Luminescent Oxygen Sensor for Monitoring of Nuclear Primary Water Cycles

Size: px
Start display at page:

Download "Luminescent Oxygen Sensor for Monitoring of Nuclear Primary Water Cycles"

Transcription

1 Luminescent Oxygen Sensor for Monitoring of Nuclear Primary Water Cycles Frank A. Dunand Nicolas Ledermann Serge Hediger Max Haller Christoph Weber ABSTRACT When we introduced a luminescent sensor to measure dissolved oxygen in water and steam cycles at the end of last year, a number of questions regarding its use in nuclear power plant applications remained open. The issues to be investigated were the behavior in the presence of hydrogen and the effect of radiation on the luminescent sensor. In collaboration with the Mühleberg Nuclear Power Plant in Switzerland a series of tests on the reactor water and the feedwater were performed to demonstrate the performance of the sensor in typical nuclear applications. In addition the system was exposed to high radiation intensities to validate the robustness of the sensor in a nuclear power plant environment. INTRODUCTION In a recent paper, we presented the first luminescent oxygen sensor applicable to monitoring the water and steam cycle []. The use of luminescent technology brings significant improvements in terms of frequency and complexity of maintenance compared with commonly used electrochemical (EC) sensors. Furthermore no particular attention has to be paid to the sample flow, and abnormally high oxygen levels have no influence on the maintenance frequency. The simplification of the maintenance and sensor preparation combined with the automation of the single point calibration renders the accuracy of the system literally operator independent. Whereas the current accuracy and detection limit of this luminescent sensor are probably not yet ideal for process monitoring requiring sub µg kg accuracy at low levels (< 5 µg kg ), it appears to be the best solution for oxygen process monitoring in plants running oxygen treatment 2007 by PowerPlantChemistry GmbH. All rights reserved. (OT) chemistry and a very good compromise of accuracy, reliability, and maintenance requirements for plants running all-volatile treatment (AVT) and working shifts with frequent contact with high oxygen containing samples. Dissolved oxygen monitoring in nuclear power plants (NPP) has the same purpose as in fossil-fueled power plants, but some applications are slightly different in essence. In this paper we will only consider the most common light water reactors (LWR): pressurized water reactors (PWR or VVER) and boiling water reactors (BWR). We will not discuss here the evolution of the different types of chemistries used in PWR or BWR reactors as this has been described in detail elsewhere [2 4]. In a PWR we have to distinguish between the primary circuit or reactor coolant system (RCS) and the secondary loop. In the primary circuit hydrogen is added, which maintains reductive conditions leading to oxygen concentrations far below 0 µg kg. Dissolved oxygen is monitored continuously in order to quickly detect any changes in the cooling system chemistry. The secondary circuit can be compared to a standard fossil power plant running AVT chemistry. Typical oxygen monitoring applications in the secondary loop include the feedwater (< 0 µg kg ), the condensate (< 30 µg kg ) and the deaerator inlet and outlet (0 30 µg kg ) [3,5]. In BWR reactors the water/steam circuit that generates power is in direct contact with the reactor. The original chemistry used in these reactors is the so-called normal water chemistry (NWC). This is very pure, slightly oxygenated water ( µg kg ) at neutral ph. As intergranular stress corrosion cracking (IGSCC) was observed under these conditions, hydrogen water chemistry (HWC) was then developed. In this chemistry, µg kg hydrogen is added to the feedwater to change the oxidizing nature of the coolant that causes IGSCC. The drawback of this method is the increase in the main steam radiation levels. However, this can be mitigated by the addition of a catalyst that helps the recombination of hydrogen with oxygen and oxygen peroxide in the reactor. This technique is called nobel metal chemical addition (NMCA). With this method, the hydrogen content of the feedwater can be limited to around µg kg whereas the hydrogen and oxygen contents in the reactor water are very low (dissolved H 2 < 50 µg kg and dissolved oxygen < µg kg ) [4,6 8]. Independent of the application, nuclear power plants do of course require very accurate monitoring of the oxygen levels all along the water cycle, but one of the most important 58 PowerPlant Chemistry 2007, 9(9)

2 Luminescent Oxygen Sensor for Monitoring of Nuclear Primary Water Cycles requirements in this industry is the As Low As Reasonably Achievable (ALARA) principle for operator exposure to radiation. Although our luminescent oxygen system has proven its capability in fossil power plants where the operator intervention is limited to a 5 min service every 8 months, there was still a question mark regarding the influence of radiation and hydrogen on the measurement using luminescent technology. The goal of this paper is to demonstrate whether our luminescent dissolved oxygen analyzer can be used in nuclear applications. THE BWR OF MÜHLEBERG NUCLEAR POWER PLANT All on-site tests were performed in the nuclear power plant Mühleberg (KKM) close to Bern, Switzerland. Mühleberg nuclear reactor is of type GE BWR 4 and was commissioned in 972. The installed power is 355 MW and the annual energy produced is GWh. The plant runs under hydrogen water chemistry (HWC) conditions with NMCA [6]. The 4 m 3 h (STP) of H 2 injected into the feedwater is generated by a polymer electrolyte membrane (PEM) that electrochemically produces H 2 and O 2 from water [9]. Dissolved oxygen is continuously monitored in the reactor water and the feedwater. During these tests, the luminescent oxygen analyzer was installed at both the reactor water and feedwater sampling points as shown in Figure. OXYGEN MONITORING OF THE REACTOR WATER The ORBISPHERE G200 luminescent oxygen sensor was first installed for more than 0 days on the reactor water sampling line near an originally installed ORBISPHERE electrochemical (EC) sensor. Under NWC conditions, the oxygen level in the reactor water would rise up to µg kg due to the radiolysis of the water. In order to limit the oxygen concentration to below µg kg, hydrogen is injected into the feedwater. The hydrogen level in the reactor water is around 2 µg kg. The radiation level at the reactor water sampling point is about 60 µsv h. To start the test, a zero calibration with pure nitrogen gas was performed and the auto-calibration feature was programmed to run a zero calibration every 5 days in order to observe the reproducibility of the calibration procedure in those conditions. The system required no intervention after initial installation. Figure 2 shows an example of the dissolved oxygen data recorded by the G200 system between day #55 and #6 (6 days). Over the full test duration the G200 successfully measured the process at low dissolved oxygen concentrations with expected ±2 µg kg accuracy. On day #58, one of the programmed auto-calibrations took place, confirming the effectiveness of the calibration procedure and validating the accuracy of this low level Figure : KKM reactor with oxygen sampling point positions. The first sampling point is the reactor water (< µg kg dissolved oxygen); the second measures the feedwater (oxygen content 50 µg kg ). Both water samples are exposed to radiation and contain H 2. PowerPlant Chemistry 2007, 9(9) 59

