An 8-Matrix Theory of the Vertex p - NN Based on the Strip Approximation (open access)

An 8-Matrix Theory of the Vertex p - NN Based on the Strip Approximation

The present study was motivated by an attempt to understand low energy [formula] scattering within the framework of the bootstrap principle and the un-Reggeized version of the strip approximation. This work attempts to generate low energy [formula] scattering in the p(1,1) and p(3,3) states assuming the potential operating in these states is generated by the exchange of low mass meson states in the crossed t-channel and low mass baryon states in the crossed u channel. In particular, the p-meson is kept in channel t; the p mass and the coupling of [formula] and [formula] appear as parameters. The parameters of the nucleon and (3,3) poles are taken as the elements to be determined by self-consistency.
Date: May 1964
Creator: Sarkissian, M. Der
Object Type: Report
System: The UNT Digital Library
The 25-Inch Liquid Hydrogen Bubble Chamber (open access)

The 25-Inch Liquid Hydrogen Bubble Chamber

None
Date: May 25, 1964
Creator: Barrera, F.; Byrns, R. A.; Eckman, G. J.; Hernandez, H. P.; Norgren, D. U.; Shand, A. J. et al.
Object Type: Report
System: The UNT Digital Library
30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 4, Operation and Maintenance Procedures (open access)

30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 4, Operation and Maintenance Procedures

Operation and maintenance procedures for 30 megawatt heat exchanger and steam generator for sodium cooled reactor system.
Date: May 15, 1962
Creator: Alco Products (Firm)
Object Type: Report
System: The UNT Digital Library
100-Watt Curium-242 Fueled Thermoelectric Generator--Conceptual Design. SNAP Subtask 5.7 Final Report (open access)

100-Watt Curium-242 Fueled Thermoelectric Generator--Conceptual Design. SNAP Subtask 5.7 Final Report

A thermoelectric generator which produces 100 watts of electrical power continuously over a six-month operational life in a space environment was designed. It employs the heat produced by the decay of Cm/sup 24/ as the source of power. Uniform output over the operational life of the generator is accomplished by means of a thermally actuated shutter which maintains the hot junction temperature of the thermoelectric conventer at a constunt figure by varying the amount of surplus heat which is radiated directly to space from the heat source. The isotopic heat source is designed to safely contain the Cm/sup 242/ under conditions of launch pad abont and rocket failure, but to burn up upon re-entry to the earth's atmosphere from orbital velocity. (W.L.H.)
Date: May 1, 1960
Creator: Weddell, J. B. & Bloom, J.
Object Type: Report
System: The UNT Digital Library
200 Area monthly report No. 4, April 1966 (open access)

200 Area monthly report No. 4, April 1966

This monthly report details activities of the 200 Area for the month of April 1966.
Date: May 10, 1966
Creator: Christy, J. T.
Object Type: Report
System: The UNT Digital Library
1559/RE: A CODE TO COMPUTE RESONANCE INTEGRALS IN MIXTURES (open access)

1559/RE: A CODE TO COMPUTE RESONANCE INTEGRALS IN MIXTURES

The computer program 1559/RE is an experimental IBM-704 code in FORTRAN language for computing the resonance integrals of isotopes in mixtures in the presence of hydrogenic moderation. There may be up to four isotopes, each with no more than 75 resolved resonance levels. Doppler broadening and interference scattering are included No estimate is made of contributions from unresolved resonances. Typical running times are 30 min (with no Doppler broadening) to 90 min (with Doppler broadening) for problems involving 67 levels and unit lethargy widths. Input and theory are discussed, and a typical listing is given. (auth)
Date: May 1, 1963
Creator: Kelber, C.N.
Object Type: Report
System: The UNT Digital Library
1965 audit of SRP radioactive waste (open access)

1965 audit of SRP radioactive waste

This report summarizes releases of radioactive waste to the environs of the Savannah River Plant during the calendar year 1965. Total quantities of radioactive waste released from plant startup through 1965 are also reported. Accuracy is not always implied to the degree indicated by the number of significant figures reported. Values were not rounded off, since data will be used in future cumulative summaries. No explanations are given for unusual releases; this information may be found in the Radiological and Environmental Sciences Division Monthly Reports and in the Semi- annual and Annual Environmental Monitoring Reports for 1965.
Date: May 1, 1966
Creator: Ashley, C.
Object Type: Report
System: The UNT Digital Library
2D PERT. A TWO-DIMENSIONAL PERTURBATION CODE (open access)

