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HRT Reactor Hazards

Description: Several potential hazards that have been recognized and anticipated in the design and fabrication of the pressure vessel in the Homogeneous Reactor Test are discussed. These hazards results from the high operating pressure and temperature of the reactor, the exposure of the reactor vessel material to potential embrittlement and other affects of fast-neutron irradiation, and the need for containment of corrosive flowing liquids. The steps taken in recognition of these hazards are also discussed. The applicability of present codes to the reactor vessel fabrication is considered. Additional fields are suggested where recommended practices developed by code writing bodies could assist in development-type reactor design and fabrication.
Date: August 3, 1956
Creator: Miller, E. C.
Partner: UNT Libraries Government Documents Department
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HRP Radiation Corrosion Studies

Description: A fifth in-pile loop experiment, L-4-8, was completed. The loop operated in-pile for a total of 1637 hr, during which time the LITR energy output was 4377 Mwhr. The average fission power in the loop based o cesium analyses was 622 w when the LITR was at full power (3 Mw). Based on oxygen data, the generalized corrosion rate for the first 300 hr was 4.0 mpy; the rate for the remaining 1357 hr was 0.7 mpy. The nickel data gave parallel results. The corrosion of the type 347 stainless steel, Zircaloy-2, and Ti-55AX [unintelligible] exposed in the core and in in-line holders was generally consistent with that observed in previous in-pile loop experiments. Some differences with steel were attributed to the fact that this was the first loop containing steel specimens operated with 0.04 m H2SO4 present in the uranyl sulfate charge solution (0.17 m UO2SO4, 0.03 m CuSO4). Stress specimens, made from the alloys Zircaloy-2, type 17-4 PH stainless steel, and Ti-C-130-AM, were exposed in care, in-line, and pressurizer locations. Microscopic examination and average weight loss gave no indication of effects attributable to the stressed condition of the specimens.
Date: August 21, 1956
Creator: Baker, J. E.; Bradley, N. C.; Jenks, G. H.; Olsen, A. R.; Savage, H. C. & Walter, F. J.
Partner: UNT Libraries Government Documents Department
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Investigation of Materials for a Water Cooled and Moderated Reactor [Secret Version]

Description: An investigation of the materials for use in the water-moderated and cooled Aray Package Power Reactor (APPR) operating at about 500°F was made. The available literature was analyzed, and the results of the different investigators were compared and averaged. Twenty different materials, including stainless steels, nickel alloys, Stellites and others, were investigated from the point of view of physical properties, susceptibility to radiation damage, and corrosion resistance. Corrosion rates were established for all the materials under various conditions, such as irradiation, flow, weld, stress, and various water conditions. Type-304 stainless steel was selected as the basic structural material. Operating conditions, to maintain minimum corrosion, were established also.
Date: August 1954
Creator: Scheib, Louis
Partner: UNT Libraries Government Documents Department
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Investigation of Materials for a Water Cooled and Moderated Reactor [Declassified Version]

Description: An investigation of the materials for use in the water-moderated and cooled Aray Package Power Reactor (APPR) operating at about 500°F was made. The available literature was analyzed, and the results of the different investigators were compared and averaged. Twenty different materials, including stainless steels, nickel alloys, Stellites and others, were investigated from the point of view of physical properties, susceptibility to radiation damage, and corrosion resistance. Corrosion rates were established for all the materials under various conditions, such as irradiation, flow weld, stress, and various water conditions. Type-304 stainless steel was selected as the basic structural material. Operating conditions, to maintain minimum corrosion, were established also.
Date: August 1954
Creator: Scheib, Louis
Partner: UNT Libraries Government Documents Department
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Remarks on the Double Dispersion Approach to the Bethe-Salpeter Equation

Description: The following remarks are made on the applicability of the double dispersion approach to the Beth-Salpeter equation introduced previously. 1) Any invariant solution of the Bethe-Salpeter equation in ladder approximation satisfies the double dispersion representation when the total energy-momentum is space-lake. 2) There are some exceptional invariant solutions which are not given by the previous method in the equal-mass case, but the existence of such solutions is very unlikely in the unequal-mass case. 3) In the case of the general separated kernel the previous results give the correct solutions even if the kernel does not reproduce the double dispersion representation.
Date: August 7, 1962
Creator: Nakanishi, Noboru
Partner: UNT Libraries Government Documents Department
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Theory of Final State Interactions

Description: Using requirements of analyticity and the unitarity of the S-matrix we obtain the dependence of a transition amplitude on the invariant mass of two particles strongly coupled to other two particle channels. As an example, we consider the production of a Σπ state near the Y*₀ resonance assuming it is coupled to a KN state in an s 1/2 state.
Date: August 20, 1962
Creator: Nauenberg, Michael
Partner: UNT Libraries Government Documents Department
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Pion Resonances in π⁻-p Interactions at 4.65 Bev/c

