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Criticality analysis of pyrochemical reprocessing apparatuses for mixed uranium-plutonium nitride spent nuclear fuel using the MCU-FR and MCNP program codes. / Kizub, P. A.; Blokhin, A. I.; Blokhin, P. A. et al.
In: Nuclear Engineering and Technology, Vol. 55, No. 3, 2023, p. 1097-1104.

Research output: Contribution to journal › Article › peer-review

Harvard

Kizub, PA, Blokhin, AI, Blokhin, PA, Mitenkova, EF, Mosunova, NA, Kovrov, VA, Shishkin, AV, Zaikov, YP & Rakhmanova, OR 2023, 'Criticality analysis of pyrochemical reprocessing apparatuses for mixed uranium-plutonium nitride spent nuclear fuel using the MCU-FR and MCNP program codes', Nuclear Engineering and Technology, vol. 55, no. 3, pp. 1097-1104. https://doi.org/10.1016/j.net.2022.11.020

APA

Kizub, P. A., Blokhin, A. I., Blokhin, P. A., Mitenkova, E. F., Mosunova, N. A., Kovrov, V. A., Shishkin, A. V., Zaikov, Y. P., & Rakhmanova, O. R. (2023). Criticality analysis of pyrochemical reprocessing apparatuses for mixed uranium-plutonium nitride spent nuclear fuel using the MCU-FR and MCNP program codes. Nuclear Engineering and Technology, 55(3), 1097-1104. https://doi.org/10.1016/j.net.2022.11.020

Vancouver

Kizub PA, Blokhin AI, Blokhin PA, Mitenkova EF, Mosunova NA, Kovrov VA et al. Criticality analysis of pyrochemical reprocessing apparatuses for mixed uranium-plutonium nitride spent nuclear fuel using the MCU-FR and MCNP program codes. Nuclear Engineering and Technology. 2023;55(3):1097-1104. doi: 10.1016/j.net.2022.11.020

Author

Kizub, P. A. ; Blokhin, A. I. ; Blokhin, P. A. et al. / Criticality analysis of pyrochemical reprocessing apparatuses for mixed uranium-plutonium nitride spent nuclear fuel using the MCU-FR and MCNP program codes. In: Nuclear Engineering and Technology. 2023 ; Vol. 55, No. 3. pp. 1097-1104.

BibTeX

@article{837999e826284f139f91ee7a79efb7d3,
title = "Criticality analysis of pyrochemical reprocessing apparatuses for mixed uranium-plutonium nitride spent nuclear fuel using the MCU-FR and MCNP program codes",
abstract = "A preliminary criticality analysis for novel pyrochemical apparatuses for the reprocessing of mixed uranium-plutonium nitride spent nuclear fuel from the BREST-OD-300 reactor was performed. High-temperature processing apparatuses, “metallization” electrolyzer, refinery remelting apparatus, refining electrolyzer, and “soft” chlorination apparatus are considered in this work. Computational models of apparatuses for two neutron radiation transport codes (MCU-FR and MCNP) were developed and calculations for criticality were completed using the Monte Carlo method. The criticality analysis was performed for different loads of fissile material into the apparatuses including overloading conditions. Various emergency situations were considered, in particular, those associated with water ingress into the chamber of the refinery remelting apparatus. It was revealed that for all the considered computational models nuclear safety rules are satisfied. {\textcopyright} 2022 Korean Nuclear Society",
author = "Kizub, {P. A.} and Blokhin, {A. I.} and Blokhin, {P. A.} and Mitenkova, {E. F.} and Mosunova, {N. A.} and Kovrov, {V. A.} and A.v. Shishkin and Yu.p. Zaikov and O.r. Rakhmanova",
year = "2023",
doi = "10.1016/j.net.2022.11.020",
language = "English",
volume = "55",
pages = "1097--1104",
journal = "Nuclear Engineering and Technology",
issn = "1738-5733",
publisher = "Elsevier",
number = "3",

}

RIS

TY - JOUR

T1 - Criticality analysis of pyrochemical reprocessing apparatuses for mixed uranium-plutonium nitride spent nuclear fuel using the MCU-FR and MCNP program codes

AU - Kizub, P. A.

AU - Blokhin, A. I.

AU - Blokhin, P. A.

AU - Mitenkova, E. F.

AU - Mosunova, N. A.

AU - Kovrov, V. A.

AU - Shishkin, A.v.

AU - Zaikov, Yu.p.

AU - Rakhmanova, O.r.

PY - 2023

Y1 - 2023

N2 - A preliminary criticality analysis for novel pyrochemical apparatuses for the reprocessing of mixed uranium-plutonium nitride spent nuclear fuel from the BREST-OD-300 reactor was performed. High-temperature processing apparatuses, “metallization” electrolyzer, refinery remelting apparatus, refining electrolyzer, and “soft” chlorination apparatus are considered in this work. Computational models of apparatuses for two neutron radiation transport codes (MCU-FR and MCNP) were developed and calculations for criticality were completed using the Monte Carlo method. The criticality analysis was performed for different loads of fissile material into the apparatuses including overloading conditions. Various emergency situations were considered, in particular, those associated with water ingress into the chamber of the refinery remelting apparatus. It was revealed that for all the considered computational models nuclear safety rules are satisfied. © 2022 Korean Nuclear Society

AB - A preliminary criticality analysis for novel pyrochemical apparatuses for the reprocessing of mixed uranium-plutonium nitride spent nuclear fuel from the BREST-OD-300 reactor was performed. High-temperature processing apparatuses, “metallization” electrolyzer, refinery remelting apparatus, refining electrolyzer, and “soft” chlorination apparatus are considered in this work. Computational models of apparatuses for two neutron radiation transport codes (MCU-FR and MCNP) were developed and calculations for criticality were completed using the Monte Carlo method. The criticality analysis was performed for different loads of fissile material into the apparatuses including overloading conditions. Various emergency situations were considered, in particular, those associated with water ingress into the chamber of the refinery remelting apparatus. It was revealed that for all the considered computational models nuclear safety rules are satisfied. © 2022 Korean Nuclear Society

UR - http://www.scopus.com/inward/record.url?partnerID=8YFLogxK&scp=85144989584

UR - https://gateway.webofknowledge.com/gateway/Gateway.cgi?GWVersion=2&SrcAuth=tsmetrics&SrcApp=tsm_test&DestApp=WOS_CPL&DestLinkType=FullRecord&KeyUT=000961804800001

U2 - 10.1016/j.net.2022.11.020

DO - 10.1016/j.net.2022.11.020

M3 - Article

VL - 55

SP - 1097

EP - 1104

JO - Nuclear Engineering and Technology

JF - Nuclear Engineering and Technology

SN - 1738-5733

IS - 3

ER -

ID: 36194957