Results 101 to 110 of about 167,510,152 (115)

Fusing together an outline design for sustained fuelling and tritium self-sufficiency. [PDF]

Philos Trans A Math Phys Eng Sci
Lord M, Bennett I, Harrington C, Cooper A, Lee-Lane D, Cureton A, Olde C, Thompson M, Jayasundara D, Meatyard T.   +9 more
europepmc   +1 more source

First-Principles Study on the Adsorption Mechanism of Oxygen on UN(100), (110), and (111) Surfaces. [PDF]

Materials (Basel)
Zhang T, Zhu M, Huang H, Pu L, Peng C, Li L, Wang Z, Li B.   +7 more
europepmc   +1 more source

Enhancing chromium coating thickness estimation with multi-head attention LSTM and data augmentation. [PDF]

Sci Rep
Jeon M, Choi W, Park JW, Lee J, Mun D.
europepmc   +1 more source

Resilient design in nuclear energy: Critical lessons from a cross-disciplinary analysis of the Fukushima Dai-ichi nuclear accident. [PDF]

iScience
Ayoub A, Wainwright HM, Sansavini G, Gauntt R, Saito K.   +4 more
europepmc   +1 more source

Hydrothermal Corrosion of Latest Generation of FeCrAl Alloys for Nuclear Fuel Cladding. [PDF]

Materials (Basel)
Nagothi BS, Qu H, Zhang W, Umretiya RV, Dolley E, Rebak RB.   +5 more
europepmc   +1 more source

Investigation of a Hydrogen Mitigation System During Large Break Loss-Of-Coolant Accident for a Two-Loop Pressurized Water Reactor [PDF]

Nuclear Engineering and Technology, 2016
Hydrogen release during severe accidents poses a serious threat to containment integrity. Mitigating procedures are necessary to prevent global or local explosions, especially in large steel shell containments.
Gholamreza Jahanfarnia
exaly   +2 more sources

Thermal analysis of heated cylinder simulating nuclear reactor during loss of coolant accident

Journal of Nuclear Science and Technology, 2014
Hirofumi Ohashi, Hiroyuki Sato, Masuro Ogawa   +2 more
exaly  

Behavior of an improved Zr fuel cladding with oxidation resistant coating under loss-of-coolant accident conditions

Journal of Nuclear Materials, 2016
Jae Ho Yang, Dong Jun Park
exaly  

Study on shaft-block under small break loss of coolant accident of nuclear main pump

Annals of Nuclear Energy, 2019
Rongsheng Zhu
exaly  

Safety Evaluation of Silicon Carbide and Zircaloy-4 Cladding during a Large-Break Loss-of-Coolant Accident †

Energies, 2018
Kyohun Joo, Sung-Pil Park, Kwangwon Ahn
exaly