Neutronic reactor
Abstract
A safety rod for a nuclear reactor has an inner end portion having a gamma absorption coefficient and neutron capture cross section approximately equal to those of the adjacent shield, a central portion containing materials of high neutron capture cross section and an outer end portion having a gamma absorption coefficient at least equal to that of the adjacent shield.
- Inventors:
-
- West Chester, PA
- Issue Date:
- Research Org.:
- Knolls Atomic Power Lab
- OSTI Identifier:
- 862616
- Patent Number(s):
- 3975233
- Assignee:
- United States of America as represented by United States Energy (Washington, DC)
- 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
- DOE Contract Number:
- W-31-109-ENG-52
- Resource Type:
- Patent
- Country of Publication:
- United States
- Language:
- English
- Subject:
- neutronic; reactor; safety; rod; nuclear; inner; portion; gamma; absorption; coefficient; neutron; capture; section; approximately; equal; adjacent; shield; central; containing; materials; outer; portion containing; approximately equal; neutronic reactor; safety rod; nuclear reactor; neutron capture; central portion; absorption coefficient; containing material; containing materials; /376/976/
Citation Formats
Wende, Charles W. J. Neutronic reactor. United States: N. p., 1976.
Web.
Wende, Charles W. J. Neutronic reactor. United States.
Wende, Charles W. J. Tue .
"Neutronic reactor". United States. https://www.osti.gov/servlets/purl/862616.
@article{osti_862616,
title = {Neutronic reactor},
author = {Wende, Charles W. J.},
abstractNote = {A safety rod for a nuclear reactor has an inner end portion having a gamma absorption coefficient and neutron capture cross section approximately equal to those of the adjacent shield, a central portion containing materials of high neutron capture cross section and an outer end portion having a gamma absorption coefficient at least equal to that of the adjacent shield.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Aug 17 00:00:00 EDT 1976},
month = {Tue Aug 17 00:00:00 EDT 1976}
}
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