scholarly journals CONTAINMENT VESSEL LEAK RATE CRITERIA FOR A PROPOSED CANEL NUCLEAR TEST FACILITY

1964 ◽  
Author(s):  
E V Sandin
Keyword(s):  
Nuclear Test ◽  
Leak Rate ◽  
Test Facility ◽  
Containment Vessel

Experimental Evaluation of Wire Type Leak Detector Layout for Prototype Fast Breeder Reactor (PFBR)

2009 ◽  
Author(s):  
K. K. Rajan ◽  
G. Vijayakumar ◽  
S. Chandramouli ◽  
K. Madhusoodhanan ◽  
P. Kalyanasundaram ◽  
...  
Keyword(s):  
Test Section ◽  
Detection System ◽  
Leak Rate ◽  
Test Facility ◽  
Fast Breeder Reactor ◽  
Leak Detector ◽  
Secondary Circuit ◽  
Flow Area ◽  
Annular Gap ◽  
Set Up

Wire type leak detectors working on conductivity principle are used for detecting sodium leak in the secondary sodium circuits of FBRs. It is required to assess the performance of these detectors and confirm that they are meeting the requirements. A test facility by name LEENA was constructed at Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam to test the wire type leak detector lay out by simulating sodium leaks of different rates. This test facility consists of a sodium dump tank, a test vessel, interconnecting pipelines with valves, micro filter and test section with leak simulators. There are three different test sections in the test set up of length 1000 mm each. These test sections simulate piping of Prototype Fast Breeder Reactor (PFBR) secondary circuit and the leak detector layout in full scale. All test sections are provided with leak simulator. A leak simulator consists of a hole of size one mm drilled in the test section and closed with a tapered pin. The pin position is adjusted by a screw mechanism and there by the annular gap of flow area is varied for getting different leak rates. Test facility was commissioned and 20 experiments were attempted at 350°C to 550°C. Out of 20 experiments 11 experiments were successfully completed and 9 experiments were terminated in between due to the choke in the simulator hole. From the experimental data it is found that sodium leak rate of 200 g/h and above can be detected within 6 hours. A relationship between leak rate and detection time was established from the experimental results and found that sodium leak rate of 100g/h is likely to be detected in 11.4 hours. This paper deals with the details of wire type leak detector layout for the secondary sodium circuit of PFBR, performance requirement of leak detection system as per codes, description of test facility, experimental procedure and test results. Paper also reviews the experiment conducted in CEA, Cadrache and compares with results of present experimental study.

scholarly journals Satellite radar observation of large surface collapses induced by the 2017 North Korea nuclear test

2020 ◽  
Vol 10 (1) ◽  
Author(s):  
Won-Kyung Baek ◽  
Hyung-Sup Jung ◽  
Tae Sung Kim
Keyword(s):  
North Korea ◽  
Surface Deformation ◽  
Complex Surface ◽  
Nuclear Test ◽  
Test Facility ◽  
Deformation Pattern ◽  
Vertical Deformation ◽  
Horizontal Deformation ◽  
Maximum Deformation ◽  
The North

Abstract The artificial earthquake of mb 6.1 related to the North Korea’s sixth nuclear test occured at Mt. Mantap, North Korea on September 3, 2017. It was reported that a large and complex surface deformation was caused by the event. The surface deformation was composed of expansion of explosions, collapse, compaction and landslides. Since the precise vertical deformation measurement is very important to estimate the stability of the nuclear test facility, we retrieved a precise 3D surface deformation field and then decomposed the vertical deformation pattern from the 3D deformation. The measured maximum deformation was about − 491, − 343 and 166 cm with the measurement uncertainty of about 3.3, 4.1 and 2.7 cm in the east, north and up directions, respectively. The maximum horizontal deformation was approximately 515 cm. The horizontal deformation clearly showed a radial pattern because it was mainly caused by the explosions and landslides, while the vertical deformation displayed a rugged pattern because it was affected by the explosions, compaction and collapse. The collapse may seem to occur along the underground tunnels and at the test site’s epicenter as well. Moreover, the severe collapse was observed westside from the epicenter of the sixth nuclear test, and it has a depth of about 68.6 cm on the area of 0.3765 km2. On the basis of our results including the shapes, locations and volume changes of the large collapse, evidently a new vital piece of information was obtained so that it could be used to interprete the sixth nuclear test more accurately.

Investigation of Leakage Rates in Pressure Retaining Piping

2017 ◽  
Author(s):  
Fabian E. Silber ◽  
Xaver Schuler ◽  
Stefan Weihe ◽  
Eckart Laurien ◽  
Rudi Kulenovic ◽  
...  
Keyword(s):  
Power Plants ◽  
Leak Detection ◽  
Operating Conditions ◽  
Leak Rate ◽  
Test Facility ◽  
Experimental Investigations ◽  
Two Phase ◽  
Detection Systems ◽  
Test Loop ◽  
Calculation Models

Within the break preclusion concept, leak-before-break (LBB) behavior must be demonstrated for safety relevant pressure retaining piping systems in nuclear power plants (NPP) [1]. This requires leak detection systems in NPP with the capability to detect leak rates below the maximum allowable leak rate calculated by the LBB assessment according to nuclear standards, like the German KTA rule 3206 or the U.S. Standard Review Plan (SRP). An important part of the LBB assessment is the availability of accurate calculation models to predict the leak rate under normal operating conditions for postulated through wall cracks. Current leak detection systems in NPP are capable of reliably detecting liquid leak rates 0.05 kg/s. However, most of the available experimental leak rate data published in literature focus on the range between 0.2 kg/s and 2 kg/s, which is significantly above the detection limit. Therefore, additional experimental investigations are necessary to develop and verify leak rate calculation models for smaller leaks. In order to investigate such types of leaks, a modular test facility (fluid-structure-interaction test loop) has been developed and installed at MPA University of Stuttgart within the framework of a research project sponsored by the German Ministry of Education and Research (BMBF). The test rig includes a leakage piping module which includes artificially machined slits and fatigue through-wall cracks. It allows the variation of the significant influencing parameters such as crack size, surface roughness and the system parameters pressure and temperature up to 75 bar and 280 °C and also the measurement of the pressure gradient across the crack surface at two locations. This is important to develop a better understanding of the two-phase flow and pressure drop across the leak channel. A first test series has been performed and the results were used to evaluate existing leak-rate models. Within this paper an overview of the test facility, the testing procedure, and the results of the investigations will be presented and discussed.

scholarly journals New challenge to nuclear test facility

Nature ◽  
1997 ◽  
Vol 386 (6624) ◽  
pp. 427-427
Author(s):  
Colin Macilwain
Keyword(s):  
Nuclear Test ◽  
Test Facility
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