Description: This note describes some results of the study of single pion production in π⁻-p interactions at 4.65 Bev/c, using the BNL 20" Hydrogen Bubble Chamber. It is well known that the observability of some of the particle resonances (e.g. 33 Isobar and η) varies markedly with the energy of the incident particle. The ρ meson has been observed in π⁻-p interactions at 1.25 Bev/c and 1.9 Bev/c incident pion energies. Evidence will be shown that this resonance persists with the much higher incident pion energy used in the present experiment.
Date: August 9, 1962
Creator: Munir, B.A. & Zorn, G. T.
Partner: UNT Libraries Government Documents Department
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BEFCYF And DBDT: IBM 704 Codes For Preparing Input For Bevatron Orbit Code (BOC)

Description: Two IBM-704 codes have been written which are auxiliary to the Bevatron orbit code BOC. The first, BEFCYF, interpolates among tabulated values of the median-plane magnetic flux density of the Bevatron to produce an equivalent array of values in a form appropriate to BOC. The second, DBDT, produces azimuthal derivatives of the fields produced by BEFCYF. The internal operation of BEFCYF and DBDT is described, and instructions for their execution are given.
Date: August 30, 1960
Creator: Gardner, C. Gerald
Partner: UNT Libraries Government Documents Department
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Particle Accelerators

Description: The principal types of particle accelerators are described briefly according to operation and history. Known operating particle accelerators are listed with their pertinent dimensions.
Date: August 1, 1960
Creator: Gordon, Hayden S. & Behman, Gerald A.
Partner: UNT Libraries Government Documents Department
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The Interactions Of Strange Particles

Description: This report is a corrected copy of the authors "rapporteur talk" at the 1959 Kiev Conference on High Energy Physics. It contains data on the rapporteur system and on interactions of strange particles with protons and neutrons, using data from bubble chambers, counters, and emulsions.
Date: August 11, 1960
Creator: Alvarez, Luis W.
Partner: UNT Libraries Government Documents Department
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A Separated 1.17-Bev/c K {sup -} Meson Beam

Description: This report describes the design and testing of a 1.17-Bev/c separated K{sup -} beam designed in the fall of 1958 in connection with a 15-in. hydrogen bubble chamber experiment.
Date: August 25, 1959
Creator: Eberhard, Phillippe; Good, Myron L. & Ticho, Harold K., 1921-2020
Partner: UNT Libraries Government Documents Department
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Equipment And Methods For Automatic Track Analysis

Description: The writer has initiated a comprehensive program of equipment development designed to give the maximum practical aid to the physicists and technicians who are carrying out track measurements. Some attention has also been given to developing systems of data handling using International Business Machine (IBM) equipment and Keysort cards. In addition, some of the steps to insure the accuracy of the emulsion data are taken long before the emulsion is studied under the microscope.
Date: August 14, 1958
Creator: Barkas, Walter H. (Walter Henry), 1912-1969
Partner: UNT Libraries Government Documents Department
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Unstable Particles As Targets In Scattering Experiments

Description: A general method is suggested for analyzing the scattering of particle A by particle B, leading to three or more final particles, in order to obtain the cross section for the interaction of A with a particle which is virtually contained in B. Binding complications are absent if a plausible assumption about the location and residues of poles in the S-matrix is accepted. The method is useful for unstable particles from which free targets cannot be made; the special examples of pion and neutron targets are discussed in detail.
Date: August 21, 1958
Creator: Chew, Geoffrey F. & Low, Francis E. (Francis Eugene), 1921-2007
Partner: UNT Libraries Government Documents Department
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Effect Of Densely Ionizing Radiations On Dry Preparations Of Lysozyme, Trypsin, And DNase

Description: The present studies are carried out in order to elucidate the effect on enzyme activity of different kinds of radiation. Beams of protons and alpha particles from the Berkeley 60-inch cyclotron and beams of accelerated nuclei of helium, carbon 12, oxygen 16, and neon 20 from the Berkeley Heavy Ion Linear Accelerator (HILAC) have been used. With this variety of particles it has been possible to cover a range of LET 10 times greater than previously utilized in similar studies. The unattenuated energy of the different particles is exactly 10 MeV per nucleon for the HILAC radiation and approximately this value for the cyclotron radiation.
Date: August 1958
Creator: Brustad, Tor
Partner: UNT Libraries Government Documents Department
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Code Listings for the Floss III - Compatible Programs Including Floss Type 3 and Type 12, Nomac, and Dash N

Description: FLOSS III is a third-generation version of a digital computer program which solves a one-dimensional difference representation of the momentum, energy, continuity, and state equations for turbulent, compressible gas flow in equivalent hydraulic channels. Extensive use of this program has been employed in the design and performance analyses of Pluto-type nuclear heat exchangers, and in the specific case of the Tory II-A test series, agreement was obtained to better than 5% for all experimentally measured parameters. The NOMAC and DASH-N programs combine the effects of up to thirty varieties of channels with the dependent boundary conditions imposed by a common inlet diffuser and exit nozzle. The resulting calculations yield performance information for blow-down facility and ramjet flight condition application of the heat exchanger.
Date: August 9, 1963
Creator: Mintz, Michael D.
Partner: UNT Libraries Government Documents Department
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Minutes of the Conference of Linear Accelerators for High Energies

