skip to main content
DOE Patents title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Fissile solution measurement apparatus

Abstract

An apparatus for determining the content of a fissile material within a solution by detecting delayed fission neutrons emitted by the fissile material after it is temporarily irradiated by a neutron source. The apparatus comprises a container holding the solution and having a portion defining a neutron source cavity centrally disposed within the container. The neutron source cavity temporarily receives the neutron source. The container has portions defining a plurality of neutron detector ports that form an annular pattern and surround the neutron source cavity. A plurality of neutron detectors count delayed fission neutrons emitted by the fissile material. Each neutron detector is located in a separate one of the neutron detector ports.

Inventors:
;
Issue Date:
OSTI Identifier:
6061566
Application Number:
ON: TI85006016
Assignee:
Dept. of Energy EDB-85-048428
DOE Contract Number:  
W-7405-ENG-36
Resource Type:
Patent
Resource Relation:
Other Information: Portions are illegible in microfiche products
Country of Publication:
United States
Language:
English
Subject:
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY; FISSILE MATERIALS; MEASURING INSTRUMENTS; DELAYED NEUTRONS; NEUTRON DETECTION; BARYONS; DETECTION; ELEMENTARY PARTICLES; FERMIONS; FISSION NEUTRONS; FISSIONABLE MATERIALS; HADRONS; MATERIALS; NEUTRONS; NUCLEONS; RADIATION DETECTION; 440101* - Radiation Instrumentation- General Detectors or Monitors & Radiometric Instruments

Citation Formats

Crane, T.W., and Collinsworth, P.R. Fissile solution measurement apparatus. United States: N. p., 1984. Web.
Crane, T.W., & Collinsworth, P.R. Fissile solution measurement apparatus. United States.
Crane, T.W., and Collinsworth, P.R. Mon . "Fissile solution measurement apparatus". United States.
@article{osti_6061566,
title = {Fissile solution measurement apparatus},
author = {Crane, T.W. and Collinsworth, P.R.},
abstractNote = {An apparatus for determining the content of a fissile material within a solution by detecting delayed fission neutrons emitted by the fissile material after it is temporarily irradiated by a neutron source. The apparatus comprises a container holding the solution and having a portion defining a neutron source cavity centrally disposed within the container. The neutron source cavity temporarily receives the neutron source. The container has portions defining a plurality of neutron detector ports that form an annular pattern and surround the neutron source cavity. A plurality of neutron detectors count delayed fission neutrons emitted by the fissile material. Each neutron detector is located in a separate one of the neutron detector ports.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1984},
month = {6}
}