The EGCR was designed to accommodate up to four gascooled experimental loops plus several experimental fuel elements in the open core. Two of the loops will utilize 51/2-in.-O.D. stainless steel tubes passing through the core along an axis which is about 17 in. from the central axis of the core. The other two loops will utilize 91/2-in.-o.d. tubes about 68 in. from the central axis. Inherent safety in the design, facility design, primary loop design, auxiliary systems and equipment design, primary and secondary containment design, instrumentation and controls, and special operations are discussed. (M.C.G.)

Thermal stress tests on Type 1, SM-1A Core II fuel ele-ment sections were performed to study plate distortion and determine its dependency on temperature distribution, temperature differential, initial flatness, and ripple length. Test results will be correlated with the analytical model and used to predict ripple growth in other plate-type fuel elements. The tests showed that ripple growth is dependent on initial flatness of the plate and that the characteristic shape of ripples is maintained at all temperature differentials: The tests also showed that the ripple growth rate for a ripple of 5 mil initial magnitude is approximately 0.12 mils/ deg F for a peak temperature differential of 103 deg F and that the apparent relationship between ripple net growth and length is 1.3 mil/in. of ripple for a peak temperature differential of 103 deg F. A permanent distortion of 2 mils for a complete temperature cycle from 0 to 103 to O deg F differential was found. The temperature profile across the plate width was found to affect the magnitude of ripple growth. (auth)

The postulate that the average number of lattice displacements is directly proportional to the available energy is carried one step further; it is assumed that damage to steel (particularly in regard to brittle fracture) is proportional to the number of lattice vacancies that occur. The model, although crude, permits estimation of the relative damage resulting from differences in neutron spectra. The results can be used as a rough method of correcting damage data for the effect of the neutron-energy spectrum. Radiation damage calculations for steel, relative to those for a fission spectrum, were made for neutron spectra that result from fission neutrons penetrating water or graphite. The results were plotted as a function of effective distance from the fission source. From this plot it is possible to make a conservative estimate of the correction factor to apply to damage data obtained with different neutron spectra. (auth)

In a prevlous paper, some inequalities occurring in the one-veloclty theory of neutron transport with lsotropic scattering were derived. Some of the previous results are generalized to the case of linearly anisotropic scattering. (auth)

Effective energy cutoffs have been calculated on an IBM7090 computer for Cd, Gd, Sm, and B filters as functions of filter geometry, the ratio of Maxwellian to epithermal flux (assumed to be 1/E), the lower energy limit of the 1/E flux, the energy corresponding to the Maxwellian most probable (modal) velocity and filter thickness. The geometrical configurations were spherical (which on the assumptions madc is equivalent to a beam flux case), cylindrical and slab. By the use of two or three different filters (Cd and Gd and perhaps Sm) it should be possible to detect resonances in the thermal to cutoff energy regions, in addition to measuring resonance integrals and thermial cross sections of unknown nuclides. (auth)

Process and product requirements to be met in the fabrication of Type 3 fuel elements are presented. The fuel elements specified consist of thin plates of a dispersion of highly enriched UO/sub 2/ and ZrB/sub 2/ in a stainless steel matrix which is clad with stainless steel on all surfaces. Quality assurance provisions are discussed. Process and material specifications and packaging and packing for shipment are described. Sample calculations and drawings are included. (M.C.G.)

The temperature coefficient of the Reactivity Measurement Facility was found to be 49 plus or minus 1 mu k/ deg C (1 mu k = 10/sup -6/ DELTA k/k) in the range 15.4 to l7.8 deg C. The change in the net reactivity of a standard sample was --0.48 plus or minus 0.02, --0.66 plus or minus 0.03, and --0.78 plus or minus 0.02 mu k/ deg C in three measuring positions. These low values generally make temperature corrections insignificant. The above results are compared with previous determined values. This information developed in the RMF should be generally applicable to flux-trap-type reactors such as the Advanced Reactivity Measurement Facility (ARMF) and ARMF-ll, now under construction. RMF was dismantled in April 1962. (auth)

