WorldCat Identities

O'Shea, D. M.

Overview
Works: 6 works in 10 publications in 1 language and 49 library holdings
Roles: Author
Classifications: QC783.4,
Publication Timeline
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Most widely held works by D. M O'Shea
The reactor kinetics of the Transient Reactor Test Facility (TREAT)( )

2 editions published in 1960 in English and held by 24 WorldCat member libraries worldwide

The Transient Reactor Test Facility (TREAT) is a pulsed, graphite-moderated reactor constructed by Argonne National Laboratory at the National Reactor Testing Station especially to generate safely very large integrated bursts of thermal neutrons over a large sample volume. It was designed to enable a rapid heating leading to destruction without harm to the reactor itself. A near maximization of available total greatest possible flexibility in experimental techniques, such as the use of natural or low-enrichment fuel pins. The integrated flux is more than twice that required to melt a natural enrichment EBR-II fuel element
Mach 1, a one-dimensional diffusion theory package by D. A Meneley( )

2 editions published in 1966 in English and held by 11 WorldCat member libraries worldwide

Some calculations pertaining to fast reactor safety by D. M O̕ Shea( Book )

1 edition published in 1962 in English and held by 8 WorldCat member libraries worldwide

One topic deals with the success obtained in analyzing complicated meltdown configurations using two-dimensional, two-group diffusion theory. Another topic deals with the dependence of energy yield in a fast reactor explosion on the shape of the power distribution in the core
MC2, a code to calculate multigroup cross sections by B. J Toppel( Book )

2 editions published in 1967 in English and held by 3 WorldCat member libraries worldwide

MC²: A code to calculate multigroup cross sections by B. J Toppel( Book )

2 editions published in 1967 in English and held by 2 WorldCat member libraries worldwide

The MC² code attempts to provide a total system compatibility in the sense of generating a complete cross-section set, using an Evaluated Nuclear Data File (ENDF), suitable for direct use by neutronics codes without performing ancillary calculations
MACH1: a one-dimensional diffusion-theory package by D. A Meneley( Book )

1 edition published in 1966 in English and held by 1 WorldCat member library worldwide

The MACH1 diffusion-theory package embodies the basic features of the AIM-6 one-dimensional diffusion code, the DEL perturbation code, and the 1188/RE delayed-neutron code, as well as several additional ancillary additions of the MAIM-6 code. The purpose of these modifications and additions was to allow single-step calculation of many reactor parameters of interest, with minimum required input data and at reasonably high speed
 
Audience Level
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Audience Level
1
  Kids General Special  
Audience level: 0.77 (from 0.76 for The reacto ... to 0.87 for MC2, a cod ...)

Languages
English (10)