... 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...

... 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...

..., 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...

... 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...

... been validated with both CFD simulations and an experimental mock-up. spacer grids PWR hydraulic network fuel assemblies’ deformation MODELING THE FLOW REDISTRIBUTION UPSTREAM FROM THE SPACER GRID OF A PWR Stanislas de Lambert1, Jérome Cardolaccia Université Paris-Saclay, CEA, Service...

... and differences between the two approaches considering the French and UK regulatory contexts. BDB DEH rare and severe natural hazards safety PWR PROTECTION OF NUCLEAR POWER PLANTS AGAINST NATURAL HAZARDS: PROTECTION PRINCIPLES AGAINST RARE AND SEVERE NATURAL HAZARDS FOR NEW NUCLEAR POWER PLANTS...

... 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...

... with those objectives, wind flow behavior around a PWR (Pressurized Water Reactor) nuclear power plant is studied. The goal of this work is to check that there is no exceeding local wind speed relative to the wind entering the site. The severe winds are characterized locally near the buildings in terms...

.... In conclusion, the capacity of the EDF 900 MW NPPs to cope with high level of natural hazard (equivalent to decamillennial events) is being verified through the 4 th periodic safety reviews, in compliance with WENRA reference level T4.2. natural hazards WENRA DBH safety PWR PROTECTION OF NUCLEAR...

... Abstract This work aims to develop a finite element model of a PWR control rod at operating conditions for stress analysis of the rod cladding. The finite element model simulates a control rod exposed to high operating temperatures and pressure while portions of the rod are irradiated...

... the risk impacts from near-term ATF (FeCrAl and Chromium-coated clads) on a generic Westinghouse three-loop pressurized water reactor (PWR) under the following accident scenarios: station blackout (SBO), loss of feedwater (LOFW), steam generator tube rupture (SGTR), loss-of-coolant accidents (LOCAs...

... is validated using the experimental test data. PWR fuel cladding PCMI DEVELOPMENT OF THE FUEL BEHAVIOR ANALYSIS CODE FOR MECHANICAL FUEL CLADDING FAILURE DURING REACTIVITY INSERTION EVENT IN PWR Yuma Higashi 1 , Nozomu Murakami 1 , Tadakatsu Yodo 1 , Teruhisa Yamamoto 2 1 Mitsubishi Heavy...

... According to advanced light water reactor (ALWR) Utility Requirement Document (URD), plant control systems should be designed to meet the specified design requirements for an advanced 1000 MWe class PWR nuclear power plant (NPP). As per the plant design requirements, AP1000 control systems were...

... TRISO coated particle, developed for HTGR initially, has advantages of nuclear proliferation-resistance and fuel integrity against the release of fission products. In this paper, a 350MWt small sized PWR core design utilizing TRISO fuel concept is presented. TRISO particles are dispersed...

... to be met by the supplier and by the manufacturer for the design justifications and for the manufacturing and inspection operations of PWR fuel assemblies and rod cluster control assemblies. We go over the different chapters of RCC-C: product and part characteristics; manufacturing and inspection processes...