Submitted to Univ. of Tennessee, Knoxville. The fast neutron-induced fission cross section of U/sup 234/ was measured from threshold to 4-Mev neutron energy. A maximum of 1.26 barns was found at 850 kev followed by a minimum of 1.10 barns at 8050 kev. The angular ani-sotropy of the fragment distribution was measured for neutron energies from 400 kev to 4 Mev. Extrema in the ratio sigma /sub f//( sigma /sub f(90 deg ) were found at 500, 850, and 1050 kev; the distribution at 500 kev showing a maximum in the direction normal to the beam (side-wise peaking) while that at 850 kev showed a maximum along the beam direction. The distribution at 8050 kev showed forward peaking but to a lesser extent than for energies immediately higher or lower. The behavior was analyzed according to the theories of Bohr and Wheeler. The dip in cross section between 850 and 1050 kev is consistent with the suggestion of Wheeler that neutron competition in the decay of the compound nucleus enters with increased strength in this area. Vibration-rotational levels in U/sup 234/ beginning at 790 kev are known to exist and inelastic neutron scattering to these levels serves to depress the …

The failure of a fuel element cladding in one of the water-cooled plutonium production reactors permits the erosion of irradiated uranium metal by the cooling water which is normally disposed to the Columbia River. Monitoring systems at both the reactors and at their effluent basin outlets to the river continuously monitor these streams, and if major fission-products release occurs the coolant can be held in retention basins. In addition to these monitoring systems, a river monitor is located at the 300 area which continuously monitors the gross gamma activity of the Columbia River; however, its sensitivity to rupture debris is limited because of the relatively high background'' from the short-lived (n, {gamma}) produced radionuclides in the river. In making hazard assessments and in providing adequate monitoring techniques and equipment at down-river locations, it is essential to know what changes occur in fission and (n, {gamma}) produced radionuclides following release of rupture products to the river.

Report discussing a studies regarding "imaging qualities and the thermal neutron and gamma-ray sensitivities of several neutron imaging detectors".

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Authority of the Insurance Department to issue original or renewal local agents' licenses to firms or partnerships composed partly of individuals who do not qualify by examination as local recording agents and who are not actively engaged in writing insurance.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Construction of Item 5 of the appropriation to the Game and Fish Commission.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Whether the Texas Water Commission is required to pay the costs of publication of notice of hearing.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Does a Commissioners Court have the authority to establish a public road under Article 6711, V.C.S., if the applicant for said road resides on the land into which there is now no public road or public access?

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Whether line item 20, to the Building Commission, in the General Appropriation bill is available to be used in refinishing certain furniture for the Third Court of Civil Appeals.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Whether certain lots and the permanent improvements and personal properties thereon are exempt from ad valorem taxes as a public library.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: The beginning date of prisoner's sentence where prisoner was denied the right of bail under Article 815 of the Code of Criminal Procedure and remained in jail while his conviction was being affirmed.

The status of aqueous processing methods for Th fuels is reviewed. A specially designed 320 ton shear was successfully tested for chopping full size simulated Consolidated Edison type unirradiated assemblies into 0.25-1.5 in. lengths. Pieces about 0.5-in. long are preferred since the core pellets are more severely crushed during the chopping operation, and consequently, the rate of core dissolution is enhanced. The Darex (dtlute aqua regia) and Sulfex (4 to 6 M sulfuric acid) processes for dissolution of stainless steel claddings were developed on a small engineering scale with unirradiated fuel. In hot cell tests on stainless steel clad ThO/sub 2/-UO/sub 2/ fuel pins irradiated up to 22,000 Mwd/ton of fuel, the core pellets were severely fractured and losses of U and Th to the Sulfex and Darex solutions were approximates 0.3% and 3 to 5%, respectively. The latter losses are easily recovered in the extraction system. U and Th can be recovered from graphite base fuels by burning and dissoiution of the ash in HNO/sub 3/ or by grinding to approximates 200 mesh followed by HNO/sub 3/ leaching. The Acid Thorex extraction process was developed to recover both U and Th using tributyl phosphate (TBP) as the solvent and …

In May, 1961, it waa determined no renewed nuclear reaction in the SL-1 pressure vessel was possible as long as water was excluded. It was therefore possible to proceed with the final phase of the SL-1 recovery. This work consisted of moving the pressure vessel and core to the Hot Shop at the north end of the National Reactor Testing Station, dissecting and analyzing the reactor and its components, cutting up and burying the reactor building, and decontaminating the rest of the SL-1 area. These things were accomplished by the General Electric Company between May 1961 and July 1962. It was determined that the central control rod was bound in its shroud at a position corresponding to 20- inch withdrawal. Analysis of the pertinent data showed that the amount of reactivity associated with this rod position, inserted at a rate compatihie with manual withdrawal of the rod, can explain the significant evidence which was coliected. No other means of withdrawing the rod was found to be in accordance with the evidence. It was found that the relatively low yield (130 Mw-sec) nuclear excursion produced a water hammer with pressures up to 10,000 psi, which, in turn, caused the pressure vessel …

