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Title: 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:
 [1]
  1. 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 = {1976},
month = {8}
}

Patent:

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