Criticality analysis of pyrochemical reprocessing apparatuses for mixed uranium-plutonium nitride spent nuclear fuel using the MCU-FR and MCNP program codes-Reference-Cited by-同舟云学术

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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

Published:2023-03 Issue:3 Volume:55 Page:1097-1104
ISSN:1738-5733
Container-title:Nuclear Engineering and Technology
language:en
Short-container-title:Nuclear Engineering and Technology

Author:

Kizub P.A.,Blokhin A.I.,Blokhin P.A.,Mitenkova E.F.,Mosunova N.A.^ORCID,Kovrov V.A.^ORCID,Shishkin A.V.,Zaikov Yu.P.,Rakhmanova O.R.^ORCID

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference25 articles.

1. Nuclear Technology Review 2020,2020

2. International developments in electrorefining technologies for pyrochemical processing of spent nuclear fuels;Lewin,2015

3. The electrical conductivity of model melts based on LiCl-KCl, used for the processing of spent nuclear fuel;Salyulev;J. Electrochim. Acta,2017

4. Interaction between UN and CdCl2 in molten LiCl-KCl eutectic. I. Experiment at 773 K;Zhitkov;J. Nucl. Eng. Technol.,2020

5. Electrical conductivity of (LiCl−KCl)eut.−SrCl2 molten mixtures;Salyulev;J. Chem. Eng. Data,2021

Cited by 1 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Efficiency of Electrochemical Methods of Purification and Control over the Oxide Concentration in Halide Melts: PbCl2;Processes;2023-02-19

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