scholarly journals FULL POWER OPERATION OF THE LAMPF 805 MHz SYSTEM.

1970 ◽  
Author(s):  
R Jameson ◽  
J Wallace ◽  
R Cady ◽  
D Liska ◽  
J Sharp ◽  
...  
Keyword(s):  
Full Power ◽  
Power Operation

Radiation shielding requirements for the full power operation of the linear IFMIF prototype accelerator (LIPAc) at Rokkasho

2019 ◽  
Vol 146 ◽  
pp. 293-298 ◽  
Author(s):  
Keitaro Kondo ◽  
Beatriz Brañas ◽  
Philippe Cara ◽  
Hervé Dzitko ◽  
Dominique Gex ◽  
...  
Keyword(s):  
Radiation Shielding ◽  
Full Power ◽  
Power Operation

The Study and Design of 20kW Photovoltaic Power System

2013 ◽  
Vol 860-863 ◽  
pp. 151-155
Author(s):  
Yun Bo Zhang ◽  
Wen Zheng ◽  
Hong Zhang
Keyword(s):  
Power System ◽  
Design Strategy ◽  
Photovoltaic Modules ◽  
Photovoltaic Power ◽  
Full Power ◽  
Power Operation ◽  
Grid Connected Inverter ◽  
Parameters Calculation

This paper firstly analysis the principle of three-phased photovoltaic grid-connected power system. Secondly, the 20KW photovoltaic power system will be given as an example to introduce the design strategy of photovoltaic modules. Also, the photovoltaic grid-connected inverter is designed, which includes its parameters calculation and components selection. Finally, the whole photovoltaic power system is designed and verified via the experiment. The result of the experiment shows the design is reasonable and reliable. The power system can achieve full power operation and satisfy its expected goal.

scholarly journals The Local Seismoacoustic Wavefield of a Research Nuclear Reactor and Its Response to Reactor Power Level

2020 ◽  
Vol 92 (1) ◽  
pp. 378-387
Author(s):  
Omar E. Marcillo ◽  
Monica Maceira ◽  
Chengping Chai ◽  
Christine Gammans ◽  
Riley Hunley ◽  
...  
Keyword(s):  
Energy Transport ◽  
Nuclear Reactor ◽  
Power Level ◽  
National Laboratory ◽  
Reactor Power ◽  
Operational Conditions ◽  
Oak Ridge ◽  
Research Nuclear Reactor ◽  
Full Power ◽  
Power Operation

Abstract We describe the seismoacoustic wavefield recorded outdoors but inside the facility fence of the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (Tennessee). HFIR is a research nuclear reactor that generates neutrons for scattering, irradiation research, and isotope production. This reactor operates at a nominal power of 85 MW, with a full-power period between 24 and 26 days. This study uses data from a single seismoacoustic station that operated for 60 days and sampled a full operating reactor cycle, that is, full-power operation and end-of-cycle outage. The analysis presented here is based on identifying signals that characterize the steady, that is, full-power operation and end-of-cycle outage, and transitional, that is, start-up and shutdown, states of the reactor. We found that the overall seismoacoustic energy closely follows the main power cycle of the reactor and identified spectral regions excited by specific reactor operational conditions. In particular, we identified a tonal noise sequence with a fundamental frequency around 21.4 Hz and multiple harmonics that emerge as the reactor reaches 90% of nominal power in both seismic and acoustic channels. We also utilized temperature measurements from the monitoring system of the reactor to suggest links between the operation of reactor’s subsystems and seismoacoustic signals. We demonstrate that seismoacoustic monitoring of an industrial facility can identify and track some industrial processes and detect events related to operations that involve energy transport.

Chemical Neutralization to Control Denting in Nuclear Steam Generators

1983 ◽  
Vol 105 (4) ◽  
pp. 763-770 ◽  
Author(s):  
T. A. Beineke ◽  
J. F. Hall ◽  
K. E. Marugg ◽  
D. B. Scott ◽  
R. M. Orsulak ◽  
...  
Keyword(s):  
Boric Acid ◽  
Calcium Hydroxide ◽  
Calcium Concentration ◽  
Chloride Concentration ◽  
Line Treatment ◽  
Steam Generators ◽  
Adverse Side Effects ◽  
On Line ◽  
Full Power ◽  
Power Operation

Laboratory testing at Combustion Engineering has indicated promise in controlling simulated steam generator tube denting through chemical neutralization. Testing was limited to on-line treatment, and two neutralizers have been evaluated: (i) calcium hydroxide, and (ii) boric acid. On-line treatment with calcium hydroxide successfully halted active denting whenever the bulk calcium concentration (in ppm) equaled or exceeded the bulk chloride concentration (in ppm). Calcium hydroxide also was effective as an alternative to ammonia as a pH controlling agent in two tests conducted without ingress of chloride. On-line treatment with boric acid consisted of a four-day soak at simulated low (approximately 30 percent) power with 50 ppm B followed by one month full-power operation with 10 ppm B. This treatment also halted denting. Nondestructive and destructive examination of test boilers gave no indication of adverse side effects associated with either neutralizer.

