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Revised Version of HFIR Critical Experiment-2 (HFCE-2)

Description: A listing and description is given of the experiments associated with the HFIR Critical Experiment-2. The primary experiments concern the reactivity of the bare core, reactivity worth of "gray" control plates, core-power distribution, reactivity. The secondary experiments concern the reactivity of the fuel, and the reactivity worth of a "partial" gray plate.
Date: January 16, 1961
Creator: Kasten, P. R. & Cheverton, R. D.
Item Type: Refine your search to only Report
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Determination of the S. S. N. M. Content of the Shipment to the Davison Chemical Company, Erwin, Tennessee, December 20, 1960

Description: A carrier containing 138.99 liters of solution, uranium concentration 202.04 g/liter with an isotopic concentration of 97.3% U-233, was prepared for shipment. The total uranium was 28,062 +/- 60 g (95% confidence level) and the U-233, 27,305 +/- 66 g (95% confidence level).
Date: January 11, 1961
Creator: Sadowski, G. S.
Item Type: Refine your search to only Report
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Summary of Runs 1, 2, and 3 in High-Temperature, High-Pressure Titanium Loop

Description: Simulated reactor fuel solutions were circulated at temperatures as high as 365°C in a small titanium pump loop. A hydroclone separator separated heavy phases formed at high temperatures. As the temperature of the solution was increased beyond the two-liquid-phase temperature (327°C), the salt concentration of the light phase decreased and the acid concentration increased. The mole ratios of uranium to sulfate, uranium to copper, and uranium to nickel in the light phase decreased in the same pr… more
Date: January 6, 1961
Creator: Griess, J. C.; Baker, J. M. & Savage, H. C.
Item Type: Refine your search to only Report

Water Treatment in Aqueous Homogeneous Reactors, Experience in HRE-2

Description: A method for water treatment has been developed for corrosion protection in the steam-water cycle of Homogeneous Reactor Experiment No. 2. The use of potassium phosphates for pH control, hydrazine for oxygen removal, and limitation of chlorides in the boiler water to less than 1 ppm has resulted in trouble-free operation of the steam system from December 1957 to December 1960.
Date: unknown
Creator: Neumann, P. D.
Item Type: Refine your search to only Report
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ORR Startup Accident and Cooling Flow Coastdown Analog Analysis

Description: Startup accident and pump run-down on the ORR have been simulated on the Reactor Controls Analog Facility. At full flow the 150% level scram (45 Mv) easily terminates the startup accident before the metal temperature gets above 180°F. For very low flows typical of criticality runs, temperature coefficients turn the excursion before it reaches 150% of full power, and temperatures climb to boiling, a potentially hazardous condition. (This same behavior can occur at full flow is the power is incr… more
Date: January 4, 1961
Creator: Stone, R. S. & Colomb, A. L.
Item Type: Refine your search to only Report
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Dispersion Strengthening of Iron-Aluminum Base Alloys: A Feasibility Study

Description: The feasibility of improving the mechanical properties at 1700-1800°F of oxidation-resistant Fe-Al-Cr alloys by means of a refractory dispersion has been explored. A literature search was conducted, preliminary experimental determinations of properties of the alloy and its oxides were carried out, and certain mathematical relations between dispersion characteristics and metallurgical variables were derived. The results indicate that the alloys can be strengthened sufficiently by using a dispers… more
Date: December 27, 1960
Creator: King, Blake
Item Type: Refine your search to only Report
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After Shutdown Heating in the HFIR

Description: After shutdown heating rates have been calculated for the target, control plates, and the beryllium reflector of the HFIR. Hilvety previously calculated the after shutdown heating rates in the element and his results are reported in ORNL CP-60-4-110. Decay times of 1.0 10, 10^2, 10^3, 10^4, and 10^5 seconds have been considered, and heat fluxes have been computed for all of the mentioned components. The greatest heat fluxes were found to be at the surfaces of the control plates and the permanen… more
Date: December 29, 1960
Creator: McLain, H. A.
Item Type: Refine your search to only Report
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Status Report on the Pneumatic Temperature Measuring system Studies for the EGCR

