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ATOMIC ENERGY

Springer 非OA 2026新锐 4区2025中科院 4区已自动采集最新完整样本 10 篇平均 140.2 天

数据更新 2026-07-21 · 完整周期 10 篇 · 日期来源可逐条复核

ATOMIC ENERGY已收录10篇完整论文周期样本，平均审稿140.2 天，中位审稿132.5 天。2025中科院4区，非OA，2025发文量93。页面含论文收到日期、录用日期、PDF、DOI和出版社网页溯源入口。

查看审稿周期计算与数据来源 · 报告数据问题

140.2平均天数

132.5中位天数

4最短天数

376最长天数

10最新论文

932025发文量

最新发表论文审稿周期

审稿天数=录用日期-收到日期；保留 PDF/DOI/网页源链接

165 天

DUM-R salinometer: innovative solution for in-circuit monitoring of water salt content in the secondary circuit of reactors for nuclear vessels, floating power units, and small modular reactor plants

收到 2024-11-22 录用 2025-05-06 发表 2025-11-10

作者V. V. Petrunin; A. V. Sokolov; N. S. Serov; P. V. Triaev; A. L. Vinogradov

作者单位1. JSC “Afrikantov OKBM”, Nizhny Novgorod, Russian Federation; 2. JSC “Morinsis-Agat-KIP”, Ryazan, Russian Federation

PDF源文件 DOI 网页

4 天

Adjustment of ROM code models for calculating the population exposure dose according to international recommendations

收到 2025-06-26 录用 2025-06-30 发表 2025-11-04

作者A. A. Kiselev; A. M. Shvedov; A. A. Zaitseva

作者单位1. IBRAE RAN, Moscow, Russian Federation

PDF源文件 DOI 网页

65 天

Estimated efficiency of gas centrifuge cascade profiling for the feeding stream of stages

收到 2025-04-23 录用 2025-06-27 发表 2025-11-04

作者V. A. Palkin

作者单位1. Ural Federal University, Ekaterinburg, Russian Federation

PDF源文件 DOI 网页

56 天

Thermophysical properties of uranium-erbium fuel for VVER reactors

收到 2025-04-28 录用 2025-06-23 发表 2025-10-31

作者A. V. Fedotov; A. V. Lysikov; M. A Lutkov

作者单位1. JSC “VNIINM”, Moscow, Russian Federation

PDF源文件 DOI 网页

100 天

Maximally optimized countercurrent gas centrifuge with the offset feeding point

收到 2025-03-19 录用 2025-06-27 发表 2025-10-31

作者V. I. Tokmantsev

作者单位1. Ural Federal University, Ekaterinburg, Russian Federation

PDF源文件 DOI 网页

256 天

System of fuel cladding failure detection for the BREST-OD-300 reactor plant

收到 2024-10-14 录用 2025-06-27 发表 2025-10-31

作者M. S. Morkin; A. V. Dragunova; V. V. Perevezentsev; A. A. Gordienko; N. V. Derbeneva; D. D. Krylova

作者单位1. JSC “NIKIET”, Moscow, Russian Federation; 2. National Research University “MPEI”, Moscow, Russian Federation; 3. Bauman Moscow State Technical Unuversity, Moscow, Russian Federation

PDF源文件 DOI 网页

376 天

Concept of a small modular high-temperature gas cooled reactor with an annular fuel-particle core

收到 2024-06-06 录用 2025-06-17 发表 2025-10-31

作者S. N. Sikorin; S. G. Mandik; A. P. Akhramovich; V. P. Kolos

作者单位1. JIPNR—Sosny NAS of Belarus, Minsk, Belarus; 2. IPE NAS of Belarus, Minsk, Belarus

PDF源文件 DOI 网页

43 天

Nuclear power sources of floating power units for energy supply of the Far Eastern Federal District, Russian Federation

收到 2025-02-24 录用 2025-04-08 发表 2025-10-23

作者A. A. Bezrukov; K. B. Veshnyakov; S. M. Brykalov; V. V. Petrunin; A. V. Kurachenkov; D. V. Shchekin

作者单位1. JSC “Afrikantov OKBM”, Nizhny Novgorod, Russian Federation

PDF源文件 DOI 网页

168 天

3D model of fluid surface tension in the TwoPhase code

收到 2024-12-17 录用 2025-06-03 发表 2025-10-22

作者V. V. Chudanov; A. E. Aksenova; A. A. Makarevich; A. A. Leonov

作者单位1. IBRAE RAS, Moscow, Russian Federation; 2. National Research Nuclear University MEPhI, Moscow, Russian Federation

PDF源文件 DOI 网页

169 天

Optimal rotor radius of a separation gas centrifuge

收到 2024-07-01 录用 2024-12-17 发表 2025-10-22

作者O. E. Aleksandrov

作者单位1. Ural Federal University, Ekaterinburg, Russian Federation

PDF源文件 DOI 网页

ATOMIC ENERGY

最新发表论文审稿周期

DUM-R salinometer: innovative solution for in-circuit monitoring of water salt content in the secondary circuit of reactors for nuclear vessels, floating power units, and small modular reactor plants

Adjustment of ROM code models for calculating the population exposure dose according to international recommendations

Estimated efficiency of gas centrifuge cascade profiling for the feeding stream of stages

Thermophysical properties of uranium-erbium fuel for VVER reactors

Maximally optimized countercurrent gas centrifuge with the offset feeding point

System of fuel cladding failure detection for the BREST-OD-300 reactor plant

Concept of a small modular high-temperature gas cooled reactor with an annular fuel-particle core

Nuclear power sources of floating power units for energy supply of the Far Eastern Federal District, Russian Federation

3D model of fluid surface tension in the TwoPhase code

Optimal rotor radius of a separation gas centrifuge

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