Effects due to elementary particle-like collisions within nuclear matter have been observed in several nuclear reactions caused by pions and protons. Simple nuclear reactions of the form ZA(a,an)Z/sup A-1/ and Z/sup A/(a,ap)(Z-1)/ sup A-1/ have excitation functions that are sensitive to changes in the elementary-particle cross sections. The excitation function for the reaction C/ sup 12/( pi /sup -/, pi /sup -/n)C/sup 11/ is measure d from 53 to 1610 Mev by bombarding targets of plastic scintillator with pions. The intensity of the pion beam is monitored with a two-counter telescope and 40 Mc scaling system. The scintillator target is mounted on a phototube and becomes the detector for the carbon-11 positron activity. Corrections are made for muon contamination in the beam, coincidence losses in the monitor system, carbon-11 activity produced by stray background at the accelerator, carbon-1l activity produced by secondaries in the target, and the efficiency of the carbon-11 detection system. The C/sup 12/( pi /sup -/, pi /sup -/n)C/sup 11/ cross sections rise to a peak of abo ut 70 mb at 190 Mev, that corresponds to the resonance in freeparticle pi /sup -/n scattering at 190 Mev. Calculations based on a knock-on'' collision mechanism and sharp-cutoff …

The phase diagram of the Th-- Mo alloy system has been determined to be of the eutectic type with a eutectoid reaction associated with the Th alpha-beta transformation. X-ray, thermal, electric resistance, and metallographic methods have established the eutectic point at 1380 plus or minus 10 deg C and 7.0 plus or minus 0.5 wt% Mo. A eutectoid reaction is proposed at 1358 plus or minus 5 deg C and less than 0.1 wt% Mo. No solubility of Th in Mo was detected at 1325 deg C. (auth)

The mechanisms by which the carbon dioxide coolant affects the strength properties of type 304 stainless steel were investigated in the range 1300 to 1700 deg F (704-927 deg C). Creep- and stress-rupture results obtained on sheet materials in wet and dry CO/sub 2/ and argon are compared. The effect of annealing in CO/sub 2/ on the tensile strength and ductility was also investigated. The question of whether the strengthening observed in CO/sub 2/ was due to oxidation or carburization was determined. Experiments on the effect of various partial pressures of oxygen in argon showed that the creep rate was minimum at approximately 10 ppm. The creep rate is CO/sub 2/ at equivalent stress and temperature was lower by a factor of 3 than the minimum rate observed in oxygen. Chemical analyses, metallography, and experiments with carbon showed that carburization occurred in pure flowing CO/sub 2/ in the temperature range studied. From this evidence it was concluded that the strengthening observed in CO/sub 2/ was primarily due to carburization. The creep- and tensile-fracture strains were adversely affected by exposure to CO/sub 2/, with the magnitude of the effect dependent on the time and temperature of exposure. (auth)

The diffusion rate of O in anion-deficient zirconia, ZrO/sub 1.994/, was determined by the interface migration of stoichiometric oxide and is represented by the equation D = 0.055 exp (--33,400 surface proces 3100/RT). A comparison was made with other processes that occur in the metal and the oxide. Excellent agreement was noted between activation energies of O diffusion in ZrO/sub 1.944/ and those for parabolic or cubic oxidation in both air and water. It appears that O diffusion in the oxide is rate-controlling during oxidation of the metal. The corrosion and oxidation behavior of Zr and some alloys are discussed in terms of the oxide defect structure and the electric conductivity behavior in the oxide. A speculative mechanism for corrosion transition to linear rates was suggested on the basis of preferential oxidation of a grain boundary metallic phase. The nature of the phase and of its formation and elimination are discussed. (auth)

The method of singular eigenfunctions introduced first by Van Kampen and developed later by Case and Mika in connection with a one velocity transport problem, was adapted to solve the time and energy dependent infinite medium problem. The expansion of neutron density and scattering kernel in series of Hermite functions reduces the Boltzmann equation to a system of homogeneous linear equations. The resulting set of regular and singular eigenfunctions is shown to be complete and explicit formulas are found for the normalization integrals and Green's function. (auth)