Works about NUCLEAR reactor cores

Results: 449

Optimized Method for Solving Boltzmann Transport Equations in Subgroup Method of Resonance Treatment.

Published in:

Mathematics (2227-7390), 2025, v. 13, n. 9, p. 1384, doi. 10.3390/math13091384

By:

Li, Song;
Liu, Lei;
Zhang, Yongfa;
Zhang, Qian;
Cai, Qi

Publication type:

Article

Radiation Shielding Optimization of ADS-SAMOP Reactor Test Facility.

Published in:

Iraqi Journal of Science, 2025, v. 66, n. 3, p. 1071, doi. 10.24996/ijs.2025.66.3.8

By:

Syarip, Syarip;
Luthfi, Wahid;
Sihana

Publication type:

Article

Mathematical modelling of nonlinear vibration and fretting wear of the nuclear fuel rods.

Published in:

Archive of Applied Mechanics, 2016, v. 86, n. 4, p. 657, doi. 10.1007/s00419-015-1053-0

By:

Zeman, Vladimír;
Dyk, Štěpán;
Hlaváč, Zdeněk

Publication type:

Article

A posteriori error estimates for mixed finite element discretizations of the Neutron Diffusion equations.

Published in:

ESAIM: Mathematical Modelling & Numerical Analysis (ESAIM: M2AN), 2023, v. 57, n. 1, p. 1, doi. 10.1051/m2an/2022078

By:

Ciarlet, Patrick;
Do, Minh Hieu;
Madiot, François

Publication type:

Article

Computational Core Baffle Swelling Assessment of WWER Reactors: Modern Experience and Comparative Analysis.

Published in:

Strength of Materials, 2024, v. 56, n. 4, p. 688, doi. 10.1007/s11223-024-00683-z

By:

Shugailo, O.;
Pištora, V.;
Shavai, S.;
Dubyk, Y.;
Yari, L.;
Shlugen, V.;
Banko, S.;
Demenkov, V.

Publication type:

Article

Computational Assessment of the Shape Change of the WWER-1000 Reactor Core Baffle Considering Effects of Radiation Swelling, Radiation Creep, and Subcritical Metal Damage Via Ductile Fracture Models.

Published in:

Strength of Materials, 2023, v. 55, n. 2, p. 239, doi. 10.1007/s11223-023-00518-3

By:

Chirkov, O. Yu.;
Kharchenko, V. V.;
Kravchuk, L. V.

Publication type:

Article

Computational Evaluation and Analysis of Change in Shape Peculiarities of WWER-1000 Baffle Under Design and Long-Term Operation Conditions.

Published in:

Strength of Materials, 2021, v. 53, n. 6, p. 813, doi. 10.1007/s11223-022-00348-9

By:

Chirkov, O. Yu.;
Kharchenko, V. V.

Publication type:

Article

Special Features of Computational Assessment of the Change in Shape of WWER-1000 Reactor Core Baffle in View of Irradiation-Induced Swelling.

Published in:

Strength of Materials, 2020, v. 52, n. 3, p. 339, doi. 10.1007/s11223-020-00184-9

By:

Chirkov, A. Yu.;
Kharchenko, V. V.

Publication type:

Article

Studies of the Hydrodynamics of the Coolant behind Mixing Intensifier Grids of Fuel Assemblies of a PWR Reactor.

Published in:

High Temperature, 2022, v. 60, n. 3, p. 358, doi. 10.1134/S0018151X2202016X

By:

Dmitriev, S. M.;
Dobrov, A. A.;
Doronkov, D. V.;
Doronkova, D. S.;
Legchanov, M. A.;
Pronin, A. N.;
Ryazanov, A. V.;
Khrobostov, A. E.

Publication type:

Article

The interaction of nuclear reactor core melt with oxide sacrificial material of localization device for a nuclear power plant with water-moderated water-cooled power reactor.

Published in:

High Temperature, 2007, v. 45, n. 1, p. 22, doi. 10.1134/S0018151X0701004X

By:

Asmolov, V.;
Sulatskii, A.;
Beshta, S.;
Granovskii, V.;
Khabenskii, V.;
Krushinov, E.;
Vitol’, S.;
Al’myashev, V.;
Gusarov, V.;
Strizhov, V.