3 measurement. On day #59, a small oxygen peak was generated manually by a slight oxygen injection on the sampling line in order to test whether the system would react properly. Figure 3 shows that the luminescent oxygen sensor successfully tracked this slight oxygen concentration change up to 60 µg kg. The accuracy of the luminescent sensor is excellent as the difference between the EC and the G200 is less than 2 3 µg kg oxygen on average. OXYGEN MONITORING OF THE FEEDWATER The same luminescent oxygen analyzer was plugged into the feedwater sampling line for 40 days. As depicted in Figure, oxygen treatment (OT) is applied just after the condensate pump. The average dissolved oxygen level is about 50 µg kg but can range between 30 and 200 µg kg. The OT process is identical to that found in fossil power plants, where the ORBI- SPHERE G00 system has proven its capability. It is of primary interest to see if radiation and hydrogen have an influence on the measurements of the luminescent sensor. In the feedwater, the radiation level is lower, with a measured value of 55 µsv h near the sampling point. The H 2 set point is 80 µg kg, corresponding to 4 m 3 h (STP) hydrogen gas injection. Figure 4 shows the feedwater sampling panel with the luminescent oxygen sensor, the existing ORBISPHERE oxygen electrochemical (EC) sensor and a hydrogen thermal-conductivity (TC) sensor. Figure 2: ORBISPHERE G200 data recorded during 6 days of a 0-day trial in the reactor water with dissolved oxygen concentration of < 2 µg kg. Figure 5 shows the results of the ORBISPHERE 3600 EC and the ORBISPHERE G200 recorded during the last week of a 40-day trial Figure 3: on the feedwater line. During this test again no intervention was necessary and all calibrations were done on automatic mode. On days #33 and #37, the luminescent sensor successfully detected two small and brief oxygen peaks that occurred due to startup of a precoat filter. Over the 39 days of the test, we programmed 9 auto-calibrations to verify the calibration reproducibility. All calibrations successfully took place, taking only 3.7 min on average. Their reproducibility was within the expected ±2 µg kg oxygen accuracy. HIGH RADIATION LEVEL RESISTANCE After 0 days of operation in the reactor water (at 60 µsv h ) and 40 days in the feedwater (at Comparison between an ORBISPHERE 3600 electrochemical (EC) sensor and the ORBISPHERE G200 dissolved oxygen measurements during small oxygen peak. 55 µsv h ), the radiation resistance of the G200 sensor was further tested by exposing the probe to a high intensity radioactive source (up to Gy h = Sv h with quality factor = ) for h. Data were recorded by the G200 sensor, while measuring pure gaseous nitrogen. Neither degradation nor influence of radiation was observed on the auto-calibration process, on the sensor repeatability (± µg kg ) or on the fluorescence signal intensity (Table ). Based on the radiation level in the KKM reactor water (60 µsv h ) and in the feedwater (55 µsv h ), this high 520 PowerPlant Chemistry 2007, 9(9)

4 Heft :59 Uhr Seite 52 Luminescent Oxygen Sensor for Monitoring of Nuclear Primary Water Cycles Radiation Test Zero DO repeat- Fluorescence level duration calibration ability intensity (Gy h )* (h) (µg kg ) (V) OK.74 OK.70 Table : G200 functional testing under high radiation levels. * = Sv h with quality factor = DO dissolved oxygen radiation test is equivalent, in terms of cumulated dose, to a system running for 9 and 27 months respectively. Over the complete trial, the G200 luminescent sensor was exposed to a cumulated radiation exposure of about 2 Gy without any loss of sensor performance. EFFECT OF HYDROGEN No measurable effect of hydrogen was observed during the above described tests at the Mühleberg NPP. Additional laboratory tests performed on 00 % hydrogen samples have shown no interference on the luminescent sensor signal. This has been confirmed by the measurement on stator cooling water, which is normally saturated with hydrogen (i.e., dissolved hydrogen levels in the mg kg range). Figure 6 shows a 0-day data extract from a 5-month test on a stator cooling water loop from a UK power plant. The G200 sensor was very consistent and stable in measuring the stator water with typical dissolved oxygen concentration below 0 µg kg, giving further proof of its insensitivity to hydrogen. Figure 4: Feedwater sampling panel, originally equipped with O2 ORBISPHERE EC sensor and H2 ORBISPHERE TC sensor, with ORBISPHERE G200 sensor at the bottom right. Sampling point Feedwater on Figure. CONCLUSION Laboratory and field tests of the ORBISPHERE G200 luminescent dissolved oxygen sensor have shown that the sensor is not influenced by the presence of radiation or hydrogen in the sample. As the maintenance of this analyzer being limited to the annual exchange of the active luminescent spot, the operator will be able to drastically reduce his exposure to radiation and therefore his annual cumulated dose. Based on its 2 µg kg accuracy and reproducibility, this system is perfectly suited to monitoring the water and steam cycle in BWR plants running NWC, HWC, or NMCA chemistries as well as the condensate in PWR plants. The use of the analyzer on the reactor water of BWRs, RCS of PWRs and feedwater of PWR PowerPlant Chemistry 2007, 9(9) Figure 5: Data recorded by the G200 and EC sensors during the last 8 days of a 40-day trial in the FW. The difference between the EC and luminescent oxygen sensors is lower than 5 µg kg. The small oxygen peaks on days #33 and #37 were due to startup of a precoat filter. 52

