scholarly journals Preliminary irradiation test results from the Yankee Atomic Electric Company reactor vessel test irradiation program

1994 ◽  
Vol 60 (3) ◽  
pp. 259-269
Author(s):  
Eric C Biemiller ◽  
Stephen Fyfitch ◽  
Christine A Campbell
Keyword(s):  
Reactor Vessel ◽  
Test Results ◽  
Electric Company ◽  
Irradiation Test ◽  
Preliminary Irradiation

Analysis of Heavy Ion Irradiation Test Results on Power Diodes

2018 ◽  
Author(s):  
M. Mauguet ◽  
L. Azema ◽  
E. Le Goulven ◽  
A. Varotsou ◽  
X. Marie ◽  
...  
Keyword(s):  
Ion Irradiation ◽  
Heavy Ion ◽  
Test Results ◽  
Power Diodes ◽  
Heavy Ion Irradiation ◽  
Irradiation Test

An Improved Test Facility for Studying Deposit Fouling on Steam Turbine Blades

2016 ◽  
Author(s):  
Alan R. May Estebaranz ◽  
Richard J. Williams ◽  
Simon I. Hogg ◽  
Philip W. Dyer
Keyword(s):  
Turbine Blades ◽  
Steam Pressure ◽  
Reactor Vessel ◽  
Test Facility ◽  
Test Results ◽  
Steam Turbines ◽  
Steam Power ◽  
Scale Test ◽  
Steam Turbine Blades ◽  
Asme Paper

A laboratory scale test facility has been developed to investigate deposition in steam turbines under conditions that are representative of those in steam power generation cycles. The facility is an advanced two-reactor vessel test arrangement, which is a more flexible and more accurately controllable refinement to the single reactor vessel test arrangement described previously in ASME Paper No. GT2014-25517 [1]. The commissioning of the new test facility is described in this paper, together with the results from a series of tests over a range of steam conditions, which show the effect of steam conditions (particularly steam pressure) on the amount and type of deposits obtained. Comparisons are made between the test results and feedback/experience of copper fouling in real machines.

scholarly journals Accelerated irradiation test of Gundremmingen reactor vessel trepan material

1992 ◽  
Author(s):  
J.R. Hawthorne
Keyword(s):  
Reactor Vessel ◽  
Irradiation Test

Evaluation of Laser Peening for Mitigation of Primary Water Stress Corrosion Cracking in Pressurized Water Reactors

2019 ◽  
Author(s):  
Stephen Marlette ◽  
Stan Bovid
Keyword(s):  
Surface Stress ◽  
Reactor Vessel ◽  
Pressurized Water Reactors ◽  
Laser Peening ◽  
Alloy 600 ◽  
Test Results ◽  
Pressurized Water ◽  
Performance Requirements ◽  
Primary Water ◽  
Water Reactors

Abstract For several decades pressurized water reactors have experienced Primary Water Stress Corrosion Cracking (PWSCC) within Alloy 600 components and welds. The nuclear industry has developed several methods for mitigation of PWSCC to prevent costly repairs to pressurized water reactor (PWR) components including surface stress improvement by peening. Laser shock peening (LSP) is one method to effectively place the surface of a PWSCC susceptible component into compression and significantly reduce the potential for crack initiation during future operation. The Material Reliability Program (MRP) has issued MRP-335, which provides guidelines for effective mitigation of reactor vessel heads and nozzles constructed of Alloy 600 material. In addition, ASME Code Case N-729-6 provides performance requirements for peening processes applied to reactor vessel head penetrations in order to prevent degradation and take advantage of inspection relief, which will reduce operating costs for nuclear plants. LSP Technologies, Inc. (LSPT) has developed and utilized a proprietary LSP system called the Procudo® 200 Laser Peening System. System specifications are laser energy of 10 J, pulse width of 20 ns, and repetition rate of 20 Hz. Scalable processing intensity is provided through automated focusing optics control. For the presented work, power densities of 4 to 9.5 GW/cm2 and spot sizes of nominally 2 mm were selected. This system has been used effectively in many non-nuclear industries including aerospace, power generation, automotive, and oil and gas. The Procudo® 200 Laser Peening System will be used to process reactor vessel heads in the United States for mitigation of PWSCC. The Procudo® 200 Laser Peening System is a versatile and portable system that can be deployed in many variations. This paper presents test results used to evaluate the effectiveness of the Procudo® 200 Laser Peening System on Alloy 600 material and welds. As a part of the qualification process, testing was performed to demonstrate compliance with industry requirements. The test results include surface stress measurements on laser peened Alloy 600, and Alloy 182 coupons using x-ray diffraction (XRD) and crack compliance (slitting) stress measurement techniques. The test results are compared to stress criteria developed based on the performance requirements documented in MRP-335 and Code Case N-729-6. Other test results include surface roughness measurements and percent of cold work induced by the peening process. The test results demonstrate the ability of the LSP process to induce the level and depth of compression required for mitigation of PWSCC and that the process does not result in adverse conditions within the material.