2D PERT. A TWO-DIMENSIONAL PERTURBATION CODE

Given multigroup fluxes and adjoint fluxes of any cylindrical R-Z configuration, 2D PERT may compute: the prompt-neutron lifetime; the relative worth of various delayed neutrons; the integrals of capture, fission, etc., of given materials over any given region; local perturbations, i.e., danger coefflcients; and integrated perturbations, i.e., reactivity effect of uniform variation in the cross sections affecting a whole region. 2D PERT is programmed for a 32K IBM-704 using 3 tape units. The code is written in FORTRAN with the exception of two SAP subroutines. Input fluxes and adjoint fluxes are on tapes which may be obtained either directly from CUREM output or manufactured by a special tape-writing routine. Homogeneous cross sections and variations of these cross sections are either read in as input information or are computed by the code from a microscopic-cross-section library and atomic densities given as input. A combination of these methods may be used. (auth)
Date: May 1, 1962
Creator: Chaumont, J. M. & Koerner, J. A.
Object Type: Report
System: The UNT Digital Library
630A MARITIME NUCLEAR STEAM GENERATOR. Progress Report No. 8 (open access)

630A MARITIME NUCLEAR STEAM GENERATOR. Progress Report No. 8

None
Date: May 1, 1964
Creator: unknown
Object Type: Report
System: The UNT Digital Library
ABWR QUARTERLY PROGRESS REPORT, JANUARY 1 TO MARCH 31, 1960. VOLUME I. SL- 1 OPERATIONS AND EVALUATION . VOLUME II. SL-1 HEALTH PHYSICS AND SAFETY (open access)

ABWR QUARTERLY PROGRESS REPORT, JANUARY 1 TO MARCH 31, 1960. VOLUME I. SL- 1 OPERATIONS AND EVALUATION . VOLUME II. SL-1 HEALTH PHYSICS AND SAFETY

The Stationary Low Power Reactor No. 1 is a three Mw boiling water reactor designed to demonstrate the feasibility of a nuclear reactor to supply electrical power and space heat for remote sites. In addition to performance evaluation the facility provides training for military personnel. The reactor was operated for 1159 hr during the quarter for a total core burnup of 20.3%. Power generation was 103.7 Mwd for a total power accumulation of 466.9 Mwd. Eight malfunctions occurred during the quarter for a total unscheduled downtime of 40 hr 44 min, As a result of malfunctions, aluminum keys will be installed on the control rod drives, instrument well covers were removed, and an order has been placed for a station auxiliaries breaker with a higher temperature rating. Data were taken on seven tests during the quarter. Four of these are expected to be completed during the next quarter. All equipment items on order for the SL-1 power extrapolation expansion program are scheduled to be delivered before June 15, 1960. Although condenser dampers and damper controls, process instrumentation, equipment cabinets, and the radiation monitoring equipment have not yet been ordered, construction will not be delayed. The two tie-ins to the existing …
Date: May 25, 1960
Creator: Canfield, R. T.; Rausch, W. P.; Vallario, E. J.; Young, R. G. & Henderson, S. K.
Object Type: Report
System: The UNT Digital Library
Accountability equations for plutonium and tritium yields for PT-IP-305-C at 105-H (open access)

Accountability equations for plutonium and tritium yields for PT-IP-305-C at 105-H

It is necessary to provide accountability tables and equations for use in routine product buildup predictions for the duration of the E-N and blanket loads charged under PT-IP-350-C. Recommended values are given.
Date: May 10, 1961
Creator: Nechodom, W. S.
Object Type: Report
System: The UNT Digital Library
AN ACCURATE CURRENT INTEGRATOR IN THE RANGE OF 10$sup -5$ TO 10$sup -9$ AMPERES (open access)

AN ACCURATE CURRENT INTEGRATOR IN THE RANGE OF 10$sup -5$ TO 10$sup -9$ AMPERES

None
Date: May 14, 1965
Creator: Law, L A & Weinstein, J
Object Type: Report
System: The UNT Digital Library
Active Metal Reduction of Plutonium Trichloride (open access)

Active Metal Reduction of Plutonium Trichloride

The reduction characteristics of plutonium trichloride are investigated. A flowsheet for batch reduction with Ca is included. (J.R.D.)
Date: May 1, 1960
Creator: Soine, T. S. & Hopkins, H. H., Jr.
Object Type: Report
System: The UNT Digital Library
ACTIVITY DUE TO N$sup 16$ AND N$sup 17$ IN THE HFIR PRIMARY COOLANT (open access)

ACTIVITY DUE TO N$sup 16$ AND N$sup 17$ IN THE HFIR PRIMARY COOLANT

The concentrations of and activities due to N/sup 16/ and N/sup 17/ in the HFIR primary coolant water were calculated. At the pressure vessel exit, the N/sup 16/ activity is 3.9 x 10/sup 6/ dis/secml and the N/sup 17/ activity is 6.9 x 10/sup 2/ dis/sec-ml. Comparison of the N/sup 16/ activity with the data obtained from the ORR water system indicates that the calculated results are slightly conservative. (auth)
Date: May 25, 1960
Creator: McLain, H. A.
Object Type: Report
System: The UNT Digital Library
Additional test on notched beryllium at 140$sup 0$R (EML-82) (open access)

