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Addition of Tomographic Capabilities to NMIS

Description: This paper describes tomographic capabilities for the Nuclear Materials Identification System (NMIS). The tomographic capabilities add weapons component spatial and material properties information that result in a more detailed item signature (template) and provide more information for physical attributes analyses. The Nuclear Materials Identification System (NMIS) is used routinely to confirm the identity of HEU components in sealed containers. It does this through a radiation signature acquir… more
Date: March 11, 2003
Creator: Mullens, J. A.
Partner: UNT Libraries Government Documents Department
open access

Dry Maintenance Facility for the HRT

Description: A portable shield has been designed, developed, fabricated and shop tested to provide the HRT with a facility for direct dry maintenance operations. It provides temporary replacement for any one of the lower roof plugs and should permit many operations to be performed without flooding the reactor cell with water.
Date: October 11, 1960
Creator: Holz, P. P.
Partner: UNT Libraries Government Documents Department
open access

Local Reactivity "Worth" in the HRT

Description: The effect of adding small quantities of fuel or poison to the HRT has been estimated using perturbation theory. The results have been reduced to a single relation and a set of graphs which make the estimation of added reactivity relatively simple. The perturbation theory results are compared with multigroup results and reasonable agreement is demonstrated; however, there is some question concerning the prompt neutron lifetime.
Date: October 11, 1960
Creator: Jaye, S. & Vondy, D. R.
Partner: UNT Libraries Government Documents Department
open access

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.
Partner: UNT Libraries Government Documents Department
open access

Semipermanent Freeze Plug Tests for HRT-CP

Description: Five uninsulated semipermanent freeze coils, series connected, can be frozen when submerged in 70 F water with a Freon-11 flow rate of 1.85 gpm at an inlet temperature of -40 F. The refrigeration unit of the HRT-CP is capable of delivering >3 gpm to a similar semipermanent freeze coil system located in Cell C. Therefore the number of F-11 risers required in Cell C of the HRT-CP can be minimized by series connecting this many semipermanent freeze coils where required.
Date: March 11, 1957
Creator: Winget, R. H.
Partner: UNT Libraries Government Documents Department
open access

Curve Plotting Routine for the Oracle

Description: A general program has been written to plot curves on the Oracle curve plotter. A description of the code and complete instructions for preparation of input tapes and operation of the code are given. The code tape is available from the Mathematics Panel or from the author.
Date: April 11, 1957
Creator: Lietzke, M. P.
Partner: UNT Libraries Government Documents Department
open access

A Brief Review of thermal Gradient Mass Transfer in Sodium and NaK Systems

Description: The fact that material transport does occur under conditions of finite temperature difference in a flowing molten metal system was established. The rate mass transfer was thought to be either diffusion limited or solution rate limited. It is believed that the mass transfer of structural materials in Na or NaK systems is solution rate limited. The limiting process has not been qualitatively or quantitatively confirmed for the Inconel-Na or Inconel-NaK system. Increasing the maximum system wall t… more
Date: February 11, 1957
Creator: DeVan, J. H. & West, J. B.
Partner: UNT Libraries Government Documents Department
open access

Two Group Calculations for Flux Distribution and Critical Mass in Clean Cold ORR Cores

Description: A series of two-group calculations has been made on the Oracle for the purpose of obtaining critical-mass and flux distribution data for various ORR core configurations. The 3G3R code of Bate, Einstein, and Kinney was used, together with the RSP code developed by Nelson. This made it possible to obtain results for the three-dimensional case. The results, which are presented graphically, are intended to serve as a guide for the design of experiments until such time as actual measurements are ava… more
Date: March 11, 1958
Creator: Binford, F. T.
Partner: UNT Libraries Government Documents Department
open access

Cross Sections for OCUSOL-A Program

Description: The OCUSOL-A program (ORNL-CF-57-6-4) for Univac is a modification of the Eyewash (ORNL-1925) multi-group, multi-region reactor code. The group=energy-lethargy-temperature relationship are given in Table A. The element code numbers are given in Table B. The cross sections now on the sigma-tape are given in tables in the Appendix numbered with the element code number. This technical report explains the bases for choosing the cross sections.
Date: June 11, 1957
Creator: Roberts, J. T. & Alexander, L. G.
Partner: UNT Libraries Government Documents Department
open access

The Reaction of Zirconium with Uranium Dioxide

Description: An investigation of the causes of observed explosive reaction of zirconium-coated uranium dioxide on dissolution in nitric acid was conducted. It was concluded that such a reaction is to be expected. Possible but unconfirmed methods of alleviating the problem are suggested.
Date: June 11, 1957
Creator: Robinson, M. T.
Partner: UNT Libraries Government Documents Department
open access

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.
Partner: UNT Libraries Government Documents Department
open access

Experiments on the Release of Fission Products from Molten Reactor Fuels

Description: Experiments in the controlled melting of irradiated fuel specimens, particularly of the APPR, STR, and MTR types, have confirmed that prolonged heating in air at temperatures in excess of the melting point results in the release of a large portion of the radioactivity. On the other hand, a moderate amount of heating in air or steam sufficient only to melt a specimen results mainly in the partial volatilization of rare gases, iodine, bromine, cesium, and rubidium. In the presence of air or water… more
Date: March 11, 1958
Creator: Parker, George W. & Creek, George E.
Partner: UNT Libraries Government Documents Department
open access

A Preliminary Study of Pre-Solvent Extraction Treatment of Stainless Steel-Uranium Fuels with Dilute Aqua Regia

Description: The continuous dissolution of 304 stainless steel and stainless steel-UO2 alloy in dilute aqua regia was studied with subsequent stripping of the dissolver product to remove chloride ion. The process has the advantage of producing, by means of a simple head end treatment, a solvent extract feed in a conventional nitric acid medium so that existing solvent extraction processes, materials of construction and waste disposal methods can be used. The purposes of this study were to investigate the va… more
Date: October 11, 1957
Creator: Kitts, F. G. & Perona, J. J.
Partner: UNT Libraries Government Documents Department
open access

Artificial Intelligence for Nuclear Deterrence Strategy 2023

Description: This report describes how the Advanced Simulation and Computing (ASC) program plans to deploy AI methods in the unique high-security and high-consequence environment in which the National Nuclear Security Administration (NNSA) must operate.
Date: March 11, 2024
Creator: United States. Department of Energy.
Partner: UNT Libraries Government Documents Department
open access

NOAA Artificial Intelligence Strategic Plan 2021-2025

Description: This report is a continuation of the original report from 2020. The goals of this report is to guide transformational advancements in the quality and timeliness of products and services across the agency's mission areas.
Date: January 11, 2021
Creator: United States. National Marine Fisheries Service.
Partner: UNT Libraries Government Documents Department
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