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Wei T.,Nuclear Power Institute of China | Lin J.,Fujian Fuqing Nuclear Power Co. | Long C.,Nuclear Power Institute of China | Chen H.,Nuclear Power Institute of China
Jinshu Xuebao/Acta Metallurgica Sinica | Year: 2016

Advanced boiling water reactors (ABWRS) show optimistic application prospect in the future. However, in these reactors, influence of dissolved oxygen (DO) on the corrosion rate of zirconium fuel claddings should be seriously considered. In this work, the effect of the dissolved oxygen (DO) on the corrosion behaviors of Zr-4, N18 (Zr-1.0Sn-0.3Nb-0.3Fe-0.1Cr) and N36 (Zr-1.0Sn-1.0Nb-0.3Fe) alloys in 400℃ and 10.3 MPa steam was investigated. A recirculation loop was used to control the DO level at about 0.1×10-6 and 1.0×10-6, respectively. The results showed that, under the two DO level conditions, N18 had almost the same weight gain as Zr-4 after exposure for 90 d, and N36 had the highest weight gain. In the initial period of the corrosion test, the three alloys had lower weight gain under higher DO level condition. With the increase of exposure time, the weight gain under 1.0×10-6DO level exceeded gradually the weight gain under 0.1×10-6 level for each alloy, and the time needed for exceeding was significantly shorter for the alloy with higher Nb content. © All right reserved. Source


Li S.,University of Science and Technology Beijing | Wang Y.,University of Science and Technology Beijing | Dai X.,Fujian Fuqing Nuclear Power Co. | Liu F.,Chalmers University of Technology | And 2 more authors.
Journal of Nuclear Materials | Year: 2016

The ion irradiation hardening behaviors of Fe-9 wt% Cr and Fe-20 wt% Cr model alloys were investigated by nanoindentation technique. The specimens were irradiated with 3 MeV Fe11+ ions at room temperature up to 1 and 5 dpa for Fe-9Cr alloy and 1 and 2.5 for Fe-20Cr alloy. The ratio of average hardness in the same depth of irradiated and unirradiated (Hirr. av/Hunirr. av) was used to determine the critical indentation depth hcrit to eliminate the softer substrate effect. The Nix-Gao model was used to explain the indentation size effect. Irradiation hardening is clearly observed in both Fe-9Cr alloy and Fe-20Cr alloy after ion irradiation. The differences of ISE and irradiation hardening behaviors between Fe-9Cr and Fe-20Cr alloys are considered to be due to their different microstructures and microstructural evolution under ion irradiation. © 2016 Elsevier B.V. Source


Li Z.,Southwest Jiaotong University | Li Z.,Fujian Fuqing Nuclear Power Co. | Zhai W.,Southwest Jiaotong University | Tian G.,Southwest Jiaotong University | Li J.,Southwest Jiaotong University
Advances in Environmental Vibration - Proceedings of the 5th International Symposium on Environmental Vibration, ISEV 2011 | Year: 2011

A numerical mxlel is set up for investigating dynamical behaviors of high-speed trains running in crosswind, which is composed of an aerodynamic model and a vehicle dynamic model. The dynamical performances of two high-speed trains with different shapes are compared. The influences of car body mass on the running safety in crosswind and absence of crosswind are investigated. Results show that the running safety of high-speed train decrease with the increase of crosswind speed or train speed. The head car is the most dangerous in one train under crosswind condition. The difference of running safety between the two trains becomes large with the increase of crosswind speed. There is little difference between the Sperling indexes of two trains. The running safety of vehicle is more sensitive to the car body mass in crosswind than under no crosswind condition. It is suggested to increase the car body mass of the head car within a certain range to ensure the running safety of high-speed train in crosswind. Source


Yan C.,University of Science and Technology Beijing | Yan C.,China Institute of Atomic Energy | Wang R.,Suzhou Nuclear Power Research Institute | Dai X.,Fujian Fuqing Nuclear Power Co. | And 4 more authors.
Journal of Nuclear Materials | Year: 2016

Irradiation hardening behavior of Zr-1Nb was examined by nanoindentation, slow positron annihilation technique, transmission electron microscopy and coplanar extremely asymmetric X-ray diffraction technique. Samples were irradiated at a dose rate of 2.78 × 10-4 dpa/s to peak doses of 0.15, 0.5, 1.5 and 2.5 dpa with 6.37 MeV Xe26+ ion beam at room temperature. The increase in hardness as a function of dose followed a power law expression with the exponent of 0.46. With increasing irradiation dose, more mono-, di- and trivacancies were induced, but their concentration remained constant once formed due to the equilibrium between the formation and recombination of vacancy type clusters during irradiation. Meanwhile, the dislocation loops were also introduced and their linear density increased with dose. The dislocation loops played an important role in the irradiation hardening behavior. But the exact contribution of each microstructural components to the overall hardness still needs further study. © 2016 Elsevier B.V. All rights reserved. Source


Liu Z.-S.,Fujian Fuqing Nuclear Power Co. | Huang H.,Fujian Fuqing Nuclear Power Co.
Hedianzixue Yu Tance Jishu/Nuclear Electronics and Detection Technology | Year: 2013

Taking Phase I Fujian Fuqing nuclear power plant project as a reference, functions and composition of PWR Nuclear Power Plant radiation monitoring system operated in our country are introduced firstly in this article. Then development tendencies, as well as the design improvements are described in detail in aspects as airborne radioactive material sediment loss in the sampling pipeline, standard calibration methods for airborne sampling monitors, detection technology for leakage of primary circuits, network topology, high humidity noble gas monitoring technology, and site monitoring technology, etc. Source

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