Decontamination of a high-temperature pressurizedwater reactor core- coolant recirculation system following a fuel element cladding failure requires the dissolution of uranium oxides + uranium metal. An oxalic--peroxide-peracetic solution was developed which was found to be superior to other solutions for this task. The solution composition is: oxalic acid, 2.3 g/l: sodium oxalate, 32.0 g/ l; hydrogen peroxide, 15.0 g/l; 8-quinolinol, 1.0 g/l; and 40% peracetic acid, 12.5 g/l. 8-Quinolinol suppresses the decomposition of H/sub 2/O/sub 2/ in steel vessels. Corrosion data indicate that, of all the structural materials tested, only brass and brass alloys are corronded to any extent by this solution. This solution was used in the decontamination of the Plutonium Recycle Test Reactor. (D.L.C.)

This document details the activities of the Reactor Branch for the months of January through December of 1962. (FI)

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.)

The research program at Brooknaven is described. Current activities in physics, high-energy accelerators, instrumentation, chemistry, nuclear engineering, applied mathematics, biology, and medical research are outlined. (D.L.C.)

Separate abstracts were prepared on the 12 sections of this report. Abstracts covering 4 sections have previously appeared in NSA. A list is included of staff publications during the period covered by this report. (C.H.)

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.)

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.)

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.)

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.)

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 …

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.)

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.)

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.)

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 …

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 …

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 …

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)

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)

>The effects of an ultrasonic field on the maximum nucleate heat flux that can be sustained by boiling water in a flow system are being investigated. Design and procurement of apparatus is underway. (M.C.G.)

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)

Research and development progress is reported on TREAT, BORAX V, ZPR- III, EBR-II, and the reactor operations personnel training program. (M.C.G.)

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.)

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)

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.)