5 plants where the dissolved oxygen level is typically below 5 µg kg will depend on the level of oxygen at which an alarm is released and an action should be taken. The system is clearly not applicable if the alarm level is at 5 µg kg of dissolved oxygen but can be effectively used if the alarm is set at a dissolved oxygen concentration of 0 µg kg or above. ACKNOWLEDGMENTS The authors warmly thank the Gx00 development team, T. Chatelain, D. Rosset, P. Vauclin, A. Doux, S. Orlandini and Y. Kestin for their efforts and enthusiasm. REFERENCES [] Dunand, F., Ledermann, N., Hediger, S., PowerPlant Chemistry 2006, 8(0) 2. [2] Bain, D. I., Bates, J., Ultrapure Water online 2004, May/June, UP20449, Part. [3] Bain, D. I., Bates, J., Ultrapure Water online 2004, September, UP20449, Part 2. [4] Fruzzetti, K., Wood, C. J., PowerPlant Chemistry 2007, 9(4) 209. [5] Böttcher, F., CD-ROM Proc., International Conference Instrumentation for PowerPlant Chemistry, 2006 (Zurich, Switzerland). PowerPlant Chemistry GmbH, Neulussheim, Germany. [6] Sarott, F. A., CHIMIA 2005, 59(2), 923. [7] Seifert, H. P., Ritter, S., CHIMIA 2005, 59(2), 944. [8] Stellwag, B., Staudt, U., PowerPlant Chemistry 2005, 7(2), 95. [9] Puthawala, A., Henzel, N., PowerPlant Chemistry 2000, 2(3), 72. THE AUTHORS Figure 6: Frank A. Dunand (Ph.D., Chemistry, Swiss Federal Institute of Technology, Lausanne, Switzerland; M.S., Chemistry, University of Fribourg, Switzerland) authored 5 technical papers in the analytical chemistry field before joining Orbisphere in He currently holds a position as senior product manager at Hach Ultra, heading the team managing all Orbisphere and Polymetron products. Nicolas Ledermann (Ph.D. and M.S., Materials Science, Swiss Federal Institute of Technology, Lausanne, Switzerland) has authored and co-authored 25 scientific 0 days of stator water monitoring from a UK power plant with the G200 sensor. papers in the field of applied materials science, MEMS and sensor design. He is presently R&D manager at Hach Ultra Analytics, Geneva, heading the sensor development group. He is a member of IEEE and the Materials Research Society. Serge Hediger (Ph.D., Micro-engineering, Swiss Federal Institute of Technology, Lausanne, Switzerland; M.S., Micro-engineering, Swiss Federal Institute of Technology, Lausanne, Switzerland) authored 6 technical papers in the micro-engineering field before joining Orbisphere in He currently holds a position as R&D engineer at Hach Ultra in the sensor development group. Christoph Weber (Ph.D., Chemistry, Ruprecht Karls Universität Heidelberg, Germany) is the division manager for chemistry at the Nuclear Power Plant Mühleberg, Switzerland. Max Haller (Chemical Engineer) is a senior laboratory engineer with more than 36 years of experience in onlineinstrumentation and analysis at the Nuclear Power Plant Mühleberg. CONTACT Frank A. Dunand Hach Ultra Analytics SA 6, Rte de Compois CP 22 CH-222 Vésenaz Switzerland fdunand@hachultra.com 522 PowerPlant Chemistry 2007, 9(9)

Research Program on Water Chemistry of Supercritical Pressure Water under Radiation Field

Research Program on Water Chemistry of Supercritical Pressure Water under Radiation Field 14th International Conference on the Properties of Water and Steam in Kyoto Research Program on Water Chemistry of Supercritical Pressure Water under Radiation Field Yosuke Katsumura 1, Kiyoshi Kiuchi

More information

Water Chemistry. Program Overview

Water Chemistry. Program Overview Water Chemistry Program Description Program Overview Water chemistry conditions at nuclear power plants can impact corrosion rates, fuel performance, and radiation management. In light of increasing demands

More information

Review of the primary coolant chemistry at NPP Temelín and its impact on the fuel cladding

Review of the primary coolant chemistry at NPP Temelín and its impact on the fuel cladding Review of the primary coolant chemistry at NPP Temelín and its impact on the fuel cladding M. Mikloš, K. Vonková, J. Kysela Research Centre Řez Ltd, 250 68 Řež, Czech Republic D. Ernst NPP Temelín, Reactor

More information

Electric Power Research Institute. Water Chemistry. Program Overview

Electric Power Research Institute. Water Chemistry. Program Overview Water Chemistry Program Description Program Overview Water chemistry conditions at nuclear power plants can impact corrosion rates, fuel performance, and radiation management. In light of increasing demands

More information

The Effect of Hydrazine Addition on the Formation of Oxygen Molecule by Fast Neutron Radiolysis

The Effect of Hydrazine Addition on the Formation of Oxygen Molecule by Fast Neutron Radiolysis International Conference on Nuclear Energy Technologies and Sciences (2015), Volume 2016 Conference Paper The Effect of Hydrazine Addition on the Formation of Oxygen Molecule by Fast Neutron Radiolysis

More information

SOME ASPECTS OF COOLANT CHEMISTRY SAFETY REGULATIONS AT RUSSIA S NPP WITH FAST REACTORS

SOME ASPECTS OF COOLANT CHEMISTRY SAFETY REGULATIONS AT RUSSIA S NPP WITH FAST REACTORS Federal Environmental, Industrial and Nuclear Supervision Service Scientific and Engineering Centre for Nuclear and Radiation Safety Scientific and Engineering Centre for Nuclear and Radiation Safety Member

More information

Young Researchers Meeting 2012

Young Researchers Meeting 2012 Karen Verrall Date: 27/03/12 Career History Berkeley Nuclear Labs (BNFL Magnox Generation) Environmental & Effluent Monitoring / Waste Radiochemistry Electric Power Research Institute (EPRI) PWR Chemistry

More information

Structural Health Monitoring of Nuclear Power Plants using Inverse Analysis in Measurements

Structural Health Monitoring of Nuclear Power Plants using Inverse Analysis in Measurements Structural Health Monitoring of Nuclear Power Plants using Inverse Analysis in Measurements Fumio Kojima Organization of Advanced Science and Technology, Kobe University 1-1, Rokkodai, Nada-ku Kobe 657-8501

More information

The exergy of asystemis the maximum useful work possible during a process that brings the system into equilibrium with aheat reservoir. (4.

The exergy of asystemis the maximum useful work possible during a process that brings the system into equilibrium with aheat reservoir. (4. Energy Equation Entropy equation in Chapter 4: control mass approach The second law of thermodynamics Availability (exergy) The exergy of asystemis the maximum useful work possible during a process that

More information

Characterization of Large Structures & Components

Characterization of Large Structures & Components Structures & Components KEY BENEFITS Key Drivers: Lack of good knowledge about the position, the identification and the radiological specification of contamination on or inside large components. Significant

More information

Understanding ph Troubleshooting and Diagnostic information

Understanding ph Troubleshooting and Diagnostic information Understanding ph Troubleshooting and Diagnostic information The desire is to achieve an accurate, reliable measurement with a reasonable electrode life expectancy while minimizing frequency or complexity

More information

Integrated Catalyst System for Removing Buildup-Gas in BWR Inert Containments During a Severe Accident

Integrated Catalyst System for Removing Buildup-Gas in BWR Inert Containments During a Severe Accident GENES4/ANP2003, Sep. 15-19, 2003, Kyoto, JAPAN Paper 1084 Integrated Catalyst System for Removing Buildup-Gas in BWR Inert Containments During a Severe Accident Kenji Arai *, Kazuo Murakami, Nagayoshi

More information

Evaluating the Safety of Digital Instrumentation and Control Systems in Nuclear Power Plants

Evaluating the Safety of Digital Instrumentation and Control Systems in Nuclear Power Plants Evaluating the Safety of Digital Instrumentation and Control Systems in Nuclear Power Plants John Thomas With many thanks to Francisco Lemos for the nuclear expertise provided! System Studied: Generic

More information

Successful Development of a New Catalyst for Efficiently Collecting Tritium in Nuclear Fusion Reactors

