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Title: METHOD OF TESTING THERMAL NEUTRON FISSIONABLE MATERIAL FOR PURITY

Abstract

A process is given for determining the neutronic purity of fissionable material by the so-called shotgun test. The effect of a standard neutron absorber of known characteristics and amounts on a neutronic field also of known characteristics is measured and compared with the effect which the impurities derived from a known quantity of fissionable material has on the same neutronic field. The two readings are then made the basis of calculation from which the amount of impurities can be computed.

Inventors:
;
Issue Date:
OSTI Identifier:
4103931
Patent Number(s):
2969307
Assignee:
U.S. Atomic Energy Commission
Patent Classifications (CPCs):
Y - NEW / CROSS SECTIONAL TECHNOLOGIES Y02 - TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE Y02E - REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
G - PHYSICS G01 - MEASURING G01N - INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
NSA Number:
NSA-15-007310
Resource Type:
Patent
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-61
Country of Publication:
United States
Language:
English
Subject:
CHEMISTRY; ABSORPTION; FISSIONABLE MATERIALS; IMPURITIES; MEASURED VALUES; NEUTRONS; STANDARDS; TESTING; THERMAL NEUTRONS

Citation Formats

Fermi, E, and Anderson, H L. METHOD OF TESTING THERMAL NEUTRON FISSIONABLE MATERIAL FOR PURITY. United States: N. p., 1961. Web.
Fermi, E, & Anderson, H L. METHOD OF TESTING THERMAL NEUTRON FISSIONABLE MATERIAL FOR PURITY. United States.
Fermi, E, and Anderson, H L. Tue . "METHOD OF TESTING THERMAL NEUTRON FISSIONABLE MATERIAL FOR PURITY". United States.
@article{osti_4103931,
title = {METHOD OF TESTING THERMAL NEUTRON FISSIONABLE MATERIAL FOR PURITY},
author = {Fermi, E and Anderson, H L},
abstractNote = {A process is given for determining the neutronic purity of fissionable material by the so-called shotgun test. The effect of a standard neutron absorber of known characteristics and amounts on a neutronic field also of known characteristics is measured and compared with the effect which the impurities derived from a known quantity of fissionable material has on the same neutronic field. The two readings are then made the basis of calculation from which the amount of impurities can be computed.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1961},
month = {1}
}