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Title: Neutronic Reactor Design to Reduce Neutron Loss

Abstract

A nuclear reactor construction is described in which an unmoderated layer of the fissionable material is inserted between the moderated portion of the reactor core and the core container steel wall. The wall is surrounded by successive layers of pure fertile material and moderator containing fertile material. The unmoderated layer of the fissionable material will insure that a greater portion of fast neutrons will pass through the steel wall than would thermal neutrons. Since the steel has a smaller capture cross section for the fast neutrons, greater nunnbers of neutrons will pass into the blanket, thereby increasing the over-all efficiency of the reactor. (AEC)

Inventors:
Issue Date:
OSTI Identifier:
4013551
Patent Number(s):
2982709
Assignee:
U.S. Atomic Energy Commission
NSA Number:
NSA-15-025665
Resource Type:
Patent
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-61
Country of Publication:
United States
Language:
English
Subject:
REACTOR TECHNOLOGY; BLANKETS; CAPTURE; CONFIGURATION; CROSS SECTIONS; EFFICIENCY; FAST NEUTRONS; FERTILE MATERIALS; MODERATORS; PATENT; PRESSURE VESSELS; REACTOR CORE; THERMAL NEUTRONS; ZONES; ABSORPTION; BREEDING; FUELS; LEAKS; NEUTRONS; PLANNING; REACTORS; STEELS; VESSELS

Citation Formats

Miles, F. T. Neutronic Reactor Design to Reduce Neutron Loss. United States: N. p., 1961. Web.
Miles, F. T. Neutronic Reactor Design to Reduce Neutron Loss. United States.
Miles, F. T. Mon . "Neutronic Reactor Design to Reduce Neutron Loss". United States. https://www.osti.gov/servlets/purl/4013551.
@article{osti_4013551,
title = {Neutronic Reactor Design to Reduce Neutron Loss},
author = {Miles, F. T.},
abstractNote = {A nuclear reactor construction is described in which an unmoderated layer of the fissionable material is inserted between the moderated portion of the reactor core and the core container steel wall. The wall is surrounded by successive layers of pure fertile material and moderator containing fertile material. The unmoderated layer of the fissionable material will insure that a greater portion of fast neutrons will pass through the steel wall than would thermal neutrons. Since the steel has a smaller capture cross section for the fast neutrons, greater nunnbers of neutrons will pass into the blanket, thereby increasing the over-all efficiency of the reactor. (AEC)},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1961},
month = {5}
}