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Author: Publisher: ISBN: Category : Languages : en Pages : 7
Book Description
Neutron coincidence counting has played an important role in determining the mass of fissile material in safeguards and nuclear industry samples. The principle is simple; the mass of material is proportional to the spontaneous fission rate. During the fission process, multiple neutrons are emitted within a very short time frame, that is, in coincidence. The number of neutrons emitted in coincidence determines the multiplicity of the event. The challenge is to determine the spontaneous fission rate from measured neutron multiplicity distributions. The authors initial work using multiplicity to solve accuracy problems in nuclear safeguards made use of an 8-channel multiplicity electronics package. Later a 32-channel version was developed and used for multiplicity detector design and assay investigations. But this too had insufficient multiplicity capacity to allow study of the desired range of sources without drastically reducing normal detector die-away times or efficiencies thereby increasing statistical counting errors. These unacceptable solutions drove the development of the current 256-channel multiplicity electronics design. This paper describes a prototype, 256-channel neutron-multiplicity-counting circuit. It is being used with a 4-MHz shift-register-based neutron coincidence circuit. The authors developed both circuits. They mount in a double-wide nuclear instrument module.
Author: Publisher: ISBN: Category : Languages : en Pages : 7
Book Description
Neutron coincidence counting has played an important role in determining the mass of fissile material in safeguards and nuclear industry samples. The principle is simple; the mass of material is proportional to the spontaneous fission rate. During the fission process, multiple neutrons are emitted within a very short time frame, that is, in coincidence. The number of neutrons emitted in coincidence determines the multiplicity of the event. The challenge is to determine the spontaneous fission rate from measured neutron multiplicity distributions. The authors initial work using multiplicity to solve accuracy problems in nuclear safeguards made use of an 8-channel multiplicity electronics package. Later a 32-channel version was developed and used for multiplicity detector design and assay investigations. But this too had insufficient multiplicity capacity to allow study of the desired range of sources without drastically reducing normal detector die-away times or efficiencies thereby increasing statistical counting errors. These unacceptable solutions drove the development of the current 256-channel multiplicity electronics design. This paper describes a prototype, 256-channel neutron-multiplicity-counting circuit. It is being used with a 4-MHz shift-register-based neutron coincidence circuit. The authors developed both circuits. They mount in a double-wide nuclear instrument module.
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Author: Michael F. L'Annunziata
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