Successful Development of a New Catalyst for Efficiently Collecting Tritium in Nuclear Fusion Reactors January 15, 2015 Japan Atomic Energy Agency Tanaka Precious Metals Tanaka Holdings Co., Ltd. Successful Development of a New Catalyst for Efficiently Collecting Tritium in Nuclear Fusion Reactors World

More information

12 Moderator And Moderator System

12 Moderator And Moderator System 12 Moderator And Moderator System 12.1 Introduction Nuclear fuel produces heat by fission. In the fission process, fissile atoms split after absorbing slow neutrons. This releases fast neutrons and generates

More information

Sensor for dissolved hydrogen with in-line calibration in aqueous media

Sensor for dissolved hydrogen with in-line calibration in aqueous media Sensor for dissolved hydrogen with in-line calibration in aqueous media by Uwe Gronowski 1 Introduction Hydrogen is becoming increasingly important as a process component in various areas of technology,

More information

Step 2 Assessment of the Reactor Chemistry of Hitachi GE s UK Advanced Boiling Water Reactor (UK ABWR)

Step 2 Assessment of the Reactor Chemistry of Hitachi GE s UK Advanced Boiling Water Reactor (UK ABWR) GDA Step 2 Assessment of the Reactor Chemistry of Hitachi GE s UK Advanced Boiling Water Reactor (UK ABWR) Civil Nuclear Reactor Build - Generic Design Assessment Step 2 Assessment of the Reactor Chemistry

More information

Title: Development of a multi-physics, multi-scale coupled simulation system for LWR safety analysis

Title: Development of a multi-physics, multi-scale coupled simulation system for LWR safety analysis Title: Development of a multi-physics, multi-scale coupled simulation system for LWR safety analysis Author: Yann Périn Organisation: GRS Introduction In a nuclear reactor core, different fields of physics

More information

ISEmax CAM40/CAS40. Technical Information

ISEmax CAM40/CAS40. Technical Information Technical Information Online measurement of nutrient parameters Ion-selective electrode system for the continuous measurement of ammonium and nitrate Application The ion-selective electrode system works

More information

DISCLAIMER. Portions of this document may be illegible in electronic image products. Images are produced from the best available original document.

DISCLAIMER. Portions of this document may be illegible in electronic image products. Images are produced from the best available original document. ; i i : L4 0 t DSCLAMER Portions of this document may be illegible in electronic image products. mages are produced from the best available original document. EVALUATON OF THE HUMDFCATON REQTJREMENTS OF

More information

Department of Engineering and System Science, National Tsing Hua University,

Department of Engineering and System Science, National Tsing Hua University, 3rd International Conference on Materials Engineering, Manufacturing Technology and Control (ICMEMTC 2016) The Establishment and Application of TRACE/CFD Model for Maanshan PWR Nuclear Power Plant Yu-Ting

More information

IAPWS International Conference on Film Forming Substances. NH Hotel, Prague City, Czech Republic. Agenda / Programme

IAPWS International Conference on Film Forming Substances. NH Hotel, Prague City, Czech Republic. Agenda / Programme IAPWS International Conference on Film Forming Substances NH Hotel, Prague City, Czech Republic Agenda / Programme Day 1 Tuesday, 20 th March 2018. FFS2018 Agenda 8:00 Registration and Welcome Coffee /

More information

Data acquisition system for optimization and control of the processes from an isotopic exchange column

Data acquisition system for optimization and control of the processes from an isotopic exchange column Data acquisition system for optimization and control of the processes from an isotopic exchange column C. M. Retevoi, I. Stefan, A. Bornea & O. Balteanu National Institute of Research-Development for Cryogenic

More information

IMPROVEMENTS OF THERMAL RESPONSE TESTS FOR GEOTHERMAL HEAT PUMPS

IMPROVEMENTS OF THERMAL RESPONSE TESTS FOR GEOTHERMAL HEAT PUMPS - 1 - IMPROVEMENTS OF THERMAL RESPONSE TESTS FOR GEOTHERMAL HEAT PUMPS R. Wagner, E. Rohner, Geowatt AG, Dohlenweg 28, CH-8050 Zürich Abstract: At present, the ground thermal conductivity at borehole heat

More information

Modelling fuel cells in start-up and reactant starvation conditions

Modelling fuel cells in start-up and reactant starvation conditions Modelling fuel cells in start-up and reactant starvation conditions Brian Wetton Radu Bradean Keith Promislow Jean St Pierre Mathematics Department University of British Columbia www.math.ubc.ca/ wetton

More information

IEC Tritium Standard

IEC Tritium Standard detect and identify IEC 62303 Tritium Standard Dr. Alfred Klett Berthold Technologies, Bad Wildbad, Germany 21 st Annual Air Monitoring Users Group (AMUG) Meeting Palace Station Hotel, Las Vegas, Nevada,

More information

Employees Contractors

Employees Contractors Attachment Exposure Dose Distribution 1. Effective Dose from External Exposure Table 1 shows the distribution of external exposure dose of workers who were involved in radiation work at the Fukushima Daiichi

More information

Chemistry Portfolio Development Research Focus Area Prioritization

Chemistry Portfolio Development Research Focus Area Prioritization 2016-2017 Chemistry Portfolio Development Research Focus Area Prioritization Rick Reid EPRI Program Manager Technical Advisory Committee Webcast May 27, 2015 15:00-17:00 EDT Conference line: 888-236-5213

More information

SPECIAL PRINT AMI CACE. Conventional Resin Cation Exchangers versus EDI for CACE Measurements An Ion Chromatography Study

SPECIAL PRINT AMI CACE. Conventional Resin Cation Exchangers versus EDI for CACE Measurements An Ion Chromatography Study Julia Gath, Heini Maurer, and Heinz Wagner SWAN Analytische Instrumente AG, 834 Hinwil/Switzerland Acid conductivity monitoring No more resin changing required AMI CACE SPECIAL PRINT PowerPlant Chemistry

More information

Radiation Damage Effects in Solids. Los Alamos National Laboratory. Materials Science & Technology Division

Radiation Damage Effects in Solids. Los Alamos National Laboratory. Materials Science & Technology Division Radiation Damage Effects in Solids Kurt Sickafus Los Alamos National Laboratory Materials Science & Technology Division Los Alamos, NM Acknowledgements: Yuri Osetsky, Stuart Maloy, Roger Smith, Scott Lillard,

More information

The Research of Heat Transfer Area for 55/19 Steam Generator

The Research of Heat Transfer Area for 55/19 Steam Generator Journal of Power and Energy Engineering, 205, 3, 47-422 Published Online April 205 in SciRes. http://www.scirp.org/journal/jpee http://dx.doi.org/0.4236/jpee.205.34056 The Research of Heat Transfer Area

More information

CZT Gamma Spectrometry Applied to the In-situ Characterisation of Radioactive Contaminations

