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
- 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}
}