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Application of Fast Neutron Removal Theory to the Calculation of Thermal Neutron Flux Distributions in Reactor Shields

Abstract: A calculational method is presented which may be used to determine fast and thermal neutron flux distributions at deep neutron penetrations in hydrogenous shields.

Date: 1958

Creator: Duncan, David S. & Whittum, H. O., Jr.

Item Type: Report

open access

Organic Moderated Reactor Experiment : Safeguards Summary

Abstract: This report presents a description of the Organic Moderated Reactor Experiment (OMRE), of the hazards associated with this experiment, and all of the safeguards taken to ensure the safety of the operating personnel and the population of the surrounding area.

Date: February 1, 1958

Creator: Sletten, H. L. & Blue, L. R.

Item Type: Report

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Organic Reactor Waste Gas Analyzer

The design of a waste-gas treatment system for organic moderated reactors requires a knowledge of reactor waste-gas composition, generation rate, and radioactivity. To obtain data on these variables a continuous stream analyzer was constructed to analyze the waste gas from the Organic Moderated Reactor Experiment (OMRE).

Date: October 15, 1958

Creator: Gilroy, H. M. & Edwards, R. J.

Item Type: Report

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Remote Maintenance Techniques for the Processing Refabrication Experiment

Abstract: This report outlines the general techniques developed for replacement of PRE in-cell equipment or equipment components.

Date: December 1, 1958

Creator: Stoker, Donald J.

Item Type: Report

UNT Libraries Government Documents Department - 4 Matching Results

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Application of Fast Neutron Removal Theory to the Calculation of Thermal Neutron Flux Distributions in Reactor Shields

Organic Moderated Reactor Experiment : Safeguards Summary

Organic Reactor Waste Gas Analyzer

Remote Maintenance Techniques for the Processing Refabrication Experiment