CZT Gamma Spectrometry Applied to the In-situ Characterisation of Radioactive Contaminations CZT Gamma Spectrometry Applied to the In-situ Characterisation of Radioactive Contaminations Alain Rocher (EDF/DPN; e-mail : alain.rocher@edf.fr) Leon Piotrowski (EDF/R&D; e-mail : leon.piotrowski@edf.fr)

More information

Employees Contractors

Employees Contractors Attachment Exposure Dose Distribution 1. Effective Dose from External Exposure Table 1 shows the distribution of external exposure dose of workers who were involved in radiation work at the Fukushima Daiichi

More information

October 2017 November Employees Contractors

October 2017 November Employees Contractors Attachment Exposure Dose Distribution 1. Effective Dose from External Exposure Table 1 shows the distribution of external exposure dose of workers who were involved in radiation work at the Fukushima Daiichi

More information

Instability Analysis in Peach Bottom NPP Using a Whole Core Thermalhydraulic-Neutronic Model with RELAP5/PARCS v2.7

Instability Analysis in Peach Bottom NPP Using a Whole Core Thermalhydraulic-Neutronic Model with RELAP5/PARCS v2.7 Progress in NUCLEAR SCIENCE and TECHNOLOGY, Vol., pp.10-18 (011) ARTICLE Instability Analysis in Peach Bottom NPP Using a Whole Core Thermalhydraulic-Neutronic Model with RELAP/PARCS v. Agustín ABARCA,

More information

Noble Gas Control Room Accident Filtration System for Severe Accident Conditions (N-CRAFT)

Noble Gas Control Room Accident Filtration System for Severe Accident Conditions (N-CRAFT) E-Journal of Advanced Maintenance Vol.7-1 (2015) 34-42 Japan Society of Maintenology Noble Gas Control Room Accident Filtration System for Severe Accident Conditions (N-CRAFT) Axel HILL *1, Dr. Cristoph

More information

THE FUTURE OF THE CHEMISTRY: CONTINUOUS FLOW REACTIONS BASEL 2016

THE FUTURE OF THE CHEMISTRY: CONTINUOUS FLOW REACTIONS BASEL 2016 THE FUTURE OF THE CHEMISTRY: CONTINUOUS FLOW REACTIONS BASEL 2016 CHEMICAL PLANT CONTINUOUS FLOW REACTOR The continuous flow reactor is a safe system, running chemical reactions in reduced volume with

More information

Journal of NUCLEAR SCIENCE and TECHNOLOGY, Vol. 41, No. 7, p (July 2004)

Journal of NUCLEAR SCIENCE and TECHNOLOGY, Vol. 41, No. 7, p (July 2004) Journal of NUCLEAR SCIENCE and TECHNOLOGY, Vol. 41, No. 7, p. 765 770 (July 2004) TECHNICAL REPORT Experimental and Operational Verification of the HTR-10 Once-Through Steam Generator (SG) Heat-transfer

More information

Chapter 4. Problem SM.7 Ethylbenzene/Styrene Column

Chapter 4. Problem SM.7 Ethylbenzene/Styrene Column Background Chapter 4. Problem SM.7 Ethylbenzene/Styrene Column In Problem SM.6 of the HYSYS manual, a modified form of successive substitution, called the Wegstein method, was used to close the material

More information

VVER-1000 Reflooding Scenario Simulation with MELCOR Code in Comparison with MELCOR Simulation

VVER-1000 Reflooding Scenario Simulation with MELCOR Code in Comparison with MELCOR Simulation VVER-1000 Reflooding Scenario Simulation with MELCOR 1.8.6 Code in Comparison with MELCOR 1.8.3 Simulation Jiří Duspiva Nuclear Research Institute Řež, plc. Nuclear Power and Safety Division Dept. of Reactor

More information

RADIOACTIVE WASTE CHARACTERIZATION IN BELGIUM. Tractebel Ariane Avenue, 7 B-1200, Brussels, Belgium ABSTRACT

RADIOACTIVE WASTE CHARACTERIZATION IN BELGIUM. Tractebel Ariane Avenue, 7 B-1200, Brussels, Belgium ABSTRACT RADIOACTIVE WASTE CHARACTERIZATION IN BELGIUM Serge Vanderperre, Christine Vanhaeverbeek, Koen Mannaerts, Baudouin Centner, Philippe Beguin and Michel Detilleux Tractebel Ariane Avenue, 7 B-1200, Brussels,

More information

In terms of production, nitric acid is the third most widely produced acid across the world.

In terms of production, nitric acid is the third most widely produced acid across the world. In terms of production, nitric acid is the third most widely produced acid across the world. It has a wide range of uses in agriculture, industry and medicine where it is used as a fertiliser and in the

More information

SPACE-DEPENDENT DYNAMICS OF PWR. T. Suzudo Japan Atomic Energy Research Institute, JAERI Tokai-Mura, Naka-Gun Japan

SPACE-DEPENDENT DYNAMICS OF PWR. T. Suzudo Japan Atomic Energy Research Institute, JAERI Tokai-Mura, Naka-Gun Japan SPACE-DEPENDENT DYNAMICS OF PWR T. Suzudo Japan Atomic Energy Research Institute, JAERI Tokai-Mura, Naka-Gun 319-11 Japan E. Türkcan and J.P. Verhoef Netherlands Energy Research Foundation P.O. Box 1,

More information

Developments and Applications of TRACE/CFD Model of. Maanshan PWR Pressure Vessel

Developments and Applications of TRACE/CFD Model of. Maanshan PWR Pressure Vessel Developments and Applications of TRACE/CFD Model of Maanshan PWR Pressure Vessel Yu-Ting Ku 1, Yung-Shin Tseng 1, Jung-Hua Yang 1 Shao-Wen Chen 2, Jong-Rong Wang 2,3, and Chunkuan Shin 2,3 1 : Department

More information

Power Plant Chemistry Instrument Theory & Essentials

Power Plant Chemistry Instrument Theory & Essentials Nuclear Division Scientech Power Plant Chemistry Instrument Theory & Essentials A Scientech Training Course October 1-5, 2018 Clearwater, Florida } Course Overview Attend this ONE training course and get

More information

Intelligent Sensor Management for Brewing Processes

Intelligent Sensor Management for Brewing Processes Intelligent Sensor Management for Brewing Processes Intelligent Sensor Management Intelligent Sensor Management, or simply ISM, is a digital technology for in-line process analytical systems that enhances

More information

Determining water chemistry conditions in nuclear reactor coolants

Determining water chemistry conditions in nuclear reactor coolants Journal of Nuclear Science and Technology ISSN: 0022-3131 (Print) 1881-1248 (Online) Journal homepage: https://www.tandfonline.com/loi/tnst20 Determining water chemistry conditions in nuclear reactor coolants

More information

CCS140 and CCS141. Technical Information. Sensors for free chlorine Amperometric, membrane-covered sensors for installation in the CCA250 assembly

