Systematic Evaluation of Neutron Shielding Effects for Materials

Ueki, Koichiro; Ohashi, Atsuto; Nariyama, Nobuteru; Nagayama, S.; Fujita, T.; Hattori, Kiyoshi; Anayama, Yoshimasa

doi:10.13182/nse124-455

Cited by 24 publications

(27 citation statements)

References 6 publications

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“…To illustrate the diagnosis tool previously detailed, examples of coupled neutron-photon configurations were selected from a series of shielding benchmark experiments [7] and geometry modifications were made for one of them: the purpose was here to magnify different contributing effects of neutron and photon physics. The initial benchmark case [7,8] is a neutron-only problem that involves a neutron source placed in a paraffin collimator, polyethylene and stainless steel slabs arranged with several stainless steel slabs close to the source followed by several polyethylene slabs close to the detector, the whole system being surrounded by air.…”

Section: Application For Coupled Simulationsmentioning

confidence: 99%

“…The initial benchmark case [7,8] is a neutron-only problem that involves a neutron source placed in a paraffin collimator, polyethylene and stainless steel slabs arranged with several stainless steel slabs close to the source followed by several polyethylene slabs close to the detector, the whole system being surrounded by air. We modified the slabs arrangement as described in the following and shown in Figure 1.…”

Section: Application For Coupled Simulationsmentioning

confidence: 99%

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Variance reduction adjustment in Monte Carlo TRIPOLI-4® neutron gamma coupled calculations

Petit

Lee²,

Diop³

2014

Progress in Nuclear Science and Technology

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This paper presents a diagnosis tool for the users of the TRIPOLI-4 Monte Carlo transport code. The aim is to facilitate the adjustment of the variance reduction scheme when dealing with coupled neutron-photon simulations. Up to now, neutron and photon importance functions have been generated independently by TRIPOLI-4 when transport biasing for both particles was necessary, leading to further adjustments by the user after running a first coupled simulation. The idea is here to combine in a fast step the TRIPOLI-4 photon importance map on the one hand, and the photon production data used by the simulation on the other hand, so as to provide at once a better knowledge of important points of neutron phase space with respect to photon tallies. The highest neutron importance mesh cells are then derived and optionally displayed on geometry graphs. The user's intervention consists then in different possible options defining the neutron variance reduction scheme of the TRIPOLI-4 coupled simulation, in the light of the previous diagnosis results. Finally, coupled neutron-photon simulations involving polyethylene and stainless steel slabs are investigated: an example of use of this diagnosis tool is provided and figures of merit related to photon tallies are then compared.

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Section: Application For Coupled Simulationsmentioning

confidence: 99%

Section: Application For Coupled Simulationsmentioning

confidence: 99%

Variance reduction adjustment in Monte Carlo TRIPOLI-4® neutron gamma coupled calculations

Petit

Lee²,

Diop³

2014

Progress in Nuclear Science and Technology

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“…The size of each slab collimator was 80 Â 80 Â 5 cm thickness with a duct of 10 cm. The material of the collimator slab is NS-4-FR, 1) a kind of epoxy-based resin that contains boron to reduce the effect of secondary gamma rays. The neutron penetration was measured using a neutron rem counter.…”

Section: Neutron Penetration Experimentsmentioning

confidence: 99%

Development of Flexible Neutron-Shielding Resin as an Additional Shielding Material

Sukegawa

Anayama²,

Ohnishi

et al. 2011

Journal of Nuclear Science and Technology

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A soft-type neutron-shielding resin has been developed by improving an existing hard-type neutronshielding material using the epoxy-based resin as an additional shielding material. A flexible heat-resistant neutron-shielding material has been developed, which consists of a new polymer-based resin with boron. The neutron shielding performance of the developed flexible heat-resistant resin with the 252 Cf neutron source is almost the same as that of polyethylene. The outgases of H, H 2 , NH 4 , H 2 O, CO, O 2 , C 4 H 10 , and CO 2 from the developed resin have been measured at high temperature (up to 250 C) by thermal desorption spectroscopy methods. The soft-type resin and the newly developed heat-resistant resin will be applied to prevent the effects of neutron streaming and to control the movement of a vibrated pipe as the seal material around the plumbing in the future fast reactor and innovative fission reactor.

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“…At accelerator facilities like SLAC, it is well known to put heavy metal closer to the high-energy neutron source. It has also been shown (6) that, for 252 Cf neutrons, putting stainless steel in front of polyethylene is better in reducing the total dose equivalent. Therefore, it seems that, for 14-MeV neutrons, the iron shield should be positioned first, followed by BPE.…”

Section: Iron-bpe Shieldmentioning

confidence: 99%

Monte Carlo Calculations Using MCNP4B for an Optimal Shielding Design for a 14 MeV Neutron Source

Liu¹,

Ng²

1999

Radiation Protection Dosimetry

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-The shielding for 14-MeV neutrons from a D-T generator at SLAC needs to be optimized in terms of shield thickness and cost. Shielding calculations were made using the MCNP4B Monte Carlo code and the ENDF/B-VI cross section set. A few materials were studied: iron, borated polyethylene, three types of normal and heavy concrete, and mixtures of iron and borated polyethylene. The effects of shielding geometry (sphere, cube, and the proposed geometry) were also examined. The transmission results of ambient dose equivalents, as well as the attenuation lengths and the average energies, for neutrons and gammas outside the shielding are presented.3

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Systematic Evaluation of Neutron Shielding Effects for Materials

Cited by 24 publications

References 6 publications

Variance reduction adjustment in Monte Carlo TRIPOLI-4® neutron gamma coupled calculations

Variance reduction adjustment in Monte Carlo TRIPOLI-4® neutron gamma coupled calculations

Development of Flexible Neutron-Shielding Resin as an Additional Shielding Material

Monte Carlo Calculations Using MCNP4B for an Optimal Shielding Design for a 14 MeV Neutron Source

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