Publication type:

Article

High-Fidelity Monte Carlo Analysis of Highly-Localized Fission Power Peaking near a Flux Trap in an MTR Core.

Published in:

International Journal of Energy Research, 2023, p. 1, doi. 10.1155/2023/9727367

By:

Abuzlf, Hadi;
Castagna, Christian;
Makmal, Tzach;
Aviv, Ofer;
Yungrais, Zohar;
Gabrieli, Guy;
Steinitz, Uri;
Neder, Izhar;
Gilad, Erez

Publication type:

Article

Radial Basis Function Surrogate Model-Based Optimization of Small Light-Weight Lead-Bismuth Reactor Core.

Published in:

International Journal of Energy Research, 2023, v. 2023, p. 1, doi. 10.1155/2023/7712739

By:

Liu, Zijing;
Li, Qiong;
Zhao, Pengcheng;
Wang, Weijia;
Yu, Tao

Publication type:

Article

Preliminary conceptual design and analysis of a 100 kWe level Nuclear Silent Thermal‐Electrical Reactor (NUSTER‐100).

Published in:

International Journal of Energy Research, 2022, v. 46, n. 14, p. 19653, doi. 10.1002/er.8542

By:

Huang, Jinlu;
Wang, Chenglong;
Tian, Zhixing;
Guo, Kailun;
Su, G. H.;
Tian, Wenxi;
Zheng, Youqi;
Qiu, Suizheng

Publication type:

Article

Conceptual design of a new space nuclear reactor with low‐enriched uranium fuel based on the optimization of fuel composition and reflector geometry via optimized adaptive neuro‐fuzzy inference system as well as investigation of fresh core cycle length

Published in:

International Journal of Energy Research, 2022, v. 46, n. 7, p. 9456, doi. 10.1002/er.7817

By:

Rafiei, Meysam;
Ansarifar, Gholamreza

Publication type:

Article

Assessment of gadolinium concentration effects on the NuScale reactor parameters and optimizing the fuel composition via machine learning method.

Published in:

International Journal of Energy Research, 2022, v. 46, n. 7, p. 8838, doi. 10.1002/er.7760

By:

Shahmirzaei, A.;
Ansarifar, G.R.;
Koraniany, A.

Publication type:

Article

Effects of the central graphite column dimension and pebble size on power density distribution in annular core pebble‐bed HTR.

Published in:

International Journal of Energy Research, 2022, v. 46, n. 6, p. 8076, doi. 10.1002/er.7711

By:

Yang, Qianye;
Gui, Nan;
Huang, Xiaoli;
Zhang, Xiaoxi;
Yang, Xingtuan;
Tu, Jiyuan;
Jiang, Shengyao

Publication type:

Article

An algorithm for accurate modeling and simulating reactor cores with involute‐shaped fuel plates by Monte Carlo.

Published in:

International Journal of Energy Research, 2021, v. 45, n. 8, p. 12449, doi. 10.1002/er.6873

By:

Zhang, Shen;
Gui, Nan;
Kai, Tan;
Yang, Xingtuan;
Tu, Jiyuan;
Jiang, Shengyao

Publication type:

Article

Technical feasibility of integrating a modified power conversion unit into a non‐nuclear microreactor testbed.

Published in:

International Journal of Energy Research, 2021, v. 45, n. 8, p. 12325, doi. 10.1002/er.6517

By:

Guillen, Donna Post;
Wendt, Daniel S.

Publication type:

Article

Neutronic analysis of sodium‐cooled fast reactor design with different fuel types using modified CANDLE shuffling strategy in a radial direction.

Published in:

International Journal of Energy Research, 2021, v. 45, n. 8, p. 12272, doi. 10.1002/er.6384

By:

Shafii, Mohammad Ali;
Septi, Revina;
Handayani Irka, Feriska;
Arkundato, Artoto;
Su'ud, Zaki

Publication type:

Article

Development a methodology for evaluating inter‐assembly heat transfer effect through reactor core in system safety analysis of sodium‐cooled fast reactor.

Published in:

International Journal of Energy Research, 2021, v. 45, n. 8, p. 12258, doi. 10.1002/er.6369

By:

Wang, Shibao;
Zhang, Dalin;
Liang, Yu;
Wang, Xinan;
Qiu, Suizheng;
Su, Guanghui;
Tian, Wenxi

Publication type:

Article

A new structure design to extend graphite assembly lifespan in small modular molten salt reactors.

