Radiation source terms of MYRRHA reactor components and equipment

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Radiation source terms of MYRRHA reactor components and equipment. / Çelik, Yurdunaz; Stankovskiy, Alexey; Engelen, Jeroen; Van den Eynde, Gert; Sarer, Basar; Sahin, Sümer.

INTERNATIONAL JOURNAL OF HYDROGEN ENERGY: 17th International Conference on Emerging Nuclear Energy Systems (ICENES). Vol. 41/17 2016. p. 7213-7220 (International Journal of Hydrogen Energy).

Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

Harvard

Çelik, Y, Stankovskiy, A, Engelen, J, Van den Eynde, G, Sarer, B & Sahin, S 2016, Radiation source terms of MYRRHA reactor components and equipment. in INTERNATIONAL JOURNAL OF HYDROGEN ENERGY: 17th International Conference on Emerging Nuclear Energy Systems (ICENES). vol. 41/17, International Journal of Hydrogen Energy, pp. 7213-7220, ICENES 2015 - 17th International Conference on Emerging Nuclear Energy Systems, Istanbul, Turkey, 2015-10-04. https://doi.org/10.1016/j.ijhydene.2016.01.119

APA

Çelik, Y., Stankovskiy, A., Engelen, J., Van den Eynde, G., Sarer, B., & Sahin, S. (2016). Radiation source terms of MYRRHA reactor components and equipment. In INTERNATIONAL JOURNAL OF HYDROGEN ENERGY: 17th International Conference on Emerging Nuclear Energy Systems (ICENES) (Vol. 41/17, pp. 7213-7220). (International Journal of Hydrogen Energy). https://doi.org/10.1016/j.ijhydene.2016.01.119

Vancouver

Çelik Y, Stankovskiy A, Engelen J, Van den Eynde G, Sarer B, Sahin S. Radiation source terms of MYRRHA reactor components and equipment. In INTERNATIONAL JOURNAL OF HYDROGEN ENERGY: 17th International Conference on Emerging Nuclear Energy Systems (ICENES). Vol. 41/17. 2016. p. 7213-7220. (International Journal of Hydrogen Energy). https://doi.org/10.1016/j.ijhydene.2016.01.119

Author

Çelik, Yurdunaz ; Stankovskiy, Alexey ; Engelen, Jeroen ; Van den Eynde, Gert ; Sarer, Basar ; Sahin, Sümer. / Radiation source terms of MYRRHA reactor components and equipment. INTERNATIONAL JOURNAL OF HYDROGEN ENERGY: 17th International Conference on Emerging Nuclear Energy Systems (ICENES). Vol. 41/17 2016. pp. 7213-7220 (International Journal of Hydrogen Energy).

Bibtex - Download

@inproceedings{a97a3f62ed4f41e2adbb1c38927e5f88,
title = "Radiation source terms of MYRRHA reactor components and equipment",
abstract = "In-vessel structural components of nuclear reactors are subject to prompt and residual neutron and photon activation. The MYRRHA fast spectrum facility, when operated in subcritical mode, suffers additional activation due to a wide range of energetic particles produced in the interactions of 600 MeV-primary protons with matter. The purpose of this work was to assess the source term (activation, heating and induced radiation level) of excore equipment and components located inside the reactor vessel. Numerous stainless steel samples uniformly distributed inside the vessel have been used to simulate the activation of equipment in order to take into account the perturbation of the neutron spectrum caused by structural materials of components and equipment. The calculated quantities were prompt and residual activation, heating, radiation dose and radiation damage. The calculations were carried out with the ALEPH2 depletion code which invokes the MCNPX code for radiation transport.",
keywords = "MYRRHA, reactor, activation, MCNPX, ALEPH2",
author = "Yurdunaz {\c C}elik and Alexey Stankovskiy and Jeroen Engelen and {Van den Eynde}, Gert and Basar Sarer and S{\"u}mer Sahin",
note = "Score=10; ICENES 2015 - 17th International Conference on Emerging Nuclear Energy Systems ; Conference date: 04-10-2015 Through 08-10-2015",
year = "2016",
month = feb,
day = "23",
doi = "10.1016/j.ijhydene.2016.01.119",
language = "English",
volume = "41/17",
series = "International Journal of Hydrogen Energy",
publisher = "Elsevier",
pages = "7213--7220",
booktitle = "INTERNATIONAL JOURNAL OF HYDROGEN ENERGY",

}

RIS - Download

TY - GEN

T1 - Radiation source terms of MYRRHA reactor components and equipment

AU - Çelik, Yurdunaz

AU - Stankovskiy, Alexey

AU - Engelen, Jeroen

AU - Van den Eynde, Gert

AU - Sarer, Basar

AU - Sahin, Sümer

N1 - Score=10

PY - 2016/2/23

Y1 - 2016/2/23

N2 - In-vessel structural components of nuclear reactors are subject to prompt and residual neutron and photon activation. The MYRRHA fast spectrum facility, when operated in subcritical mode, suffers additional activation due to a wide range of energetic particles produced in the interactions of 600 MeV-primary protons with matter. The purpose of this work was to assess the source term (activation, heating and induced radiation level) of excore equipment and components located inside the reactor vessel. Numerous stainless steel samples uniformly distributed inside the vessel have been used to simulate the activation of equipment in order to take into account the perturbation of the neutron spectrum caused by structural materials of components and equipment. The calculated quantities were prompt and residual activation, heating, radiation dose and radiation damage. The calculations were carried out with the ALEPH2 depletion code which invokes the MCNPX code for radiation transport.

AB - In-vessel structural components of nuclear reactors are subject to prompt and residual neutron and photon activation. The MYRRHA fast spectrum facility, when operated in subcritical mode, suffers additional activation due to a wide range of energetic particles produced in the interactions of 600 MeV-primary protons with matter. The purpose of this work was to assess the source term (activation, heating and induced radiation level) of excore equipment and components located inside the reactor vessel. Numerous stainless steel samples uniformly distributed inside the vessel have been used to simulate the activation of equipment in order to take into account the perturbation of the neutron spectrum caused by structural materials of components and equipment. The calculated quantities were prompt and residual activation, heating, radiation dose and radiation damage. The calculations were carried out with the ALEPH2 depletion code which invokes the MCNPX code for radiation transport.

KW - MYRRHA

KW - reactor

KW - activation

KW - MCNPX

KW - ALEPH2

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/31584797

U2 - 10.1016/j.ijhydene.2016.01.119

DO - 10.1016/j.ijhydene.2016.01.119

M3 - In-proceedings paper

VL - 41/17

T3 - International Journal of Hydrogen Energy

SP - 7213

EP - 7220

BT - INTERNATIONAL JOURNAL OF HYDROGEN ENERGY

T2 - ICENES 2015 - 17th International Conference on Emerging Nuclear Energy Systems

Y2 - 4 October 2015 through 8 October 2015

ER -

ID: 6771173