DETERMINATION OF SPECIFIC NEUTRONIC REACTIVITY
Abstract
A method is given for production-line determination of the specific neutronic reactivity of such objects as individual nuclear fuel or neutron absorber elements and is notable for rapidity and apparatus simplicity. The object is incorporated in a slightly sub-critical chain fission reactive assembly having a discrete neutron source, thereby establishing a K/sub eff/ within the crucial range of 0.95 to 0.995. The range was found to afford, uniquely, flux- transient damped response in a niatter of seconds simultaneously with acceptable analytical sensitivity. The resulting neutron flux measured at a situs spaced from both object and source within the assembly serves as a calibrable indication of said reactivity.
- Inventors:
- Issue Date:
- Research Org.:
- Originating Research Org. not identified
- OSTI Identifier:
- 4166678
- Patent Number(s):
- 2936274
- Assignee:
- U.S. Atomic Energy Commission
- Patent Classifications (CPCs):
-
G - PHYSICS G21 - NUCLEAR PHYSICS G21C - NUCLEAR REACTORS
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
- NSA Number:
- NSA-14-022243
- Resource Type:
- Patent
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-60
- Country of Publication:
- United States
- Language:
- English
- Subject:
- PHYSICS; ADSORPTION; FISSION; FUELS; MEASURED VALUES; NEUTRON FLUX; NEUTRON SOURCES; NEUTRONS; PRODUCTION; QUANTITATIVE ANALYSIS; REACTIVITY; STANDARDS
Citation Formats
Dessauer, G. DETERMINATION OF SPECIFIC NEUTRONIC REACTIVITY. United States: N. p., 1960.
Web.
Dessauer, G. DETERMINATION OF SPECIFIC NEUTRONIC REACTIVITY. United States.
Dessauer, G. Tue .
"DETERMINATION OF SPECIFIC NEUTRONIC REACTIVITY". United States.
@article{osti_4166678,
title = {DETERMINATION OF SPECIFIC NEUTRONIC REACTIVITY},
author = {Dessauer, G},
abstractNote = {A method is given for production-line determination of the specific neutronic reactivity of such objects as individual nuclear fuel or neutron absorber elements and is notable for rapidity and apparatus simplicity. The object is incorporated in a slightly sub-critical chain fission reactive assembly having a discrete neutron source, thereby establishing a K/sub eff/ within the crucial range of 0.95 to 0.995. The range was found to afford, uniquely, flux- transient damped response in a niatter of seconds simultaneously with acceptable analytical sensitivity. The resulting neutron flux measured at a situs spaced from both object and source within the assembly serves as a calibrable indication of said reactivity.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1960},
month = {5}
}
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