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ESTIMATION OF THE HEATING OF THERMAL NEUTRONS IN THE FUEL ELEMENTS OF HETEROGENEOUS REACTORS

Achim Müller

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Abstract

In heterogeneous reactors the thermal neutron spectrum during absorption in fuel elements is different from the spectrum in the moderator since the neutrons coming from the moderator were heated up'' by scattering collisions in the hot fuel elements in the core. A formula was derived which permits an estimation of this heating when the average energy transfer to a thermal neutron in scattering by liquid and crystalline substances is sufficientiy well known. (tr-auth)

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What this paper is about

In heterogeneous reactors the thermal neutron spectrum during absorption in fuel elements is different from the spectrum in the moderator since the neutrons coming from the moderator were heated up'' by scattering collisions in the hot fuel elements in the core. A formula was derived which permits an estimation of this heating when the average energy transfer to a thermal neutron in scattering by liquid and crystalline substances is sufficientiy well known. (tr-auth)

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Available abstract

In heterogeneous reactors the thermal neutron spectrum during absorption in fuel elements is different from the spectrum in the moderator since the neutrons coming from the moderator were heated up'' by scattering collisions in the hot fuel elements in the core. A formula was derived which permits an estimation of this heating when the average energy transfer to a thermal neutron in scattering by liquid and crystalline substances is sufficientiy well known. (tr-auth)

Key concepts: Neutron temperature, Neutron moderator, Neutron, Neutron poison, Nuclear engineering, Thermal, Nuclear reactor core, Neutron cross section

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ESTIMATION OF THE HEATING OF THERMAL NEUTRONS IN THE FUEL ELEMENTS OF HETEROGENEOUS REACTORS — Research Paper | ScholarLens