Neutron shielding evaluation for a small fuel transport case

M. Coeck; F. Vermeersch; F. Vanhavere

doi:10.1016/S0168-9002(01)01484-X

Neutron shielding evaluation for a small fuel transport case

Research output › peer-review

Abstract

We investigated the effectiveness of a small neutron shield configuration for the transportation of fresh MOX fuel rods in an experimental facility, this in order to reduce the dose received by the personnel. Monte Carlo simulations using the Tripoli and MCNP4B code were applied. Different configurations were studied, starting from the bare fuel rod positioned on an iron plate up to a fuel rod covered by a box-shaped shield made of different materials such as polyethylene, polyethylene with boron and polyethylene with a cadmium layer. We compared the neutron spectra for the different cases and calculated the corresponding ambient equivalent dose rate H*(10).

Original language	English
Pages (from-to)	273-276
Number of pages	4
Journal	Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment
Volume	476
Issue number	1-2
DOIs	https://doi.org/10.1016/S0168-9002(01)01484-X
State	Published - 1 Jan 2002
Event	Workshop on Neutron Field Spectrometry in Science (NEUSPEC 2000) - Pisa Duration: 4 Jun 2000 → 8 Jun 2000

ASJC Scopus subject areas

Nuclear and High Energy Physics
Instrumentation

Access to Document

10.1016/S0168-9002(01)01484-X

Cite this

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title = "Neutron shielding evaluation for a small fuel transport case",

abstract = "We investigated the effectiveness of a small neutron shield configuration for the transportation of fresh MOX fuel rods in an experimental facility, this in order to reduce the dose received by the personnel. Monte Carlo simulations using the Tripoli and MCNP4B code were applied. Different configurations were studied, starting from the bare fuel rod positioned on an iron plate up to a fuel rod covered by a box-shaped shield made of different materials such as polyethylene, polyethylene with boron and polyethylene with a cadmium layer. We compared the neutron spectra for the different cases and calculated the corresponding ambient equivalent dose rate H*(10).",

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T1 - Neutron shielding evaluation for a small fuel transport case

AU - Coeck, M.

AU - Vermeersch, F.

AU - Vanhavere, F.

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N2 - We investigated the effectiveness of a small neutron shield configuration for the transportation of fresh MOX fuel rods in an experimental facility, this in order to reduce the dose received by the personnel. Monte Carlo simulations using the Tripoli and MCNP4B code were applied. Different configurations were studied, starting from the bare fuel rod positioned on an iron plate up to a fuel rod covered by a box-shaped shield made of different materials such as polyethylene, polyethylene with boron and polyethylene with a cadmium layer. We compared the neutron spectra for the different cases and calculated the corresponding ambient equivalent dose rate H*(10).

AB - We investigated the effectiveness of a small neutron shield configuration for the transportation of fresh MOX fuel rods in an experimental facility, this in order to reduce the dose received by the personnel. Monte Carlo simulations using the Tripoli and MCNP4B code were applied. Different configurations were studied, starting from the bare fuel rod positioned on an iron plate up to a fuel rod covered by a box-shaped shield made of different materials such as polyethylene, polyethylene with boron and polyethylene with a cadmium layer. We compared the neutron spectra for the different cases and calculated the corresponding ambient equivalent dose rate H*(10).

KW - Monte Carlo calculations

KW - Neutron shielding

KW - Radiation protection

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JO - Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment

JF - Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment

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