Description: The pneumatic temperature probe (PIM) is a device for measuring gas temperatures by utilizing the dependency of the flow of gases through a restriction on the temperature and pressure conditions. The determination is made by measuring critical mass flow across a restrictive element such as a nozzle and by knowing the upstream pressure and other variables pertinent to the critical flow equation, computing the temperature at the entrance to the restrictive element. In practice it has been found u… more
Date: December 30, 1960
Creator: Hochreiter, H. M.
Item Type: Refine your search to only Report
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Homogeneous Molten Salt Reactors

Description: Multigroup one-dimensional calculations were done recently to obtain estimates of critical masses, power density distributions and fissioning spectra for some homogeneous molten salt reactors having outer reflectors and central "islands," placed inside the currently proposed MSRE vessel. For a 5-inch-thick outer reflector and 1-ft-diamter island, both beryllium, the calculated critical mass is 108 kg; 40 percent of the fissions occur at thermal, and the maximum power density of 3.9 times the co… more
Date: December 13, 1960
Creator: Nestor, C. W., Jr
Item Type: Refine your search to only Report
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Thermal-Neutron Flux at the HRE-2 Core Wall, Determined from Zircaloy-2 Induced-Activity Measurements During Runs 13, 14, 16, 17, 18, 19, 20 and 21.

Description: The thermal-neutron flux prevailing near the upper hole in the HRE-2 core wall was determined from measurements of the induced activity in a specimen cut from the edge of the hole. The specimen was removed following run 21 and was thus exposed to reactor neutrons during runs 13, 14, 16,17, 18. 19, 20, and 21. The neutron flux, calculated for an average core power level of 2 Mw, was 2.8 x10^13 neutrons/cm^2 sec. the core wall area from which the specimen was removed was located approximately 16-… more
Date: December 20, 1960
Creator: Baker, J. E.
Item Type: Refine your search to only Report
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Steady-State Radial and Axial Temperature Profiles of an E. G. C. R. 5 1/2" O. D. Through Tube During 1500 KW Operation - Part II

Description: The steady-state radial and axial temperature profiles of an E. G. C. R. 5 1/2" O. D. through tube are determined for the test condition of an attemperated fuel assembly operating at 1500 KW in the loop. The profiles are determined for the case of the central control rod fully inserted and bank insertion to 62 inches (Δk = 0.025). The data are presented in the form of tables and curves.
Date: December 30, 1960
Creator: Noggle, L. W.
Item Type: Refine your search to only Report
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Analog Computer Analysis of the Thermal Behavior of the EDCR Due to Reactivity Accidents

Description: The ORNL analog computer was used to examine one aspect of a safety system for the EGCR. The thermal behavior of the fuel as a result of increases in reactivity at various power levels and gas flows was examined. Safety actions initiated by wither a flux-minus-flow signal or a reactor outlet gas temperature signal were included in simulation.
Date: December 16, 1960
Creator: Pierce, R. M.
Item Type: Refine your search to only Report
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Use of Convergent and Asymptotic Series for Computation of the Modified Bessel Function of the First Kind.

Description: In the Communications of the ACM of April, 1960, p. 240, there appeared two Algol algorithms for the computation of In, the modified Bessel function of the first kind. One of these algorithms uses a convergent series and the other an asymptotic series. Their author, Dorothea S. Clarke, did not give any information with regard to which algorithm is more appropriate in a given situation (a given situation meaning the computation of In (x) for a definite pair of numbers n and x). Such information … more
Date: December 12, 1960
Creator: Bumgarner, L. L.
Item Type: Refine your search to only Report
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Analysis of Uranium Fuel-Element Wafers from Atomics International for Uranium, Plutonium and Samarium

Description: Five irradiated and five unirradiated wafers were analyzed. Each wafer was analyzed for samarium by emission spectrography. The unirradiated wafers were analyzed for uranium by coulometric and potentiometric methods and for uranium isotopes by mass spectrometry. The irradiated wafers were analyzed for uranium and plutonium by coulometric methods, for plutonium isotopes by the 256-channel alpha pulse analyzer, and for the isotopes of uranium and of plutonium by mass spectrometry. The methods of … more
Date: December 27, 1960
Creator: Gaitanis, M. J.
Item Type: Refine your search to only Report
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A Statistical Model of Nuclear Level Spacings