CCS140 and CCS141. Technical Information. Sensors for free chlorine Amperometric, membrane-covered sensors for installation in the CCA250 assembly Technical Information CCS140 and CCS141 Sensors for free chlorine Amperometric, membrane-covered sensors for installation in the CCA250 assembly Application Oxidising agents such as chlorine or anorganic

More information

Common Cause Failures: Extended Alpha Factor method and its Implementation

Common Cause Failures: Extended Alpha Factor method and its Implementation Common Cause Failures: Extended Alpha Factor method and its Implementation Alexandra Sitdikova Reactor Engineering Division, Jožef Stefan Institute Jamova 39, SI-1000 Ljubljana, Slovenia Institute of Physics

More information

High Pressure DSC Differential Scanning Calorimeter

High Pressure DSC Differential Scanning Calorimeter High Pressure DSC Differential Scanning Calorimeter Introduction The Differential Scanning Calorimetry (DSC) is the most popular thermal analysis technique to measure endothermic and exothermic transitions

More information

Dynamics of hydrogen in sodium in LMFBR secondary circuit

Dynamics of hydrogen in sodium in LMFBR secondary circuit Indian Journal of Engineering & Materials Sciences Vol. 13, October 2006, pp. 391-396 Dynamics of hydrogen in sodium in LMFBR secondary circuit Vivek Nema, D Sujish, B Muralidharan, M Rajan & G Vaidyanathan*

More information

473 Dew Point Hygrometer

473 Dew Point Hygrometer High Performance Chilled Mirror Hygrometer With Cable Mounted Measuring Heads Highly precise chilled mirror dew point technology Cable mounted dew point and temperature measurement Aspirated and direct

More information

e - Galvanic Cell 1. Voltage Sources 1.1 Polymer Electrolyte Membrane (PEM) Fuel Cell

e - Galvanic Cell 1. Voltage Sources 1.1 Polymer Electrolyte Membrane (PEM) Fuel Cell Galvanic cells convert different forms of energy (chemical fuel, sunlight, mechanical pressure, etc.) into electrical energy and heat. In this lecture, we are interested in some examples of galvanic cells.

More information

Chemical Engineering 3P04 Process Control Tutorial # 1 Learning goals

Chemical Engineering 3P04 Process Control Tutorial # 1 Learning goals Chemical Engineering 3P04 Process Control Tutorial # 1 Learning goals 1. Sensor Principles with the flow sensor example 2. The typical manipulated variable: flow through a conduit Sensors: We need them

More information

QUALIFICATION OF A CFD CODE FOR REACTOR APPLICATIONS

QUALIFICATION OF A CFD CODE FOR REACTOR APPLICATIONS QUALIFICATION OF A CFD CODE FOR REACTOR APPLICATIONS Ulrich BIEDER whole TrioCFD Team DEN-STMF, CEA, UNIVERSITÉ PARIS-SACLAY www.cea.fr SÉMINAIRE ARISTOTE, NOVEMBER 8, 2016 PAGE 1 Outline Obective: analysis

More information

Ultraviolet LEDS as a Source of Emission for Resist Exposure on Printed Circuit Boards

Ultraviolet LEDS as a Source of Emission for Resist Exposure on Printed Circuit Boards Ultraviolet LEDS as a Source of Emission for Resist Exposure on Printed Circuit Boards Alexander V. Fomenko Institute of Robotics, Innopolis University, Innopolis, Russia xanderfomenko@gmail.com Alexander

More information

THE USE OF PB-BI EUTECTIC AS THE COOLANT OF AN ACCELERATOR DRIVEN SYSTEM. Joint research Centre of the European Commission Ispra, Italy.

THE USE OF PB-BI EUTECTIC AS THE COOLANT OF AN ACCELERATOR DRIVEN SYSTEM. Joint research Centre of the European Commission Ispra, Italy. THE USE OF PB-BI EUTECTIC AS THE COOLANT OF AN ACCELERATOR DRIVEN SYSTEM Alberto Peña 1, Fernando Legarda 1, Harmut Wider 2, Johan Karlsson 2 1 University of the Basque Country Nuclear Engineering and

More information

Radioactive effluent releases from Rokkasho Reprocessing Plant (1) - Gaseous effluent -

Radioactive effluent releases from Rokkasho Reprocessing Plant (1) - Gaseous effluent - Radioactive effluent releases from Rokkasho Reprocessing Plant (1) - Gaseous effluent - K.Anzai, S.Keta, M.Kano *, N.Ishihara, T.Moriyama, Y.Okamura K.Ogaki, K.Noda a a Reprocessing Business Division,

More information

Jason T. Harris, Ph.D. Department of Nuclear Engineering and Health Physics

Jason T. Harris, Ph.D. Department of Nuclear Engineering and Health Physics Jason T. Harris, Ph.D. Department of Nuclear Engineering and Health Physics Idaho State University North American Technical Center July 24, 2012 1 2 Commercial Nuclear Power Plants (NPPs) produce gaseous,

More information

Condition Monitoring for Maintenance Support

Condition Monitoring for Maintenance Support Journal of Marine Science and Application, Vol.6, No., January 26, PP***-*** Condition Monitoring for Maintenance Support BEERE William, BERG Øivind, WINGSTEDT Emil SAVOLAINEN Samuli 2, and LAHTI Tero

More information

473-SHX Dew Point Mirror

473-SHX Dew Point Mirror Humidity and Temperature Reference Hygrometer For Temperature up to 125 C Precise and stable chilled mirror dew point mirror technology High temperature optical components High temperature sample fan Cable

More information

Title: Assessment of activity inventories in Swedish LWRs at time of decommissioning

Title: Assessment of activity inventories in Swedish LWRs at time of decommissioning Paper presented at the seminar Decommissioning of nuclear facilities, Studsvik, Nyköping, Sweden, 14-16 September 2010. Title: Assessment of activity inventories in Swedish LWRs at time of decommissioning

More information

Proposal for a neutron imaging station at n TOF EAR2

Proposal for a neutron imaging station at n TOF EAR2 EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH Proposal to the ISOLDE and Neutron Time-of-Flight Committee Proposal for a neutron imaging station at n TOF EAR2 January 11, 2017 F. Mingrone 1, M. Calviani 1,

More information

3D CFD and FEM Evaluations of RPV Stress Intensity Factor during PTS Loading

3D CFD and FEM Evaluations of RPV Stress Intensity Factor during PTS Loading E-Journal of Advanced Maintenance Vol.9-2 (2017) 84-90 Japan Society of Maintenology 3D CFD and FEM Evaluations of RPV Stress Intensity Factor during PTS Loading Xiaoyong Ruan 1,*, Toshiki Nakasuji 1 and