Published in:

International Journal of Energy Research, 2021, v. 45, n. 8, p. 12247, doi. 10.1002/er.6361

By:

Wang, Yong;
Guo, Wei;
Zhu, Gui‐Feng;
Dai, Ye;
Zhong, Yu;
Zou, Yang;
Chen, Jin‐Gen;
Cai, Xiang‐Zhou

Publication type:

Article

Numerical simulation on thermal‐hydraulic and thermoelectric characteristics of the TOPAZ‐II reactor core.

Published in:

International Journal of Energy Research, 2021, v. 45, n. 8, p. 12159, doi. 10.1002/er.6170

By:

Dai, Zhiwen;
Wang, Chenglong;
Zhang, Dalin;
Tian, Wenxi;
Qiu, Suizheng;
Su, G.H.

Publication type:

Article

Burn‐up calculation of the neutronic and safety parameters of thorium‐uranium mixed oxide fuel cycle in a Westinghouse small modular reactor.

Published in:

International Journal of Energy Research, 2021, v. 45, n. 8, p. 12013, doi. 10.1002/er.6000

By:

Uguru, Edwin H.;
Abdul Sani, Siti F.;
Khandaker, Mayeen U.;
Rabir, Mohamad H.;
Karim, Julia A.;
Onah, Daniel U.;
Bradley, David A.

Publication type:

Article

Conceptual design of a long cycle small modular reactor core with annular UO2 and FCM (TRU) fuels.

Published in:

International Journal of Energy Research, 2021, v. 45, n. 8, p. 11957, doi. 10.1002/er.5957

By:

Choi, Jae Yeon;
Hong, Ser Gi;
Kwon, Hyuk

Publication type:

Article

Preliminary study on physical characteristics of single‐pass super‐critical water‐cooled reactor core.

Published in:

International Journal of Energy Research, 2021, v. 45, n. 8, p. 11807, doi. 10.1002/er.5764

By:

Wang, Mingyue;
Huang, Liping;
Zhang, Qian;
Seidl, Marcus;
Liu, Zijing;
Wang, Xiang

Publication type:

Article

Automated core design code development for a lead‐cooled fast reactor and its core optimization.

Published in:

International Journal of Energy Research, 2021, v. 45, n. 8, p. 11721, doi. 10.1002/er.5553

By:

Luo, Xiao;
Zhang, Xilin;
Wang, Shuai;
Jiang, Rong;
Chen, Hongli

Publication type:

Article

3D Analysis of a multipurpose modular reactor for small energy production.

Published in:

International Journal of Energy Research, 2021, v. 45, n. 8, p. 11656, doi. 10.1002/er.5453

By:

Şahin, Sümer;
Şarer, Başar

Publication type:

Article

The AP‐Th 1000 – An advanced concept to use MOX of thorium in a closed fuel cycle.

Published in:

International Journal of Energy Research, 2021, v. 45, n. 8, p. 11642, doi. 10.1002/er.5421

By:

Stefani, Giovanni L.;
Maiorino, José R.;
Losada Moreira, João M.

Publication type:

Article

Review of the experimental research on the thermal‐hydraulic characteristics in the pebble bed nuclear reactor core and fusion breeder blankets.

Published in:

International Journal of Energy Research, 2021, v. 45, n. 8, p. 11352, doi. 10.1002/er.5378

By:

Liu, Limin;
Deng, Jian;
Zhang, Dalin;
Gu, Hanyang

Publication type:

Article

Thermal‐hydraulic analysis of an open‐grid megawatt gas‐cooled space nuclear reactor core.

Published in:

International Journal of Energy Research, 2021, v. 45, n. 8, p. 11616, doi. 10.1002/er.5329

By:

Qin, Hao;
Zhang, Ran;
Guo, Kailun;
Wang, Chenglong;
Tian, Wenxi;
Su, Guanghui;
Qiu, Suizheng

Publication type:

Article

Impacts of an ATF cladding on neutronic performances of the soluble‐boron‐free ATOM core.

