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Title: NUCLEAR REACTOR

Abstract

This patent relates to nuclear reactors of the type which use a liquid fuel, such as a solution of uranyl sulfate in ordinary water which acts as the moderator. The reactor is comprised of a spherical vessel having a diameter of about 12 inches substantially surrounded by a reflector of beryllium oxide. Conventionnl control rods and safety rods are operated in slots in the reflector outside the vessel to control the operation of the reactor. An additional means for increasing the safety factor of the reactor by raising the ratio of delayed neutrons to prompt neutrons, is provided and consists of a soluble sulfate salt of beryllium dissolved in the liquid fuel in the proper proportion to obtain the result desired.

Inventors:
;
Publication Date:
Research Org.:
Originating Research Org. not identified
OSTI Identifier:
4329372
Patent Number(s):
US 2820753
Assignee:
U.S. Atomic Energy Commission DTIE; NSA-12-007043
Resource Type:
Patent
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-58
Country of Publication:
United States
Language:
English
Subject:
PATENTS; BERYLLIUM OXIDES; CONTROL SYSTEMS; FUEL ELEMENTS; LIQUIDS; NEUTRON DETECTION; PATENT; REACTORS; REFLECTORS; RODS; SOLUTIONS; SULFATES; URANYL COMPOUNDS; VESSELS; WATER MODERATOR

Citation Formats

Miller, H.I., and Smith, R.C.. NUCLEAR REACTOR. United States: N. p., 1958. Web.
Miller, H.I., & Smith, R.C.. NUCLEAR REACTOR. United States.
Miller, H.I., and Smith, R.C.. 1958. "NUCLEAR REACTOR". United States. doi:.
@article{osti_4329372,
title = {NUCLEAR REACTOR},
author = {Miller, H.I. and Smith, R.C.},
abstractNote = {This patent relates to nuclear reactors of the type which use a liquid fuel, such as a solution of uranyl sulfate in ordinary water which acts as the moderator. The reactor is comprised of a spherical vessel having a diameter of about 12 inches substantially surrounded by a reflector of beryllium oxide. Conventionnl control rods and safety rods are operated in slots in the reflector outside the vessel to control the operation of the reactor. An additional means for increasing the safety factor of the reactor by raising the ratio of delayed neutrons to prompt neutrons, is provided and consists of a soluble sulfate salt of beryllium dissolved in the liquid fuel in the proper proportion to obtain the result desired.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = 1958,
month = 1
}