More information

Chapter 7. Design of Steam Generator

Chapter 7. Design of Steam Generator Nuclear Systems Design Chapter 7. Design of Steam Generator Prof. Hee Cheon NO 7.1 Overview and Current Issues of S/G 7.1.1 Essential Roles of S/G 2 3 7.1.2 S/G and Its Interfacing Interfacing system of

More information

A MULTIPARAMETER INSTRUMENTATION APPROACH TO MAKEUP AND CYCLE CHEMISTRY MEASUREMENTS

A MULTIPARAMETER INSTRUMENTATION APPROACH TO MAKEUP AND CYCLE CHEMISTRY MEASUREMENTS Presented at the 8 th International Conference on Cycle Chemistry in Fossil and Combined Cycle Plants with Heat Recovery Steam Generators, EPRI, Calgary, June 2006 A MULTIPARAMETER INSTRUMENTATION APPROACH

More information

Tritium Transport and Corrosion Modeling in the Fluoride Salt-Cooled High-Temperature Reactor

Tritium Transport and Corrosion Modeling in the Fluoride Salt-Cooled High-Temperature Reactor Tritium Transport and Corrosion Modeling in the Fluoride Salt-Cooled High-Temperature Reactor John D. Stempien, PhD Content Based on Doctoral Thesis Defense Workshop on Tritium Control Salt Lake City,

More information

DISTRIBUTION LIST. Preliminary Safety Report Chapter 21 Reactor Chemistry UK HPR1000 GDA. GNS Executive. GNS all staff. GNS and BRB all staff CGN EDF

DISTRIBUTION LIST. Preliminary Safety Report Chapter 21 Reactor Chemistry UK HPR1000 GDA. GNS Executive. GNS all staff. GNS and BRB all staff CGN EDF Rev: 000 Page: 2 / 23 DISTRIBUTION LIST Recipients GNS Executive GNS all staff Cross Box GNS and BRB all staff CGN EDF Regulators Public Rev: 000 Page: 3 / 23 SENSITIVE INFORMATION RECORD Section Number

More information

Defining quality standards for the analysis of solid samples

Defining quality standards for the analysis of solid samples Defining quality standards for the analysis of solid samples Thermo Scientific Element GD Plus Glow Discharge Mass Spectrometer Redefine your quality standards for the elemental analysis of solid samples

More information

MCNP neutron streaming investigations from the reactor core to regions outside the reactor pressure vessel for a Swiss PWR

MCNP neutron streaming investigations from the reactor core to regions outside the reactor pressure vessel for a Swiss PWR DOI: 10.15669/pnst.4.481 Progress in Nuclear Science and Technology Volume 4 (2014) pp. 481-485 ARTICLE MCNP neutron streaming investigations from the reactor core to regions outside the reactor pressure

More information

Finnigan TC/EA. High Temperature Conversion Elemental Analyzer

Finnigan TC/EA. High Temperature Conversion Elemental Analyzer m a s s s p e c t r o m e t r y Finnigan TC/EA High Temperature Conversion Elemental Analyzer Analyze Detect Measure Control Finnigan TC/EA High Temperature Conversion Elemental Analyzer Finnigan TC/EA

More information

Elemental Scientific. Stability. Elemental Scientific

Elemental Scientific. Stability. Elemental Scientific Elemental Scientific prepfast ICP-MS: USP Oral Drugs by Dilution Automated Inline Calibration and Sample Dilution Authors: Kyle Uhlmeyer and Paul Field (field@icpms.com) Brief The prepfast inline

More information

Turbine Meter TRZ 03 PRODUCT INFORMATION. Reliable Measurement of Gas

Turbine Meter TRZ 03 PRODUCT INFORMATION. Reliable Measurement of Gas Turbine Meter TRZ 0 PRODUCT INFORMATION Reliable Measurement of Gas TURBINE METER TRZ 0 Method of operation, Construction Method of operation The TRZ 0 turbine meter is a flow meter suitable for gas measurement

More information

One-hand ph/temperature measuring instrument

One-hand ph/temperature measuring instrument One-hand ph/temperature measuring instrument testo 205 ph tip embedded in breakage-proof plastic ph Combined penetration tip with temperature probe Maintenance-free gel electrolyte C Measurement tip exchangeable

More information

Correlation between neutrons detected outside the reactor building and fuel melting

Correlation between neutrons detected outside the reactor building and fuel melting Attachment 2-7 Correlation between neutrons detected outside the reactor building and fuel melting 1. Introduction The Fukushima Daiichi Nuclear Power Station (hereinafter referred to as Fukushima Daiichi

More information

Integrated radiation monitoring and interlock system for the LHD deuterium experiments

Integrated radiation monitoring and interlock system for the LHD deuterium experiments Integrated radiation monitoring and interlock system for the LHD deuterium experiments Nakanishi H. with Safety & Env. Monitoring Team and LHD Information Systems Group National Institute for Fusion Science,

More information

AP1000 European 11. Radioactive Waste Management Design Control Document

AP1000 European 11. Radioactive Waste Management Design Control Document CHAPTER 11 RADIOACTIVE WASTE MANAGEMENT 11.1 Source Terms This section addresses the sources of radioactivity that are treated by the liquid and gaseous radwaste systems. Radioactive materials are generated

More information

Role of the Halden Reactor Project for TVEL nuclear fuels & materials development. B. Volkov IFE/HRP (Norway) Sochi, May 14-16

Role of the Halden Reactor Project for TVEL nuclear fuels & materials development. B. Volkov IFE/HRP (Norway) Sochi, May 14-16 Role of the Halden Reactor Project for TVEL nuclear fuels & materials development B. Volkov IFE/HRP (Norway) Sochi, May 14-16 1 International OECD Halden Reactor Project foundation and history organisation

More information

THERMAL HYDRAULIC REACTOR CORE CALCULATIONS BASED ON COUPLING THE CFD CODE ANSYS CFX WITH THE 3D NEUTRON KINETIC CORE MODEL DYN3D

THERMAL HYDRAULIC REACTOR CORE CALCULATIONS BASED ON COUPLING THE CFD CODE ANSYS CFX WITH THE 3D NEUTRON KINETIC CORE MODEL DYN3D THERMAL HYDRAULIC REACTOR CORE CALCULATIONS BASED ON COUPLING THE CFD CODE ANSYS CFX WITH THE 3D NEUTRON KINETIC CORE MODEL DYN3D A. Grahn, S. Kliem, U. Rohde Forschungszentrum Dresden-Rossendorf, Institute

More information

Automated multi-vapor gravimetric sorption analyzer for advanced research applications

Automated multi-vapor gravimetric sorption analyzer for advanced research applications Automated multi-vapor gravimetric sorption analyzer for advanced research applications Automated multi-vapor gravimetric sorption analyzer for advanced research applications Key benefits of the DVS Advantage

More information

Development of depletion models for radionuclide inventory, decay heat and source term estimation in discharged fuel

