily dispersed ultrasonically, and are more easily calcined. The water filtration method for determining total porosity of powders was adapted for use with PuO/sub 2/. Moisture pickup studies show that the problems encountered with PuO/sub 2/ are similar to those found in handling ceramic-grade UO/. Reproducibility tests carried out on UO/sub 2/--PuO/ sub 2/ mixtures indicate that production methods are satisfactory. Lab-scale experiments on production of PuO/sub 2/-- UO/sub 2/feed for the plasma torch indicate that further work is worthwhile. Adaptation of a potentiometric filtration for Pu is reported. A twophase microstructure found in PuO/ after sintering in N6% H atmosphere was identified as PuO/sub 2/ and cubic Pu/sub 2/O/ sub 3/. Spherical particles were produced in the plasma torch using crushed or preformed high-fired particles. Spherical particles of PuO/sub 2/ were also produced by a multi-step process of drying, pressing, granulation, sizing, shaping, and sintering. Reactor physics studies were continued to determine the effect of cross section assumptions on the calculated behavior of Pu-fueled near- thermal reactor systems. It was concluded that relatively long core life (reactivity limiting) is attainable with these systems. (J.R.D.)
Date: October 31, 1962
Partner: UNT Libraries Government Documents Department
open access

ENERGY STORAGE MECHANISMS IN LIQUID HYDROGEN

Description: Section II, Task 1, Item 5 of FZM-2386. Energy-storing molecular products of radiation in liquid H/sub 2/ are examined from the point of view that the expulsion of potertial energy in the form of such products may lead to lower design weights for nuclear rockets. It is found that a significant fraction of the energy deposited by radiation in liquid H/sub 2/ is stored temporarily through the dissociation and excitation of H/sub 2/ molecules. Experimental and theoretical results are consistent with a rate of dissipation of such energy into thermal motion which is much slower than the rate at which the radiation products are expelled from the tank. It is shown that, if this is the case, relatively high levels of infrared radiation are to be expected but that such energy will not rapidly be translated into thermal motion. It is concluded that, insofar as radiation heating of the propellant is a significant design factor, further consideration should be given to radiation-induced reactions in liquid H/sub 2/ and that any radiation-heating experiments should be interpreted in terms of possible energy-storage effects. (auth)
Date: October 31, 1962
Creator: Carter, H.G.
Partner: UNT Libraries Government Documents Department
open access

EXPERIMENTAL INVESTIGATION OF THE EFFECTS OF ULTRASONIC VIBRATIONS ON BURNOUT HEAT FLUX WITH BOILING WATER. Quarterly Technical Progress Report No. 3, April-June 1961

Description: The heat-transfer loop was completed and is in operation. Difficulty was experienced in obtaining a sufficiently strong connection between the burnout- detector voltage tap and the heating element. This problem and its potential solution are described. The lack of means of obtaining controlled burnout prevented collection of data on the burnout effects of the ultrasonic field. (auth)
Date: October 31, 1962
Creator: Romie, F.E.
Partner: UNT Libraries Government Documents Department
open access

GAUGE FOR MEASURING BOW OF TUBES

Description: A mechanical gage was designed to measure the bow over any one-foot length of long cylindrical material. The gage was used successfully for measuring bow in components of tubular fuel elements at the Savannah River Laboratory. (auth)
Date: October 31, 1962
Creator: Alewine, G.B.
Partner: UNT Libraries Government Documents Department
open access

IDAHO DIVISION SUMMARY REPORT, APRIL THROUGH SEPTEMBER 1961

Description: Research and development progress is reported on TREAT, BORAX V, ZPR- III, EBR-II, and the reactor operations personnel training program. (M.C.G.)
Date: October 31, 1962
Partner: UNT Libraries Government Documents Department
open access

IDO REPORT ON THE NUCLEAR INCIDENT AT THE SL-1 REACTOR, JANUARY 3, 1961 AT THE NATIONAL REACTOR TESTING STATION

Description: A summary of activities which took place following an incident at the SL- 1 is presented. No attempt to determine the incident cause is included. A brief description of the SL-1 and the operating program in progress prior to the incident is given along with detailed information on various aspects of the past incident developments. (J.R.D.)
Date: October 31, 1962
Partner: UNT Libraries Government Documents Department
open access

IMPROVED DESIGN FOR FUEL HANDLING ON SODIUM GRAPHITE POWER REACTORS

Description: Operational experience at the SRE and evaluation of alternate methods resulted in the development of an optimized fuel-handling system for the Hallam Nuclear Power Facility Beactor. Increased reliability, easier maintenance, improved safeguards, and broader flexibility are some of the characteristics of this system, which features a manually-operated, shielded cask with reactor atmosphere seals that is usable in a conventional unshielded air-atmosphere building. (auth)
Date: October 31, 1962
Creator: Edziak, T.F.; Crosgrove, R.O. & Stolz, J.F.
Partner: UNT Libraries Government Documents Department
open access

INVESTIGATION OF THE TECHNICAL FEASIBILITY OF COLD EXTRUSION FOR ZIRCALOY-2 TUBING PRODUCTION. Quarterly Technical Progress Report, July-September, 1961

Description: Bar-extrusion tests were performed at 50. 65, and 80% reductions at room temperature and 300 deg C. Tensile tests were conducted on as-extruded and heat-treated specimens. The results are tabulated for comparison. The extrusion of small tubing, 0.560-in. OD x 0.030-in. wall, in the first and second tube- extrusion steps are described. (B.O.G.)
Date: October 31, 1962
Creator: Weil, F.E. & Hill, J.G.
Partner: UNT Libraries Government Documents Department
open access

INVESTIGATION OF THE TECHNICAL FEASIBILITY OF COLD EXTRUSION FOR ZIRCALOY-2 TUBING PRODUCTION. Quarterly Technical Progress Report No. 3, April-June 1961

Description: Investigations are being made to establish the feasibility of using cold extrusion to produce Zircaloy-2 tubular products. Tests on extruding 1 1/4-in. diameter billets were completed. Samples in 46 bar-extrusion tests were extruded with 80% reduction at 400 deg C. Severe lubricant breakdown occurred. Piercing tests were conducted at, room temperature and 200 deg C, using 50% reduction and a 140-degree conical punch profile. Good extrusions were obtained in forraing 1.07-in. OD x 0.052-in. wall tubes with 65% reduction. Low efficiencies in tube- extrusion tests compared with those for bar extrusion were due to the large surface-to-volume ratio of tubular specimens. Tooling was designed and fabricated to produce, in three steps, 12-in. lengths of 0.560-in. OD x 0.030- in. wall tubing from
Date: October 31, 1962
Creator: Weil, F.E. & Hill, J.G.
Partner: UNT Libraries Government Documents Department
open access

INVESTIGATION OF THE TECHNICAL FEASIBILITY OF COLD EXTRUSION FOR ZIRCALOY-2 TUBING PRODUCTION. Quarterly Technical Progress Report, October-December 1960

Description: S>Activities included completion of room-temperature extrusion tests on Zircaloy bar, and extrusions with 50% reduction at temperatures up to 400 deg C. Results of these tests are tabulated along with results of billet piercing tests at 300 deg C. It is noted that production of capped Zircaloy tubes by cold extrusion appears promising. (J.R.D.)
Date: October 31, 1962
Partner: UNT Libraries Government Documents Department
Back to Top of Screen