scholarly journals LISA PathFinder radiation monitor proton irradiation test results

2012 ◽  
Vol 363 ◽  
pp. 012050 ◽  
Author(s):  
I Mateos ◽  
M Diaz-Aguiló ◽  
F Gibert ◽  
C Grimani ◽  
D Hollington ◽  
...  
Keyword(s):  
Proton Irradiation ◽  
Test Results ◽  
Radiation Monitor ◽  
Lisa Pathfinder ◽  
Irradiation Test

Pressure Fluctuations and Fatigue Stresses in Storage Pumps and Pump-Turbines

1964 ◽  
Vol 86 (2) ◽  
pp. 191-194 ◽  
Author(s):  
R. A. Strub
Keyword(s):  
Pressure Fluctuations ◽  
Full Scale ◽  
Development Work ◽  
Test Results ◽  
Pump Turbine ◽  
Blade Passage ◽  
Joint Development ◽  
Electric Company ◽  
Peripheral Speed ◽  
Two Machines

Similarity is shown between a model and a full scale pump or pump-turbine in the static and dynamic fields of stress and in the vibration characteristics, if the peripheral speed of rotation and the material used for the blades are the same for the two machines. Simple formulas are derived for predicting phase coincidence of the pressure fluctuations caused by the blade passage of the runner rotating in a diffuser. Test results are shown which confirm the established theory. This work was made as part of a joint development work on pump-turbine by Sulzer Brothers, Ltd., and English Electric Company.

Experimental and Analytical Studies on Penetration Integrity of the Reactor Vessel Under External Vessel Cooling

2002 ◽  
Author(s):  
Rae-Joon Park ◽  
Kyoung-Ho Kang ◽  
Jong-Tae Kim ◽  
Kil-Mo Koo ◽  
Sang-Baik Kim ◽  
...  
Keyword(s):  
Power Reactor ◽  
Effective Means ◽  
Computer Code ◽  
Reactor Vessel ◽  
Severe Accident ◽  
Test Results ◽  
Analytical Studies ◽  
System Pressure ◽  
Lower Head ◽  
Analysis Computer

Experimental and analytical studies on the penetration integrity of the reactor vessel in the APR (Advanced Power Reactor) 1400 have been performed under the condition of external vessel cooling in a severe accident. The objective of this study is to estimate failure or non-failure of the penetration including the ICI (In-Core Instrumentation) nozzle and the thimble tube. Five tests in conditions with and without external vessel cooling have been performed to estimate the effects of system, corium mass, and vessel geometry using alumina (Al2O3) melt as a simulant. The test results have been evaluated using the LILAC (Lower head IntegraL Analysis computer Code). The tests results have shown that penetration in the no external vessel cooling case is more damaged than that in the external vessel cooling case. An increase in system pressure from 0.9 MPa to 1.5 MPa was not effective on penetration damage, but an increase in corium mass from 40 kg to 60 kg and a vessel geometry change to flat plate with curvature were effective. The LILAC results are very similar to the test results on the ablation depth in the weld. It is concluded that external vessel cooling is a very effective means for maintaining penetration integrity.

scholarly journals First irradiation test results of the ALICE SAMPA ASIC

2018 ◽  
Author(s):  
Sohail Musa Mahmood ◽  
Ketil Roeed ◽  
Fredrik Lindseth Winje ◽  
Arild Velure ◽  
Keyword(s):  
Test Results ◽  
Irradiation Test
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