Standard

Choice of the Optimum Composition of the Solution Fuel for a Homogeneous Reactor and of Termoxid Sorbent for Recovering 99Mo. / Denisov, E. I.; Betenekov, N. D.
в: Radiochemistry, Том 60, № 5, 01.09.2018, стр. 541-547.

Результаты исследований: Вклад в журнал › Статья › Рецензирование

Harvard

Denisov, EI & Betenekov, ND 2018, 'Choice of the Optimum Composition of the Solution Fuel for a Homogeneous Reactor and of Termoxid Sorbent for Recovering 99Mo', Radiochemistry, Том. 60, № 5, стр. 541-547. https://doi.org/10.1134/S1066362218050119

APA

Denisov, E. I., & Betenekov, N. D. (2018). Choice of the Optimum Composition of the Solution Fuel for a Homogeneous Reactor and of Termoxid Sorbent for Recovering 99Mo. Radiochemistry, 60(5), 541-547. https://doi.org/10.1134/S1066362218050119

Vancouver

Denisov EI, Betenekov ND. Choice of the Optimum Composition of the Solution Fuel for a Homogeneous Reactor and of Termoxid Sorbent for Recovering 99Mo. Radiochemistry. 2018 сент. 1;60(5):541-547. doi: 10.1134/S1066362218050119

Author

Denisov, E. I. ; Betenekov, N. D. / Choice of the Optimum Composition of the Solution Fuel for a Homogeneous Reactor and of Termoxid Sorbent for Recovering 99Mo. в: Radiochemistry. 2018 ; Том 60, № 5. стр. 541-547.

BibTeX

@article{9413bef63ac04b479e9e2cfb6af5d8a5,
title = "Choice of the Optimum Composition of the Solution Fuel for a Homogeneous Reactor and of Termoxid Sorbent for Recovering 99Mo",
keywords = "distribution coefficient, homogeneous solution reactor, low-enriched uranium fuel, molybdenum-99, sorption, sulfate and nitrate solutions, Termoxid T-5, Termoxid T-52, uranium",
author = "Denisov, {E. I.} and Betenekov, {N. D.}",
year = "2018",
month = sep,
day = "1",
doi = "10.1134/S1066362218050119",
language = "English",
volume = "60",
pages = "541--547",
journal = "Radiochemistry",
issn = "1066-3622",
publisher = "Pleiades Publishing",
number = "5",

}

RIS

TY - JOUR

T1 - Choice of the Optimum Composition of the Solution Fuel for a Homogeneous Reactor and of Termoxid Sorbent for Recovering 99Mo

AU - Denisov, E. I.

AU - Betenekov, N. D.

PY - 2018/9/1

Y1 - 2018/9/1

KW - distribution coefficient

KW - homogeneous solution reactor

KW - low-enriched uranium fuel

KW - molybdenum-99

KW - sorption

KW - sulfate and nitrate solutions

KW - Termoxid T-5

KW - Termoxid T-52

KW - uranium

UR - http://www.scopus.com/inward/record.url?scp=85057008308&partnerID=8YFLogxK

UR - https://gateway.webofknowledge.com/gateway/Gateway.cgi?GWVersion=2&SrcAuth=tsmetrics&SrcApp=tsm_test&DestApp=WOS_CPL&DestLinkType=FullRecord&KeyUT=000451028900011

UR - https://elibrary.ru/item.asp?id=38615063

U2 - 10.1134/S1066362218050119

DO - 10.1134/S1066362218050119

M3 - Article

AN - SCOPUS:85057008308

VL - 60

SP - 541

EP - 547

JO - Radiochemistry

JF - Radiochemistry

SN - 1066-3622

IS - 5

ER -

ID: 8334509