Description: A generalization of Wigner's simple model for the distribution of nuclear level spacings is studied. It is based on a stochastic process which reproduces the correct joing probability distribution of N enerfy levels for small spacings. The case N=3, which includes the effect of the correlation between adjacent spacings, is discussed in detail. The resulting distribution and the correlation coefficient are compared with experimental data. No definite conclusion can be drawn except to say that th… more
Date: December 4, 1960
Creator: Dresner, L. & Inönü, E.
Item Type: Refine your search to only Report
open access

A Transport Calculation of the HFIR Beam Hole Currents

Description: An estimate was made of the beam hole currents to be expected from both the radial and tangential beam holes in the present HFIR design. The angular fluxes required for these calculation were determined by an 18-group, S8 transport calculation (SNG reactor code). Both type beam holes produced thermal neutron currents of 7.5 x 10^10 neutrons/cm^2 sec. at a power level of 100 Mw. The nonthermal component of the beam current was 7.0 x 10^10 and 4.5 x 10^10 neutrons/cm^2 -sec for the radial and tan… more
Date: December 5, 1960
Creator: Claiborne, H. C. & Rakavy, G.
Item Type: Refine your search to only Report
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Fission Product Release from UO2 and by High Temperature Diffusion and Melting in Helium and Air.

Description: The experimental demonstration of fission product release from over heated reactor fuel is necessarily subject in many respects to the arbitrary conditions imposed by the experimenter. Since an almost infinite latitude exists in the choice of materials, atmospheres, gas, velocities, temperatures etc., some allowance for an extrapolation to alternate conditions is definitely in order. The conditions imposed in this study are best described as those most likely to maximize fission product release… more
Date: February 8, 1961
Creator: Parker, G. W.; Creek, G. E. & Martin, W. J.
Item Type: Refine your search to only Report
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Design Study of a Pebble-Bed Reactor Power Plant

Description: Sanderson & Porter have carried out a series of studies over the last four years which indicate that the pebble-bed reactor way be an attractive way to obtain low-cost power. At the request of the Atomic Energy Commission, two design studies have been carried out on this concept at the Oak Ridge National Laboratory. The first of these a preliminary design of a 10-Mw(t) reactor experiment, the PRRE, was initiated September 10, and a report on the study was issued November 1960. The second phase … more
Date: May 11, 1961
Creator: Fraas, A. P.; Carlsmith, R. S.; Corum, J. M. & Foster, J.
Item Type: Refine your search to only Report
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Chemical Development Section C Progress Report for October-November 1960

Description: Studies are being made on the recovery of thorium (and uranium) from granitic rock, since this source represents a very large potential thorium reserve for the nuclear power industry. In preliminary leaching studies on 16 granite samples (containing 8-95 ppm thorium and 1.5-16 ppm uranium), maximum recoveries of thorium and uranium ranged 30-85% and 15-65% respectively, and sulfuric acid consumption was high (30-120 lbs H2SO4 per ton of granite). A relatively high acidity was needed to obtain r… more
Date: March 3, 1961
Creator: Brown, K. B.
Item Type: Refine your search to only Report
open access

Radioactivation Analysis

Description: The development of nuclear reactors and other sources of nuclear particles has provided the analyst with a new method which has been successfully applied to the determination of microgram and even submicrogram quantities of many elements. In this method, known as "radioactivation analysis," the element to be determined is "activated" through some type of nuclear reaction which produces a radioactive isotope of the element. Since the radioisotope produced decays with its own characteristic radia… more
Date: September 22, 1961
Creator: Leddicotte, G. W.
Item Type: Refine your search to only Report
open access

Radioactivation Analysis

Description: The development of nuclear reactors and other nuclear particle sources has given the analyst a new analysis method which can be successfully applied to the determination of microgram and submicrogram quantities of many elements. Known as "radioactivation analysis", this method is one in which an "activation" by some type of nuclear reaction is used to produce a radioactive isotope of the element to be determined. Since this radioisotope decays with its own characteristic radiations and half-lif… more
Date: November 30, 1960
Creator: Leddicotte, G. W.
Item Type: Refine your search to only Report
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