scholarly journals Test plan for phase-1 residential testing at the MIT/LL PV Systems Test Facility

1979 ◽  
Author(s):  
S. Sacco
Keyword(s):  
Phase 1 ◽  
Author(s):  
Fumihiko Kanayama

The Japan Atomic Energy Research Institute Reprocessing Test Facility (JRTF) was the first reprocessing facility which was constructed by applying only Japanese technology to establish basic technology on wet reprocessing. JRTF had been operated since 1968 to 1969 using spent fuels (uranium metal/aluminum clad, about 600kg as uranium metal and 600MWD/T) from the Japan Research Reactor No.3 (JRR-3). Reprocessing testings on PUREX process were implemented at 3 runs, so that, 200g of plutonium dioxide were extracted. After JRTF was shut down at 1970, it had been used for research and development of reprocessing since 1971. The more mature research and development of nuclear are, the more opportunity of dismantling of old nuclear facilities would be. Japan Atomic Energy Agency (JAEA) has an experience of full scale of dismantling through decommissioning of Japan Power Demonstration Reactor (JPDR)1). On the other hand, we didn’t have that of fuel cycle facility. Moreover, it is considered that dismantling methods of nuclear reactor and fuel cycle facility are different for following reason, components contaminated TRU nuclide including Pu, and components installed inside narrow cells. Dismantling methods are important factor to decide manpower and time for dismantling. So, it is indispensable to optimize dismantling method in order to minimize manpower and time for dismantling. Considering the background mentioned above, the decommissioning project of JRTF was started in 1990. The decommissioning project of JRTF is carried out phase by phase. Phase 1; Investigation for dismantling of the JRTF2)3)4). Phase 2; R&D of decommissioning technologies for dismantling of the JRTF5)6)7)8). Phase 3; Actual dismantling of the JRTF9)10). There were several components used for reprocessing and a system for liquid radwaste storage, and those were installed inside of each of several thick concrete cells. The inner surfaces of each cell were contaminated by TRU nuclides including Pu. In phase 3, components used in reprocessing and a system for liquid radwaste storage were dismantled. Moreover, opening was made in concrete walls (including ceiling) for this work. Effective practices for dismantling fuel cycle facilities were obtained through these works. On this report, effective dismantle methods obtained by actual dismantling activities in JRTF are introduced.


Author(s):  
M. Dohlus ◽  
K. Flöttmann ◽  
O.S. Kozlov ◽  
T. Limberg ◽  
Ph. Piot ◽  
...  
Keyword(s):  
Phase 1 ◽  

Author(s):  
Y. Takeda ◽  
K. Takigawa ◽  
H. Kobayashi ◽  
K. Nakahara ◽  
T. Morishita ◽  
...  

2006 ◽  
Vol 129 (3) ◽  
pp. 798-805 ◽  
Author(s):  
P. J. Maziasz ◽  
J. P. Shingledecker ◽  
N. D. Evans ◽  
Y. Yamamoto ◽  
K. L. More ◽  
...  

The Oak Ridge National Laboratory (ORNL) and ATI Allegheny Ludlum worked together on a collaborative program for about two years to produce a wide range of commercial sheets and foils of the new AL20-25+Nb™ (AL20–25+Nb) stainless alloy for advanced microturbine recuperator applications. There is a need for cost-effective sheets/foils with more performance and reliability at 650–750°C than 347 stainless steel, particularly for larger 200–250 kW microturbines. Phase 1 of this collaborative program produced the sheets and foils needed for manufacturing brazed plated-fin air cells, while Phase 2 provided foils for primary surface air cells, and did experiments on modified processing designed to change the microstructure of sheets and foils for improved creep-resistance. Phase 1 sheets and foils of AL20-25+Nb have much more creep-resistance than 347 steel at 700–750°C, and those foils are slightly stronger than HR120 and HR230. Results for Phase 2 showed nearly double the creep-rupture life of sheets at 750°C/100 MPa, and similar improvements in foils. Creep data show that Phase 2 foils of AL20-25+Nb alloy have creep resistance approaching that of alloy 625 foils. Testing at about 750°C in flowing turbine exhaust gas for 500 h in the ORNL Recuperator Test Facility shows that foils of AL20–25+Nb alloy have oxidation-resistance similar to HR120 alloy, and much better than 347 steel.


2012 ◽  
Vol 433-440 ◽  
pp. 6409-6413 ◽  
Author(s):  
Xiang Yang Zhao ◽  
Yu Jin

To verify the design of a standalone photovoltaic (PV) system, a test facility has been installed. This paper describes a platform to test the stand-alone solar system according to the IEC62124 standard. Essentially, this entire system involves the integration of a Personal Computer (PC), Data Acquisition (DAQ), an AC load and a solar array simulator (SAS) to test and simulate a stand-alone PV system. The main functions of this test facility are data acquisition, display, save and analysis data and print reports. The information obtained by monitoring parameters, such as average battery’s temperature, voltage and current is fed to the PC via the DAQ for analysis. This customized control interface has been developed by utilizing Labview software. This new system boasts of high accuracy measurements coupled with the commercial viability of low cost.


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