In a previous report on effects of thermal discharges from power plants into the Great Lakes, we stressed the need for a statistical analysis of the spatial and temporal pattern of the thermal plume. The plume pattern is recognized as stochastic in nature and requires statistical analysis. A single realization of the Waukegan Station plume is studied with emphasis on its information content. Areas between isotherms at various depths are computed together with volumes of water in given temperature ranges above ambient; these measurements indicate the extent of the various parts of the plume together with the heat content of each part.

In a previous report on effects of thermal discharges from power plants into the Great Lakes, we stressed the need for a statistical analysis of the spatial and temporal pattern of the thermal plume. The plume pattern is recognized as stochastic in nature and requires statistical analysis. A single realization of the Waukegan Station plume is studied with emphasis on its information content. Areas between isotherms at various depths are computed together with volumes of water in given temperature ranges above ambient; these measurements indicate the extent of the various parts of the plume together with the heat content of each part.

At the present stage of reactor coolant studies it is possible to say that radiation affects the deposition behavior of corrosion products in the reactor. A quantitative relation between flux and deposition rate or amount is not available, nor is there information as to exactly which component, or combination thereof, of the radiation is most important. To determine these effects and those of other process parameters, Battelle-Northwest (BNW) is conducting an experimental program for the Knolls Atomic Power Laboratory (KAPL) to evaluate the behavior of corrosion products in pressurized, water-cooled nuclear reactor systems. This program is authorized by and is being performed under the terms and conditions of KAPL Purchase Order 7730-A (and Amendments).

Papers are presented for the following topics: (1) Nuclear Structure and Nuclear Properties - (a) Nuclear Spectroscopy and Radioactivity; (b) Nuclear Reactions and Scattering; (c) Nuclear Theory; and (d) Fission. (2) Chemical and Atomic Physics - (a) Atomic and Molecular Spectroscopy; and (b) Hyperfine Interactions. (3) Physical, Inorganic, and Analytical Chemistry - (a) X-Ray Crystallography; (b) Physical and Inorganic Chemistry; (c) Radiation Chemistry; and (d) Chemical Engineering. (4) Instrumentation and Systems Development.

SPEAKEASY is a computer language designed for scientists. This document is primarily an introduction to that language, but it also serves as a reference manual for the version currently available for IBM-360 series computers. The specific control cards needed to run jobs at the Argonne installation are described. The report contains two major sections. The first is a detailed description of the basic language. The last section of the report is an illustration of the use of the language in the form of an actual computer run.

This document contains information from the Battelle Pacific Northwest Laboratory about tritium levels in ground water at the Richland site. Several test wells were sampled and the results are reported.

A request is made for 50,000 photographs of 60 GeV/c {pi}{sup -} and 50,000 photographs of 200 GeV/c {pi}{sup -} in the Argonne 30 inch hydrogen bubble chamber at NAL. Reasons are given explaining how good physics can be done with this chamber. This experiment is a natural extension of the work of the group and will be of great usefulness in preparing for experiments with the CERN II accelerator.

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Driver fuel cladding, process tube and graphite temperatures were experimentally simulated with an electrically heated test assembly to establish the rate of radiation heat transfer from the fuel to the process tube foilowing a loss-of-coolant incident in the N-Reactor. This information is necessary as supporting data and verification for the analytical description of such an incident. The available results of the first three of a total of six experiments are presented. These results are suitable to allow DUN to evaluate, modify, and calibrate the MELT Code which is used to analytically describe the loss-of- coolant incident in N-Reactor. (auth)

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Report on the use of the QUAL-I mathematical modeling system for simulating water quality in streams and canals.

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