Analysis of PSA Conservative Assumptions’ Impact on Risk Profile for Armenian NPP Unit 2

2008 ◽  
Author(s):  
Shahen Poghosyan ◽  
Armen Amirjanyan ◽  
Surik Bznuni
Keyword(s):  
Risk Assessment ◽  
Decision Making ◽  
Risk Profile ◽  
Informed Decision ◽  
Informed Decision Making ◽  
Comparative Risk Assessment ◽  
Comparative Risk ◽  
Full Power ◽  
Power Operation ◽  
The Impact

PSA is a powerful tool for detailed risk assessment and risk-informed decision making. The main deliverables from PSA models is comparative risk assessment of different risk contributors including systems, components, IEs, etc. Risk-informed decision making process is based on obtained risk profile. In comparison with deterministic approach conservatism included in PSA models could lead to deformation of risk profile which will bring to inappropriate decision making based on PSA results. This paper presents analysis done for Armenian NPP PSA study in order to assess the impact of conservative assumptions on final risk profile coming from potential internal initiating events at full power operation.

The extended living probabilistic safety assessment

2019 ◽  
Vol 234 (1) ◽  
pp. 183-192
Author(s):  
Marko Čepin
Keyword(s):  
Low Power ◽  
Nuclear Power ◽  
Safety Assessment ◽  
Risk Level ◽  
Probabilistic Safety Assessment ◽  
Core Damage ◽  
Full Power ◽  
Power Operation ◽  
Plant Shutdown ◽  
Probabilistic Safety

The term living probabilistic safety assessment was defined soon after the initial probabilistic safety assessments were implemented. The objective of this article is to present the extended living probabilistic safety assessment and its applications considering realistic nuclear power plant models, including the low power and shutdown plant operating states. One of the key objectives is to compare the suitability of conventional and additional risk measures, core damage frequency and conditional core damage frequency, respectively. The methods are presented considering all states of the plant from the full power operation to the low power and shutdown states. The example models of the nuclear power plants and the results of the living probabilistic safety assessment of the plant operating states are discussed. The results show that the risk of low power and shutdown states is generally smaller than the risk of full power operation, but the low power and shutdown plant operating states differ significantly among each other regarding the risk level. The deficiency of living probabilistic safety assessment applied to the plant shutdown states is connected with significantly increased human effort for the analyses, with a significantly greater amount of results and with increased uncertainty of some parameters due to the larger dynamics of actions in the plant shutdown versus the full power operation states. The benefit of the living probabilistic safety assessment applied to the plant low power and shutdown states lays in consideration of all states and potential identification of risk significant states and directions for possible safety improvements.

Progress of the HTR-10 Measured Data Utilization

2014 ◽  
Author(s):  
Fubing Chen ◽  
Yujie Dong ◽  
Yanhua Zheng ◽  
Lei Shi ◽  
Fu Li ◽  
...  
Keyword(s):  
High Temperature ◽  
Measured Data ◽  
Inherent Safety ◽  
Data Utilization ◽  
Existing Problems ◽  
New Energy ◽  
Full Power ◽  
Power Operation ◽  
Safety Features ◽  
High Temperature Gas

The 10 MW High Temperature Gas-cooled Reactor-Test Module (HTR-10), which was designed, constructed and operated by the Institute of Nuclear and New Energy Technology (INET) of Tsinghua University, is the first High Temperature Gas-cooled Reactor (HTGR) in China. Stepping into the commissioning phase in April, 2000, the HTR-10 attained the first criticality in December, 2000 and achieved its full power operation in January, 2003. Up to now, the HTR-10 has been successfully operated for more than ten years with different power levels. During the relatively long period of commissioning and operation, various kinds of tests were carried out on this reactor. Within the scope of this paper, the commissioning stage, the operation history and the test implementation of the HTR-10 are briefly summarized. At this stage, the HTR-10 is the only pebble bed HTGR under operation in the world, so the measured data from this reactor are extremely valuable for verifying the inherent safety features incorporated in small modular HTGRs as well as for testing the computer programs employed in the HTGR design process. With the purpose of ensuring the code credibility, validation work using the HTR-10 operation and test data has been performed for several years in INET. What is more, these data were partly shared with different countries through some collaborative research projects related to code development and assessment. In this paper, progress of the HTR-10 measured data utilization is reviewed. Meanwhile, existing problems observed from the code-to-test as well as code-to-code comparisons are pointed out. In addition, possible reasons of such problems are discussed in detail.

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