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Safety Assessment of Advanced PWR

2018 International Conference on Power Generation Systems and Renewable Energy Technologies (PGSRET), 2018
In the present study, safety assessment of advanced light water nuclear reactor has been performed using the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) methodology. This methodology is considered to be a tool to check the nuclear energy system (NES) sustainability in seven different areas. Out of these seven areas, one
Suhail Ali   +4 more
openaire   +1 more source

Studies on the Use of Thorium in PWR

2020
A study was taken up to assess the use of thorium in PWR type of lattice. The case study was done for the 17 × 17 square lattice fuel assembly (FA) of Westinghouse design used in modern PWRs namely AP1000 and EPR. This work describes some theoretical results obtained by loading thorium in oxide form as main fertile with either LEU or PWR grade ...
Devesh Raj, Umasankari Kannan
openaire   +1 more source

Accident management for French PWRs

Nuclear Engineering and Design, 1994
Abstract The accident management scheme as it exists now for French pressurized water reactors has been developed in stages over a period of more than 10 years. The requirement — equipment, procedures, structures, communication and transmission systems — are operational although improvements are still to be considered.
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?????????????? ?????????????????????????? ???????????????????? ?????????????????? ?????????????????????????? ?????????????? ?????????????? ?? ?????????????? ???????? ?????????????? ?????????????? ?????? ?? ????????, PWR ???? ???????????????????????? ????????????????????????

2016
???????? ?????????????????????????? ???????????? ?????????????????? ??????????-?????????????????????? ???????????? ???? ???????????? ???????????????????? ?????? ?? ???????????????????? ???????? PWR ?? ???????????????????? ??????, ???? ?????????????????? ?????????????? ???????????????????????????? ???????????????? ?????????????????????? ?????????????????
openaire   +1 more source

?????????????? ?????????????????????? ?????????? ???? ???????????????? ???????? ???? ???????????? ?????????????? ?????????????? ?????? ???????????????????????? PWR ?? ???????????????????? ???????????? ?????? ????????-1000

2018
???????????????????????????? ?????????????????????? ?????????????????? ?????????? ?? ???????????????????? ?????????????? ?????????????? ?????????????????? ???????? ?? ?????????? ?????????????????? ?????????????????????????? ?????????? ?????? ????????????????????. ???? ???????????????? ?????? ?? ???????????????????? PWR ?????????????????? ?????????? ?? ?
openaire   +1 more source

PWR Supplemental Surveillance Program

2014
A pressurized water reactor (PWR) supplemental surveillance program (PSSP) is being designed to provide high-fluence reactor vessel material embrittlement data for the operating U.S. PWRs. Peak reactor pressure vessel (RPV) fluence levels as high as 7 × 1019n/cm2 (E > 1.0 MeV) will be attained as PWRs operate to 60 years and potentially beyond ...
J. Brian Hall   +3 more
openaire   +1 more source

Design of the flexible switching controller for small PWR core power control with the multi-model

Nuclear Engineering and Technology, 2021
Wenjie Zeng, Qingfeng Jiang
exaly  

PWR steam generators

International Journal of Multiphase Flow, 1995
S.J. Green, G. Hetsroni
openaire   +1 more source

Low cycle fatigue behavior of alloy 690 in simulated PWR water—Effects of dynamic strain aging and hydrogen

Materials Science & Engineering A: Structural Materials: Properties, Microstructure and Processing, 2014
Jong-Dae Hong, Changheui Jang
exaly  

History of PWR and BWR Development

2021
Jeffery A. Brown, G. Ivan Maldonado
openaire   +1 more source

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