Neutronic behavior evaluation of an Accelerator Driven Subcritical Reactor based on Th-U fuel cycle using computational method

S. A.H. Feghhi; Z. Gholamzadeh; C. Tenreiro; H. Kim

doi:10.1109/NSSMIC.2013.6829493

Neutronic behavior evaluation of an Accelerator Driven Subcritical Reactor based on Th-U fuel cycle using computational method

S. A.H. Feghhi, Z. Gholamzadeh, C. Tenreiro, H. Kim

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

Abstract

Accelerator Driven Subcritical Reactor (ADSR), offer advantages in terms of flexibility in using exotic fuels, allowing operation with reactivity variations and in term of intrinsic safety. Neutronic parameters of a modeled ADSR has been investigated using MCNPX 2.6 computational method. According to the obtained data, a neutron flux of ∼ 10¹⁴ (n/s.cm²) is suitable for minor actinide incineration. The system can efficiently burn minor actinide with a ∼10¹⁷ atom/s rate and produce power in the fission region with good fission per absorption ratio of 0.863.

Original language	English
Title of host publication	2013 IEEE Nuclear Science Symposium and Medical Imaging Conference, NSS/MIC 2013
Publisher	Institute of Electrical and Electronics Engineers Inc.
ISBN (Print)	9781479905348
DOIs	https://doi.org/10.1109/NSSMIC.2013.6829493
State	Published - 2013
Externally published	Yes
Event	2013 60th IEEE Nuclear Science Symposium and Medical Imaging Conference, NSS/MIC 2013 - Seoul, Korea, Republic of Duration: 27 Oct 2013 → 2 Nov 2013

Publication series

Name	IEEE Nuclear Science Symposium Conference Record
ISSN (Print)	1095-7863

Conference

Conference	2013 60th IEEE Nuclear Science Symposium and Medical Imaging Conference, NSS/MIC 2013
Country/Territory	Korea, Republic of
City	Seoul
Period	27/10/13 → 2/11/13

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10.1109/NSSMIC.2013.6829493

Cite this

Feghhi, S. A. H., Gholamzadeh, Z., Tenreiro, C., & Kim, H. (2013). Neutronic behavior evaluation of an Accelerator Driven Subcritical Reactor based on Th-U fuel cycle using computational method. In 2013 IEEE Nuclear Science Symposium and Medical Imaging Conference, NSS/MIC 2013 Article 6829493 (IEEE Nuclear Science Symposium Conference Record). Institute of Electrical and Electronics Engineers Inc.. https://doi.org/10.1109/NSSMIC.2013.6829493

Feghhi, S. A.H. ; Gholamzadeh, Z. ; Tenreiro, C. et al. / Neutronic behavior evaluation of an Accelerator Driven Subcritical Reactor based on Th-U fuel cycle using computational method. 2013 IEEE Nuclear Science Symposium and Medical Imaging Conference, NSS/MIC 2013. Institute of Electrical and Electronics Engineers Inc., 2013. (IEEE Nuclear Science Symposium Conference Record).

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title = "Neutronic behavior evaluation of an Accelerator Driven Subcritical Reactor based on Th-U fuel cycle using computational method",

abstract = "Accelerator Driven Subcritical Reactor (ADSR), offer advantages in terms of flexibility in using exotic fuels, allowing operation with reactivity variations and in term of intrinsic safety. Neutronic parameters of a modeled ADSR has been investigated using MCNPX 2.6 computational method. According to the obtained data, a neutron flux of ∼ 1014 (n/s.cm2) is suitable for minor actinide incineration. The system can efficiently burn minor actinide with a ∼1017 atom/s rate and produce power in the fission region with good fission per absorption ratio of 0.863.",

author = "Feghhi, {S. A.H.} and Z. Gholamzadeh and C. Tenreiro and H. Kim",

year = "2013",

doi = "10.1109/NSSMIC.2013.6829493",

language = "English",

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series = "IEEE Nuclear Science Symposium Conference Record",

publisher = "Institute of Electrical and Electronics Engineers Inc.",

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note = "2013 60th IEEE Nuclear Science Symposium and Medical Imaging Conference, NSS/MIC 2013 ; Conference date: 27-10-2013 Through 02-11-2013",

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Feghhi, SAH, Gholamzadeh, Z, Tenreiro, C & Kim, H 2013, Neutronic behavior evaluation of an Accelerator Driven Subcritical Reactor based on Th-U fuel cycle using computational method. in 2013 IEEE Nuclear Science Symposium and Medical Imaging Conference, NSS/MIC 2013., 6829493, IEEE Nuclear Science Symposium Conference Record, Institute of Electrical and Electronics Engineers Inc., 2013 60th IEEE Nuclear Science Symposium and Medical Imaging Conference, NSS/MIC 2013, Seoul, Korea, Republic of, 27/10/13. https://doi.org/10.1109/NSSMIC.2013.6829493

Neutronic behavior evaluation of an Accelerator Driven Subcritical Reactor based on Th-U fuel cycle using computational method. / Feghhi, S. A.H.; Gholamzadeh, Z.; Tenreiro, C. et al.
2013 IEEE Nuclear Science Symposium and Medical Imaging Conference, NSS/MIC 2013. Institute of Electrical and Electronics Engineers Inc., 2013. 6829493 (IEEE Nuclear Science Symposium Conference Record).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

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AU - Kim, H.

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AB - Accelerator Driven Subcritical Reactor (ADSR), offer advantages in terms of flexibility in using exotic fuels, allowing operation with reactivity variations and in term of intrinsic safety. Neutronic parameters of a modeled ADSR has been investigated using MCNPX 2.6 computational method. According to the obtained data, a neutron flux of ∼ 1014 (n/s.cm2) is suitable for minor actinide incineration. The system can efficiently burn minor actinide with a ∼1017 atom/s rate and produce power in the fission region with good fission per absorption ratio of 0.863.

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Feghhi SAH, Gholamzadeh Z, Tenreiro C, Kim H. Neutronic behavior evaluation of an Accelerator Driven Subcritical Reactor based on Th-U fuel cycle using computational method. In 2013 IEEE Nuclear Science Symposium and Medical Imaging Conference, NSS/MIC 2013. Institute of Electrical and Electronics Engineers Inc. 2013. 6829493. (IEEE Nuclear Science Symposium Conference Record). doi: 10.1109/NSSMIC.2013.6829493

Neutronic behavior evaluation of an Accelerator Driven Subcritical Reactor based on Th-U fuel cycle using computational method

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