Description: During the past year notable progress was made in several laboratories on design for linear accelerators in the energy range up to and above 1 Bev. Interest in linacs for this energy centers on two possible applications: first, as injectors for 300 to 1000 Bev synchrotrons, and second, as sources of intense meson beams. To review this progress, a conference jointly sponsored by the Brookhaven National Laboratory and Yale University was held at Brookhaven during the week of August 20, 1962.
Date: 1962-08-20/1962-08-24
Creator: Blewett, J. P.; van Steenbergen, A.; Knowles, H. B.; Ohnuma, S. & Sinclair, C. K.
Partner: UNT Libraries Government Documents Department
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Operating Manual for the Argonaut Reactor

Description: The design of the Argonaut (Argonne Nuclear Assembly for University Training) was initiated by the Reactor Engineering Division of Argonne National Laboratory to satisfy needs for a low-power reactor facility within the Laboratory, and for training uses within the international School of Nuclear Science and Engineering (ISNSE). It was intended primarily for instruction and research in reactor physics. It was also considered as a possibility that it would fulfill the requirements of universities engaged in a program of nuclear science. The cost of the facility was to be kept to a minimum consistent with the high degree of inherent safety and a great amount of flexibility in the system. The basic design stemmed from the Knolls Atomic Power Laboratory Thermal Test Reactor* (TTR), now called Nuclear Test Reactor (NTR). Modification during the course of the work justified the new name "Argonaut".
Date: August 1959
Creator: Argonne National Laboratory
Partner: UNT Libraries Government Documents Department
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Further End Cap Temperature Calculations

Description: Abstract. Recently (CP-1989) it has been shown that the neutron density, and thus the heat production, at the end of a slug with an A1 cap may be appreciably higher than that at the middle of the slag. A re-examination of earlier temperature calculations is made in light of this effect.
Date: August 16, 1944
Creator: Karush, William; Monk, A. T. & Wilkins, J. Ernest, Jr., 1923-2011
Partner: UNT Libraries Government Documents Department
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Warping Instability in Long Rods

Description: Abstract. If a pile rod gets bowed within its cooling tube it becomes warmer on the side which approaches the tube wall, and thermal expansion tends to warp it in the same direction as the original displacement. This was discussed roughly in N-601, and it was there concluded that the mechanism was not important for an isolated short slug. In connection with current development of continuous jacket (cartridge) assemblies, it seems desirable to look at this question again. In this case it is possible that the effect may be of some concern.
Date: August 17, 1944
Creator: Young, Gale Jay
Partner: UNT Libraries Government Documents Department
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The Distribution of Thermal Neutrons in a Slug with Thick End Caps

Description: The distribution of thermal neutrons in a W slug having a one centimeter aluminum end cap has been calculated on the basis of simple diffusion theory. It is found that the average neutron density, and therefore the power output, at the end of the slug is about 34% higher than the density far from the end cap. This result agrees well with the recent Argonne pile experiments (CP-1729).
Date: August 3, 1944
Creator: Wilkins, J. Ernest, Jr., 1923-2011
Partner: UNT Libraries Government Documents Department
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Temperature and Heat Flow in a Graphite Electrode

Description: In making various experimental heat studies a power producing metal slug is simulated by a slug with a graphite rod electrode of 3/8" diameter inserted lengthwise through it. There is a helium filled annular space between the graphite and the inner surface of the slug cylinder. Radiant heat passes from the electrode to the metal; with proper adjustment of the electrode current the slug in the steady state will therefor "produce" the same amount of energy from its exterior surface as it would under operating conditions. The question arises, however, as to how uniform the electrode temperature is along its length. And also, in some cases one end of the electrode is embedded in the slug metal; it is then desirable to know how much heat flows by conduction from the electrode into the slug.
Date: August 3, 1944
Creator: Schlegel, R.
Partner: UNT Libraries Government Documents Department
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Space Propulsion and Auxiliary Power Units: a Bibliography

Description: This partially annotated bibliography contains references on advanced space propulsion units. References are also included on auxiliary power units, energy requirements, and mission requirements. The references are arranged alphabetically by title, with corporate author and subject indexes provided. This bibliography is issued in two parts: CNLM-2370-3, Part I, contains unclassified references; CNLM2370-3, Part II, contains classified material. Sources used in compiling this bibliography are: Abstracts of Classified Reports 1957-June 1960, Applied Science and Technology Index 1958-June 1960, ASTIA 1958-June 1960, Engineering Index 1957-1959, Industrial Arts Index 1957, Nuclear Science Abstracts 1957-June 1960, U.S. Government Publications Monthly Catalog 1958-June 1960.
Date: August 2, 1960
Creator: Cernak, Elizabeth A.
Partner: UNT Libraries Government Documents Department
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