This report covers the S-I-5-B-M* fuel irradiation in the GETR Maritime Loop during the fourth quarter of fiscal year 1961. The data are summarized in Section II.

This study was designed to determine how swaging stainless steel over unground pellets will affect the integrity of fuel rods, and to find maximum pellet diameter variation that can be tolerated.

Recently a T=1 resonance in the [Alpha w] system called [Y*1] has been observed with a mass of 1385 Mev. Two types of resonances have been predicted that might relate this observation to other elementary-particle interactions: (1) P 3/2 resonances in the Alpha w and Sigma w systems predicted by global symmetry corresponding to the (3/2, 3/2) resonance of the wN system, (2) a spin-1/2 Y-w resonance resulting from a bound state in the KN system. The position and width of the observed [Y*1] resonance agree with both theories but since the spin and parity have not yet been determined, it is impossible at present to distinguish between the two theoretical interpretations.

The objective of the test discussed in this report is to verify further the corrosion rate of irradiated tubular fuel elements under conditions of high specific power and central core temperatures. The fuel will be the inner component of an NPR fuel element assembly. A proposal to charge two tubular fuel elements into the GEH-P7 Loop has been made. The upper fuel element of the two has been irradiated to 1660 MWD/T in a Hanford reactor. A hydraulic cylinder will be attached to the upper fuel element. The hydraulic cylinder will be used to move a chisel along the outer surface of the upper fuel element and shear off a cap which has been welded over a hole through the cladding. The lower fuel element of the two will be used to add heat to the loop so that the desired loop water temperatures can be maintained.

This report provides some temperature and swelling data on Zircaloy-2 clad, coextruded fuel elements irradiated in the KER loops and in the GEH-3 {times} 3P7 loop at the ETR. Data on both rod cluster fuel elements and tubular fuel elements are included. Density changes, where density measurements were made, have also been included. These data are preliminary and are subject to change.

Irradiation of a third thermocouple train with a thermocouple element of the same design as used on the previous two trains, but with different train design and heater elements, is authorized to an exposure no greater than 1000 MWD/T. A third decontamination of KER-1 is also authorized.

Tables are given for revised constants in the optimization model for charge-discharge rates, tube replacement rate, non-power-exposure- associated loss (EMISC), hours lost per rupture, and ruptured slug removal time in the reactors B, C, D, DR, F, H, KE, and KW.

Laboratory results are presented for a flowsheet study of a process for decontaminating ORNL low level waste water. The water is adjusted to approximately pH 12 with NaOH, clarified, and passed through a bed of phenolic cation exchange resin. This study, using a phenolic-carboxylic resin, showed essentially the same results as those previously reported using a phenolic-sulfonic resin, i.e., radioactivities in ORNL waste were reduced to the order of 10% of MPC. The phenolic-carboxylic resin has the advantage that it can be regenerated with 0.5 M HNO/sub 3/ instead of the 5 M HCl required for the phenolic-sulfonic resin. Volume reduction factors of 2000 to 3000 were achieved.

The large aqueous pilot plant facilities at ORNL were cleaned and are being put in standby condition. Experience was gained during the year as anion exchange was used to recover more than one kg of plutonium left in the exploded evaporator system. This experience is being applied to a new recovery program just beginning in cell 1 of Building 4507. (auth)

Hydraulic tests were made on the Hallam Prototype Free-Surface Sodium Pump to determine the net positive suction head (NPSH) required at various sodium flow rates. Pump performance data were also collected. The results indicate that an NPSH of 22 ft sodium is required at the design flow rate of 7200 gpm at approximates 1000 deg F, agreeing with computed values, and that the pump is designed with a safety margin of slightly over l0%. (D.L.C.)

A spectrographic method using d-c arc excitation in a controlled atmosphere was developed to analyze for seven impurity elements in radioactive hafnium samples. Analysis requires as little as 35 mg of hafnium oxide. (auth)

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Calculations are presented which show that the reactivity effect of flooding and unflooding the fast superheating section of the Mixed Spectrum Superheater can be made small by the addition of epithermal poisons to the superheater. The reactivity effects of flooding superheater sections ranging in size from 1.25 to 3.5 ft cubes and containing U/sup 23/5/sup >/oxide or Pu/sup 239/ oxide fuel and various amounts o f the epithermal poison europium were calculated. Reactivity changes during several postulated flooding processes are given. Methods for deterthination of fissile and fertile material and poison cross sections in the resonance- region are discussed. (auth)

A simple mathematical model was developed to describe the steady-state release rate of gaseous fission products from porous ceramic fuels in low- permeability containers. The resulting equations are used to analyze experimental release rate results obtained from a UC/sub 2/-fueled graphite fuel body enclosed in a low-permeability impregnated graphite container. The relative release rates of the fission-product species Kr/sup 85m/, Kr/sup 88/, and Xe/sup 133/ were predicted with reasonable success. Absolute-rate predictions were not possible due to lack of information on true permeability and porosity profiles in the graphite container. (auth)

The results of a limited analysis of the extended SM-2 critical experiments are given. A review of the analytical models is presented to ascertain the accuracy of the reactivity calculations for the reference SMi-2 Core I. A new reference B-l0 loading was derived based on analysis and experimental measurements. Calculations of power distributions and burnup behavior of the reference core are presented and comparisons to available measured data made. (auth)

Measurements were made to determine the extent of activity build-up inside the 1 AC and 1 BD punification demineralizer concrete enclosures. Radiation levels were obtained at 6-in. intervals from 6 to 17.5 ft below the top of the concrete shield on the 1 AC demineralizer and from 0.5 tc 24.5 ft on the 1 BD dendneralizer by lowering the probe through the 3-in. pipe on top of the concrete enclosure. The results indicated that the long-lived activity in the purification demineralizers had decreased considerably, since the previous test, with the addition of new resin. (M.C.G.)