Published in:

International Journal of Energy Research, 2020, v. 44, n. 10, p. 8193, doi. 10.1002/er.5322

By:

Nguyen, Xuan Ha;
Jang, Seongdong;
Kim, Yonghee

Publication type:

Article

Application of R2S unstructured tetrahedral mesh method to radioactive concrete structure dismantling using AETIUS/FISPACT codes.

Published in:

International Journal of Energy Research, 2020, v. 44, n. 10, p. 8181, doi. 10.1002/er.5321

By:

Kim, Jong W.;
Cho, Jin Y.;
Lee, Young‐Ouk

Publication type:

Article

Investigation of core meltdown phenomena and radioactive materials release in VVER‐1000/V446 nuclear reactor at severe accident condition due to LBLOCA along SBO.

Published in:

International Journal of Energy Research, 2020, v. 44, n. 10, p. 8113, doi. 10.1002/er.5056

By:

Ghasemi, A.;
Pirouzmand, A.;
Kamyab, S.

Publication type:

Article

Core neutronic characterization of a large molten‐salt cooled thorium‐based solid fuel fast reactor.

Published in:

International Journal of Energy Research, 2020, v. 44, n. 10, p. 8062, doi. 10.1002/er.5004

By:

Peng, Yu;
Zhu, Guifeng;
Zou, Yang;
Liu, Sijia;
Xu, Hongjie

Publication type:

Article

Preliminary investigation on the sodium fast reactor concave cores with near‐zero or negative sodium void reactivity.

Published in:

International Journal of Energy Research, 2020, v. 44, n. 10, p. 8025, doi. 10.1002/er.4913

By:

Liem, Peng Hong;
Tahara, Yoshihisa;
Takaki, Naoyuki

Publication type:

Article

Research of two‐phase density wave instability in reactor core channels with rolling motion.

Published in:

International Journal of Energy Research, 2020, v. 44, n. 9, p. 7323, doi. 10.1002/er.5444

By:

Tian, Wenxi;
Lian, Qiang;
Qiu, Suizheng;
Su, G.H.

Publication type:

Article

Thermoelectric characteristics analysis of thermionic space nuclear power reactor.

Published in:

International Journal of Energy Research, 2020, v. 44, n. 2, p. 855, doi. 10.1002/er.4926

By:

Dai, Zhiwen;
Wang, Chenglong;
Zhang, Dalin;
Tian, Wenxi;
Qiu, Suizheng;
Su, Guanghui

Publication type:

Article

Development and application of CFD and subchannel coupling analysis code for lead‐cooled fast reactor.

Published in:

International Journal of Energy Research, 2019, v. 43, n. 14, p. 8447, doi. 10.1002/er.4845

By:

Wang, Chi;
Cao, Liankai;
Zhang, Xuebei;
Shen, Chong;
Chen, Hongli

Publication type:

Article

Conceptual study of an accelerator‐driven ceramic fast reactor with long‐term operation.

Published in:

International Journal of Energy Research, 2018, v. 42, n. 4, p. 1693, doi. 10.1002/er.3970

By:

Yan, Xuesong;
Zhang, Xunchao;
Zhang, Yaling;
Yang, Yangyang;
Gao, Xiaofei;
Yang, Lei;
Zhan, Wenlong

Publication type:

Article

サブチャンネルスケールの分布定数のモデル化及びBWR 管群ボイド試験データによる妥当性確認

Published in:

Japanese Journal of Multiphase Flow, 2021, v. 35, n. 4, p. 543

By:

尾崎哲浩;
日引俊詞

Publication type:

Article

Seismic response of cylinder assemblies in axial flow.

Published in:

Journal of Fluid Mechanics, 2022, v. 943, p. 1, doi. 10.1017/jfm.2022.433

By:

Capanna, Roberto;
Ricciardi, Guillaume;
Sarrouy, Emmanuelle;
Eloy, Christophe

Publication type:

Article

NEUTRONIC DESIGN OF SMALL MODULAR LONG-LIFE PRESSURIZED WATER REACTOR USING THORIUM CARBIDE FUEL AT A POWER LEVEL OF 300–500 MWth.