Additional test on notched beryllium at 140$sup 0$R (EML-82)

None
Date: May 11, 1966
Creator: Hengstenberg, T.F.
Object Type: Report
System: The UNT Digital Library
Adjustment of total control parameters for C Reactor (open access)

Adjustment of total control parameters for C Reactor

The three alterations discussed in this report have an effect on the parameters used in Total Control Calculations for C Reactor: Conversion to smaller diameter and shorter vertical safety rods in six outer control channels; installation of forty-four overbored tubes with short fuel charges in the flat zone and an associated increase in spike enrichment; and centralization of the enrichment ring into a three-lattice unit width in place of three and one-half lattice units previously in use. New parameters are derived in this document for future total control calculations.
Date: May 22, 1962
Creator: Vaughn, A. D.
Object Type: Report
System: The UNT Digital Library
ADVANCED BONUS CORE DEVELOPMENT PROGRAM. Quarterly Progress Report No. 5, December 1964-February 1965 (open access)

ADVANCED BONUS CORE DEVELOPMENT PROGRAM. Quarterly Progress Report No. 5, December 1964-February 1965

None
Date: May 17, 1965
Creator: Gibbons, J F; Knapp, R W; Mordarski, W J; Anderson, L E & Grubelich, F T
Object Type: Report
System: The UNT Digital Library
Advanced, graphite-matrix, dispersion-type fuel systems. First annual report, April 1, 1962--March 31, 1963 (open access)

Advanced, graphite-matrix, dispersion-type fuel systems. First annual report, April 1, 1962--March 31, 1963

Declassified 4 Sep 1973. A hot-working device for compression of graphite bodies was used to deform cylindrical specimens of matrix graphite containing ZrC or UC-ZrC particles to strains of the order of 30% at temperatures of 2400 to 2900 deg C. The graphite bodies containing ZrC particles (chosen as representative carbide particles) were found to be more plastic near 2500 deg C than similar bodies containing no carbide particles. Microradiographic techniques were used to determine diffusion coefficients of U and Th on actual coated particles by nondestructive means. A tentative energy of activation for the migration of uranium from UC/sub 2/ particles into PyC coatings was determined over the temperature range 1850 to 2300 deg C. The penetration of U into the coatings is not uniform but occurs radially in localized positions, and then spreads circumferentially, creating a banded structure. These results show the importance of the structure of PyC in regard to the diffusion of both fuel and fission-product materials. It was also observed that the diffusion of U is considerably more rapid in the direction parallel to the layer planes in the PyC than it is in the perpendicular direction. Tests with PyC-coated (U, Zr)C particles in graphite-matrix …
Date: May 1, 1963
Creator: Goeddel, W.V.; Sandefur, N.L. & White, J.L.
Object Type: Report
System: The UNT Digital Library
Advanced Nuclear Rocket Materials Research (open access)

Advanced Nuclear Rocket Materials Research

A number of metals, carbides, nitrides, oxides, borides, and uranium gulfides are briefly evaluated concerning their possible applications as advanced nuclear rocket materials. (R.J.S.)
Date: May 31, 1962
Creator: unknown
Object Type: Report
System: The UNT Digital Library
The Advisory Commission on Intergovernmental Relations. (open access)

The Advisory Commission on Intergovernmental Relations.

The ACIR Library is composed of publications that study the interactions between different levels of government. This document addresses the ACIR itself for the year 1967.
Date: May 1, 1967
Creator: United States. Advisory Commission on Intergovernmental Relations.
Object Type: Book
System: The UNT Digital Library
Aeroradioactivity Survey and Related Surface Geology of Parts of the Los Angeles Region, California (ARMS-I) (open access)

Aeroradioactivity Survey and Related Surface Geology of Parts of the Los Angeles Region, California (ARMS-I)

Report regarding an airborne gamma-radioactivity survey that took place in the 2,800 square mile area around the Los Angeles region in California. Topics include the types of bedrock noted in the area as well as their levels of radioactivity.
Date: May 1961
Creator: Books, Kenneth G.
Object Type: Report
System: The UNT Digital Library
Aeroradioactivity Survey and Related Surface Geology of Parts of the San Francisco Region, California (ARMS-I) (open access)

Aeroradioactivity Survey and Related Surface Geology of Parts of the San Francisco Region, California (ARMS-I)

This report follows an aeroradioactivity survey that took place in the San Francisco region, California.
Date: May 1966
Creator: Books, Kenneth G.
Object Type: Report
System: The UNT Digital Library
Aerospace Nuclear Safety Program at Sandia Corporation. Summary of a Speech (open access)

Aerospace Nuclear Safety Program at Sandia Corporation. Summary of a Speech

This report describes research, development, support, and test activities in the Sandia Laboratory Aerospace Nuclear Safety Program.
Date: May 1, 1965
Creator: Colp, J. L.
Object Type: Report
System: The UNT Digital Library