Laboratory results are presented for a flowsheet study of a process for decontaminating ORNL low level waste water. The water is adjusted to approximately pH 12 with NaOH, clarified, and passed through a bed of phenolic cation exchange resin. This study, using a phenoliccarboxylic resin, showed essentially the same results as those previously reported using a phenolic- sulfonic resin, i.e., radioactivities in ORNL waste were reduced to the order of 10% of MPC. The phenolic-carboxylic resin has the advantage that it can be regenerated with 0.5 M HNO/sub 3/ instead of the 5 M HCl required for the phenolic-sulfonic resin. Volume reduction factors of 2000 to 3000 were achieved. (auth)

A full scale 15 deg sector of the P122 reactor configuration was constructed. The model was complete with respect to all internal cooling air passages, and reflectors, thermal shielding, and island reflector. The contract was terminated before any test data could be obtained. Investigation of the effect of atmospheric dust on performance of reactor systems using wire screen matrix fuel elements is reported. The interim conclusion is that dust would not limit aircraft performance or life. Work proposed but not completed is outlined. Appendices contain previously unpublished reports. (auth)

The Zirflex process was studied extensively at Hanford in the development of technology for the interim reprocessing of power reactor fuels. The process involves the dissolution of Zircaloy in aqueous ammonium fluoride - ammonium nitrate solution. It is of particular interest at Hanford because of the impending fuel recovery from Zircaloy-clad PRTR and NPR elements. The chemical kinetics of the Zirflex reaction were not fuily defined at the end of the original studies. However, a pseudo first order reaction with free'' fluoride (fluoride not complexed with Zr) was deemed to describe the kinetics adequately for engineering calculations. The refined kinetic equation and the analog computer solution on model of the system are discussed. The results of thirty computer simulated dis solutions are also presented, and the data are used to illustrate the effects of the process variables on the Zirflex dissolution time cycle. The data from a selected few of the runs are directly applicable to the reprocessing of PRTR fuel elements in Redox. It was found that the Zirflex reaction kinetics are dependent on free'' fluoride ion to the 2.0l7 power and on H ion to the 0.457 power according to laboratory data secured after completion of the original …

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Recently a T = 1 resonance in the {Lambda}{pi} system called Y*{sub 1} has been observed with a mass of 1385 Mev. Two types of resonances have been predicted that might relate this observation to other elementary-particle interactions: (1) P 3/2 resonances in the {Lambda}{pi} and {Sigma}{pi} systems predicted by global symmetry corresponding to the (3/2, 3/2) resonance of the {pi}N system; (2) a spin-1/2 Y-{pi} resonance resulting from a bound state in the KN system. The position and width of the observed Y*{sub 1} resonance agree with both theories, but since the spin and parity have not yet been determined, it is impossible at present to distinguish between the two theoretical interpretations.

Concrete mix design criteria, based on existing theories of proportioning and specifically oriented toward the solution of radiation shielding problems, were developed. Effects of aggregate gradation, cement-to- aggregate ratio, and water content were examined. A barytes concrete, designed according to these criteria, was thoroughly investigated in the Lid Tank Shielding Facility. Relative effectivenesses of dry aggregates, aggregates plus cement, and cured concrete were compared through thermal-neutron flux, fast- neutron dose, and gamma-ray dose measurements behind slab configurations. Attenuation was measured for the aggregate, the aggregate plus cement, and for the barytes concrete. Comparison with attenuations calculated on the basis of removal cross sections for the measured chemical compositions showed satisfactory agreement. (auth)

Incremental couples at 10% intervals across the U-Nb binary system were prepared and diffused. Irradiation damage of nickel single crystals bombarded with 3-Mev electrons from a Van de Graaff generator were studied by Kossel line techniques. It was concluded that most defects anneal out below room temperature and all anneal out below 400 deg C. The cold-rolled texture of tantaium is described by (200) and (110) pole figures. This texture may be approximated by the ideal orientations, {112} <011>, {100{ <011>, and {111} <112>. The directionality of Young's modulus, yield strength, and tensile strengih of tantalum is also presented. The effects of thermal gradients on the transformation kinetics and diffusion in U--10 wt.% Mo were investigated. The alloy U(Fe,Mn) was found to be paramagnetic from 480 to 10 deg K. The remanent magnetization of hematite along particular directions in the (111) plane and along the STA111! direction of a rectangular prism was measured during a complete cycle of temperature chsnge between 488 and 77 deg K. The remanent-temperature relationship snd the thermal hysteresis effect were also measured. The concept of space filling was developed for presenting geometrical relationships of different crystal structures. The structure of the pseudo-binary system ReTi/sub 2/--TiSi/sub …