Published in:

Eastern-European Journal of Enterprise Technologies, 2024, v. 127, n. 8, p. 18, doi. 10.15587/1729-4061.2024.290996

By:

Lapanporo, Boni Pahlanop;
Suâ€™ud, Zaki;
Andi Mustari, Asril Pramutadi

Publication type:

Article

A COMPARATIVE ANALYSIS OF GAS-COOLED FAST REACTOR USING HETEROGENEOUS CORE CONFIGURATIONS WITH THREE AND FIVE FUEL VARIATIONS.

Published in:

Eastern-European Journal of Enterprise Technologies, 2024, v. 127, n. 8, p. 6, doi. 10.15587/1729-4061.2024.298202

By:

Prasetya, Fajri;
Syarifah, Ratna Dewi;
Karomah, Iklimatul;
Aji, Indarta Kuncoro;
Trianti, Nuri

Publication type:

Article

NEUTRONIC ANALYSIS ON MOLTEN SALT REACTOR FUJI-12 USING 235U AS FISSILE MATERIAL IN LiF-BeF2-UF4 FUEL.

Published in:

Eastern-European Journal of Enterprise Technologies, 2022, v. 119, n. 8, p. 6, doi. 10.15587/1729-4061.2022.265798

By:

Mabruri, Ahmad Muzaki;
Syarifah, Ratna Dewi;
Aji, Indarta Kuncoro;
Hanifah, Zein;
Arkundato, Artoto;
Jatisukamto, Gaguk

Publication type:

Article

COMPARISON OF THORIUM NITRIDE AND URANIUM NITRIDE FUEL ON SMALL MODULAR PRESSURIZED WATER REACTOR IN NEUTRONIC ANALYSIS USING SRAC CODE.

Published in:

Eastern-European Journal of Enterprise Technologies, 2022, v. 116, n. 8, p. 21, doi. 10.15587/1729-4061.2022.255849

By:

Syarifah, Ratna Dewi;
Aula, Mila Hidayatul;
Ardianingrum, Andini;
Janah, Laela Nur;
Maulina, Wenny

Publication type:

Article

Long-time irradiation effect on corrosion behavior of aluminum alloy in pool water of low-power research reactor.

Published in:

Scientific Reports, 2023, v. 13, n. 1, p. 1, doi. 10.1038/s41598-023-44287-0

By:

Bagherzadeh, Mojtaba;
Karimi, Meysam;
Choopan Dastjerdi, Mohammad Hosein;
Asadi Asadabad, Mohsen;
Mokhtari, Javad;
Babanejhad, Afshin

Publication type:

Article

Long-time irradiation effect on corrosion behavior of aluminum alloy in pool water of low-power research reactor.

Published in:

Scientific Reports, 2023, v. 13, n. 1, p. 1, doi. 10.1038/s41598-023-44287-0

By:

Bagherzadeh, Mojtaba;
Karimi, Meysam;
Choopan Dastjerdi, Mohammad Hosein;
Asadi Asadabad, Mohsen;
Mokhtari, Javad;
Babanejhad, Afshin

Publication type:

Article

THERMAL HYDRAULIC METHOD OF OPTIMIZING THE THERMAL RESISTANCE OF NUCLEAR FUEL OF REACTOR INSTALLATIONS.

Published in:

Nuclear Physics & Atomic Energy, 2024, v. 25, n. 1, p. 43, doi. 10.15407/jnpae2024.01.043

By:

Skalozubov, V. I.;
Dorozh, O. A.;
Komarov, Yu. O.;
Galatsan, M. P.;
Mazurenko, A. S.;
Bundev, D. S.

Publication type:

Article

МОДЕЛЬ РЕАКТИВНІСНОЇ АВАРІЇ НА РБМК-1000.

Published in:

Nuclear Physics & Atomic Energy, 2022, v. 23, n. 2, p. 99, doi. 10.15407/jnpae2022.02.099

By:

Борисенко, В. І.;
Горанчук, В. В.

Publication type:

Article

THERMAL-HYDRAULIC CALCULATIONS OF THE WWR-SM RESEARCH REACTOR.

Published in:

Nuclear Physics & Atomic Energy, 2020, v. 21, n. 2, p. 152, doi. 10.15407/jnpae2020.02.152

By:

Baytelesov, S. A.;
Kungurov, F. R.;
Yuldashev, B. S.

Publication type:

Article