[en] The Nuclear Power Plant Analyzer (NPA), a personal computer based faster running simulator for PWR, is developed for transient analysis, personnel training, and computer-aid diagnosis. The NPA can be divided into two categories: plant module and man-machine interaction module. The plant module-TAPWR, consists of models for core kinetics, fuel transient conduction, reactor coolant system, pressurizer, and U-tube steam generator. Each of the models is optimized to obtain the capability of faster than real-time simulation. To check the sensitivity of models, TAPWR has been benchmarked against RELAP5/MOD2 code for a reactivity insertion accident. The NPA has a convenient, interactive and user friendly graphics interface. Simulation results can be displayed dynamically on a color graphics terminal by the interaction module. Using NPA, a LOFW accident for DAYA Bay Nuclear Power plant is analyzed

[en] The related investigations and the latest standards and criterions of start-up means for periodic test of EDG in nuclear power plant (NPP) were analyzed. The related amendments and its effect in overseas NPP were described. The necessity for the adoption of slow start-up means during periodic test of EDG in domestic NPP was demonstrated. Two kinds of modification methods were brought forward, theirs venture were detailed analyzed. This provided an important reference for the related modification in NPP. (authors)

[en] The statistics and classification of EMI event in nuclear power plant (NPP) were analyzed; the root cause and the solution of EMI event in NPP were also provided. The necessity of establishing the whole process defenses strategy for the EMI Event in NPP was described. And then, 3 main problems were put forward from the perspective of the whole process defenses strategy for the EMC problem in NPP. The answer provided very important reference for the whole process defenses strategy for the EMI Event in NPP. (authors)

[en] The 'pressure well' function preventing the thermal fatigue phenomenon of the primary loop safety injection pipeline and its effect on the safety injection are analyzed comprehensively. Three modification schemes have been put forward. After referring to lots of data and literature, The advantages and disadvantages of three different schemes under accident condition are compared, and the optimal system design scheme is determined. This demonstration method could provide reference for relevant improvement of the engineered safety features of nuclear power plan. (authors)

[en] Mixed core compatibility is one of important issues affecting the nuclear safety and the reliable generation of a Nuclear Power Plant. The thermal and hydraulic design and safety bases of mixed cores are defined and the approach of DNB design is well illustrated with its application to the 18-month fuel cycles project of Daya Bay Nuclear Power Plant. The mixed core analyses of the project shows that the requirements are fully satisfied

[en] AFA-2G assemblies in Ling Ao NPS (LNPS) have been replaced gradually by AFA-3G assemblies from cycle 2 and subsequent cycles. the enrichment of the fuels will be increased from 3.2% to 3.7% from cycle 3 in Ling Ao. Therefore, the study of ling Ao mixed core and increased enrichment have been performed since 2001. Lots of accidents need to be re-analyzed in Ling Ao NPS in order to verify its safety requirements for the new fuel management. Control rod drop accident for LNPS was re-analyzed in 2001 in frame of FRAMATOME ANP analytical methodology. The analytical codes used in the accident analysis include SCIENCE, ESPADON, CINEMA, CANTAL and FLICA III. The control rod drop accident analysis is performed with respect to the 10 reference cycles of the generic fuel management design for Ling Ao mixed core and increased enrichment study. The pre-drop FδH for the first transition cycles and other cycles are 1.52 and 1.55, respectively. For detected dropped rod configurations, the negative flux rate protection system actuates a reactor trip. For the non-detected dropped rod configurations, the minimum DNBR values have been evaluated with conservative analysis methodology and assumptions and the DNBR fuel design limit is respected the analytical results shows that, for all the non-detected dropped rod configurations, the minimum DNB margin is about 2% which occurs in AFA-2G fuel assembly in the first transition cycle. (author)

[en] Graphical abstract: Electrochemically cathodic exfoliation of graphite into few-layer graphene sheets in room temperature ionic liquids (RTILs) N-butyl, methylpyrrolidinium bis(trifluoromethylsulfonyl)-imide (BMPTF₂N). -- Highlights: • Few-layer graphene sheets were prepared through electrochemically cathodic exfoliation in room temperature ionic liquids. • The mechanism of cathodic exfoliation in ionic liquids was proposed. • The derived activated graphene sheets show enhanced electrochemical properties. -- Abstract: Electrochemically cathodic exfoliation in room temperature ionic liquids N-butyl, methylpyrrolidinium bis(trifluoromethylsulfonyl)-imide (BMPTF₂N) has been developed for few-layer graphene sheets, demonstrating low levels of oxygen (2.7 at% of O) with a nearly perfect structure (I_D/I_G < 0.05). The mechanism of cathodic exfoliation in BMPTF₂N involves the intercalation of ionic liquids cation [BMP]⁺ under highly negatively charge followed by graphite expansion. Porous activated graphene sheets were also obtained by activation of graphene sheets in KOH. Transmission electron microscopy, X-ray photoelectron spectroscopy and Raman spectroscopy were used to characterize these graphene materials. The electrochemical performances of the graphene sheets and porous activated graphene sheets for lithium-ion battery anode materials were evaluated using cyclic voltammetry, galvanostatic charge–discharge cycling, and electrochemical impedance spectroscopy

[en] A superconducting cavity coupler with coaxial symmetric structure is introduced. The coupling parameter of the coupler is analyzed by the SUPERFISH program. The curve of the coupler inner conductor position versus coupling parameter is obtained. The analyze result of coupling parameter is according with the experiment of a model cavity. As a result, the coupling parameter of CAEP superconducting photocathode injector experiment is given: coupling parameter is 1637, the position of coupler inner conductor is 15.45 cm and the average accelerating field is 20 MV/m

[en] Objective: To study the CKMBmass by immunoturbidimetric method and verify the consistency of CKMBmass and method of chemiluminescence platform creatine kinase isoenzyme MB (CK-MB) by testing clinical random samples and samples of CKMB inverted in the active method in clinical setting. The receiver operating characteristic (ROC) curve was referenced to the clinical judgment with gold standard of high-sensitivity troponin I to verify the accuracy of CKMBmass. Methods: CKMBmass was detected by Beckman AU5811 biochemical analyzer, while CK-MB and high-sensitivity troponin I (cTnI) were detected by Abbott i2000 chemiluminescence meter. 24 inverted samples of CKMBmass and CK-MB were collected to verify the consistency of the measured values. 45 serum samples of CKMBmass and CK-MB were detected at random to verify their correlations. CKMBmass and cTnI were used to measure AMI group samples and non-AMI samples simultaneously. The results were analyzed using ROC curve to verify the accuracy of CKMBmass. Results: In 24 inverted samples, the CKMBmass measurement was the same as the Abbott CK-MB measurement, and the direction of negative-positive was the same. In 45 random samples, the regression equation of the CKMBmass and Abbott CK-MB measurement was Y = 1.002X-0.080. There was a significant difference in the non-AMI group (P < 0.05), and CKMBmass AUC was 0.963. Conclusion: The anti-interference ability and correlation of CMBMmass are consistent with the chemiluminescence method CK-MB. The diagnosis of AMI is highly consistent with the high-sensitivity cTnI, which meets the clinical needs. (authors)

[en] The defect of earlier physical protection system of nuclear power plant (NPP) was described. The trend of development of physical protection system of NPP was put forward after the analysis of the demand of new tendency for the physical protection system of NPP. A new architecture of physical protection system of NPP was raised after the analyzing of new technology which can be used in physical protection system of NPP. (authors)