... to be complex and error-prone. In light of this, we developed Bamboo-Frame to automate the modeling procedure in Pressurized Water Reactor (PWR) core analysis. This innovative tool requires users to provide only structural and operational parameters, while effectively managing complex tasks such as lattice...

... higher than that of other hydrogen production methods coupled with PWR. The hydrogen production efficiency of this method can be higher than 42%, which is more than 50% higher than that before optimization. The comparison of the hydrogen production efficiency of this method with that of other renewable...

...Proceedings of the 2024 31st International Conference on Nuclear Engineering ICONE31 August 4-8, 2024, Prague, Czech Republic ICONE31-134481 DISCUSSION ON RADIATION PROTECTION FOR PWR SECOND-LOOP STEAM SUPPLY OUTSIDE FOR INDUSTRIAL APPLICATION Yaping Zhuang Shandong Nuclear Power Company, Haiyang...

.... To demonstrate that these calculations using the simulation code are valid, it is important to validate both the simulation code and the input data. We present our approach to PWR accident analysis based on simulations of a small-break LOCA test (SB-CL-18) in the Large-Scale Test Facility (LSTF) using the three...

... inlet and outlet under asymmetric loop flow conditions are summarised, which provides certain reference value for the optimal design and safety analysis of the reactor. Keywords PWR; RPV; CFD; Porous media core; Core inlet flow distribution; Coolant flow mixing; Konvoi 1 Copyright © 2024 by ASME 1...

... Abstract In the realm of nuclear reactor design, ensuring uniform flow rates at the core inlet of Pressurized Water Reactors (PWR) is vital for safety, impacting cooling functions and “fuel hot spot” criteria. This intricate balance is influenced by fluid dynamics in the reactor pressure...

... affecting tube deformation. PWR steam generator fluid-structure coupling flow induced vibration Proceedings of the 2024 31st International Conference on Nuclear Engineering ICONE31 August 4-8, 2024, Prague, Czech Republic ICONE31-134975 FLUID-STRUCTURE COUPLING ANALYSIS OF U-TYPE TUBE BUNDLE...

...-of-coolant accidents. accident tolerant fuels neutronics PWR chromium coating Serpent 2.31 code Proceedings of the 2024 31st International Conference on Nuclear Engineering ICONE31 August 4-8, 2024, Prague, Czech Republic ICONE31-135127 PERFORMANCE ANALYSIS FOR ENHANCED CR-COATED FUEL CLADDING...

... of Nuclear Science and Technology, Southwest University of Science and Technology, Mianyang, China ABSTRACT This paper introduces the thermal-fast neutron conversion material 6LiD to improve the transmutation efficiency of MAs in commercial PWR, especially the fission rate, and investigate the feasibility...

... of the nuclear fuel cycle requires gradual and phased progresses. Since most of the operating nuclear power plants in China are PWR units, and China implements and promotes a commercial closed nuclear fuel cycle, how to initiate a closed nuclear fuel cycle from the mature commercial pressurized water reactors...

... Abstract This paper describes the loading pattern, safety evaluation and operating experiences of PWR plant off-site Spent Fuel Dry Storage System (SFDSS). According to the limits from the SFDSS criticality and heat-transfer safety analysis, ALARA principle and AFA series fuel characteristics...

..., the responses of the detectors to some remote rods are not obvious, which are not easy to determine. All the methods were tested on the numerical calculation examples of a pressurized water reactor case. control rod position monitoring global search algorithm PWR Proceedings of the 2022 29th...

... of the core loaded with annular fuel by 50%. annular fuel PWR safety analysis Proceedings of the 2022 29th International Conference on Nuclear Engineering ICONE29 August 8-12, 2022, Virtual, Online ICONE29-92118 PERFORMANCE EVALUATION OF TYPICAL 3-LOOP PWR WITH ANNULAR FUEL ASSEMBLIES UNDER TYPICAL...

... Abstract Currently, the supplementary strategy of PWR nuclear power unit to deal with the Station Black-Out (SBO) and Total Loss of Feed-water (TLFW) accidents mainly depends on mobile facilities and manual operation. Under the SBO together with TLFW (SBO+TLFW) beyond design basis accident...

... comprehension of PWR and VVER. 3) European codes and methods development for VVER safety assessment will open the VVER market to the European nuclear industry. CAMIVVER will perform developments required for the new generation codes and will generalize 3D-multiphysics coupling, performing benchmark against...

... analysis method nuclear safety evaluation PWR Proceedings of the 2021 28th International Conference on Nuclear Engineering ICONE28 August 4-6, 2021, Virtual, Online ICONE28-64393 APPLICATION OF BEST-ESTIMATE PLUS UNCERTAINTY ANALYSIS METHOD IN NUCLEAR SAFETY EVALUATION Xinlu Tian, Jianping Jing...

... than 10 15 Bq. Inhalation dose was the major contribution to the total effective dose. The total effective dose and thyroid dose of Hualong 1 at EAB and the outer boundary of LPZ fully met the requirements of Chinese GB6249. radioactivity radiation dose loss of coolant accident PWR...

... better utilization for research and training, especially in nuclear newcomer countries. transient analysis reactor safety PWR LOCA SGTR PCTRAN Proceedings of the 2021 28th International Conference on Nuclear Engineering ICONE28 August 4-6, 2021, Virtual, Online ICONE28-65663 A SYSTEMATIC...

... the French and UK regulatory contexts. Keywords: BDB, DEH, Rare and Severe Natural Hazards, Safety, PWR 1. INTRODUCTION The field of protection against external natural hazards has regularly evolved since the design of the first NPPs (Nuclear Power Plants) to take into account: operational feedback...

... of nuclear power plants to the climatic hazards through the consideration of the updated hazard levels. climatic hazards climate change safety PWR IMPACT OF CLIMATE CHANGE ON EDF'S NUCLEAR FACILITIES: CLIMATE WATCH APPROACH L. Guinard1, S. Parey2, H. Cordier1, L. Grammosenis1 1Electricité de...