Development of depletion models for radionuclide inventory, decay heat and source term estimation in discharged fuel Development of depletion models for radionuclide inventory, decay heat and source term estimation in discharged fuel S. Caruso, A. Shama, M. M. Gutierrez National Cooperative for the Disposal of Radioactive

More information

RESULTS OF ICARUS 9 EXPERIMENTS RUN AT IMRA EUROPE

RESULTS OF ICARUS 9 EXPERIMENTS RUN AT IMRA EUROPE Roulette, T., J. Roulette, and S. Pons. Results of ICARUS 9 Experiments Run at IMRA Europe. in Sixth International Conference on Cold Fusion, Progress in New Hydrogen Energy. 1996. Lake Toya, Hokkaido,

More information

Half-Cell, Steady-State Flow-Battery Experiments. Robert M. Darling and Mike L. Perry

Half-Cell, Steady-State Flow-Battery Experiments. Robert M. Darling and Mike L. Perry Half-Cell, Steady-State Flow-Battery Experiments Robert M. Darling and Mike L. Perry United Technologies Research Center, East Hartford, Connecticut, 06108, USA An experimental approach designed to separately

More information

Thermo Scientific Electrochemistry Products

Thermo Scientific Electrochemistry Products Comparing Performance of DO Methods The world leader in serving science in Water and Seawaters Thermo Scientific Electrochemistry Products Dissolved Oxygen Measurement Oxygen is essential for most of the

More information

Analysis for Progression of Accident at Fukushima Dai-ichi Nuclear Power Station with THALES2 code

Analysis for Progression of Accident at Fukushima Dai-ichi Nuclear Power Station with THALES2 code Analysis for Progression of Accident at Fukushima Dai-ichi Nuclear Power Station with THALES2 code Toshinori MATSUMOTO, Jun ISHIKAWA, and Yu MARUYAMA Nuclear Safety Research Center, Japan Atomic Energy

More information

Available online at ScienceDirect. Evaluation of the streaming current detector (SCD) for coagulation control

Available online at  ScienceDirect. Evaluation of the streaming current detector (SCD) for coagulation control Available online at www.sciencedirect.com ScienceDirect Procedia Engineering 70 ( 2014 ) 1211 1220 12th International Conference on Computing and Control for the Water Industry, CCWI2013 Evaluation of

More information

CHALLENGES ASSESSING AND TREATING WASTEWATER FROM BIOTECHNOLOGY SCALE UP OPERATIONS

CHALLENGES ASSESSING AND TREATING WASTEWATER FROM BIOTECHNOLOGY SCALE UP OPERATIONS CHALLENGES ASSESSING AND TREATING WASTEWATER FROM BIOTECHNOLOGY SCALE UP OPERATIONS Wayne Bates PhD, P.E. William Potochniak, P.E. ISPE Product Show Track 3 Session 2 September 26, 2018 Overview > Existing

More information

Getting started with BatchReactor Example : Simulation of the Chlorotoluene chlorination

Getting started with BatchReactor Example : Simulation of the Chlorotoluene chlorination Getting started with BatchReactor Example : Simulation of the Chlorotoluene chlorination 2011 ProSim S.A. All rights reserved. Introduction This document presents the different steps to follow in order

More information

SOME CONSIDERATION IN THE TRITIUM CONTROL DESIGN OF THE SOLID BREEDER BLANKET CONCEPTS

SOME CONSIDERATION IN THE TRITIUM CONTROL DESIGN OF THE SOLID BREEDER BLANKET CONCEPTS SOME CONSIDERATION IN THE TRITIUM CONTROL DESIGN OF THE SOLID BREEDER BLANKET CONCEPTS L.V. Boccaccini, N. Bekris, R. Meyder and the HCPB Design Team CBBI-13, Santa Barbara, 30th Nov.-2nd Dec. 2005 L.V.

More information

Metrological Methods for Low Volume Liquid Handling in Drug Delivery and In-Vitro Diagnostics

Metrological Methods for Low Volume Liquid Handling in Drug Delivery and In-Vitro Diagnostics Metrological Methods for Low Volume Liquid Handling in Drug Delivery and In-Vitro Diagnostics Dr. Department of Microsystems Engineering IMTEK University of Freiburg, Germany koltay@imtek.de Outline Introduction

More information

Industrial Applications of Microreactor Technology

Industrial Applications of Microreactor Technology Industrial Applications of Microreactor Technology Name / Lonza AG / xx Month 2010 Microreactors are at the heart of a dramatic shift in API production Microreactor (MR) technology enables continuous processes

More information

Integrating third party data from partner networks: Quality assessment using MeteoSwiss Meteorological Certification procedure

Integrating third party data from partner networks: Quality assessment using MeteoSwiss Meteorological Certification procedure Federal Department of Home Affairs FDHA Federal Office of Meteorology and Climatology MeteoSwiss Integrating third party data from partner networks: Quality assessment using MeteoSwiss Meteorological Certification

More information

Bolometry. H. Kroegler Assciazione Euratom-ENEA sulla Fusione, Frascati (Italy)

Bolometry. H. Kroegler Assciazione Euratom-ENEA sulla Fusione, Frascati (Italy) Bolometry H. Kroegler Assciazione Euratom-ENEA sulla Fusione, Frascati (Italy) Revised May 28, 2002 1. Radiated power Time and space resolved measurements of the total plasma radiation can be done by means

More information

Performance Characterization of A New Cam System M.J. Koskelo 1, J.C. Rodgers 2, D.C. Nelson 2, A.R. McFarland 3 and C.A. Ortiz 3

Performance Characterization of A New Cam System M.J. Koskelo 1, J.C. Rodgers 2, D.C. Nelson 2, A.R. McFarland 3 and C.A. Ortiz 3 Performance Characterization of A New Cam System M.J. Koskelo 1, J.C. Rodgers 2, D.C. Nelson 2, A.R. McFarland 3 and C.A. Ortiz 3 1 CANBERRA Industries, Meriden, CT 06450 2 Los Alamos National Laboratory,

More information

Electrolysis System CHLORINSITU V (PLUS)

Electrolysis System CHLORINSITU V (PLUS) Output of 100 3.500 g/h of ultra-pure active chlorine (hypochlorous acid) Electrolysis systems of the type CHLORINSITU V generate ultrapure active chlorine using the unique vacuum method with the membrane

More information

THE APPLICATION OF PROCESS MASS SPECTROMETRY TO FUMED SILICA PRODUCTION

THE APPLICATION OF PROCESS MASS SPECTROMETRY TO FUMED SILICA PRODUCTION JPACSM 5 Process Analytical Chemistry THE APPLICATION OF PROCESS MASS SPECTROMETRY TO FUMED SILICA PRODUCTION Peter Traynor and Steven Trimuar Thermo Electron Corporation Houston, TX Robert G. Wright Thermo

More information

11. Radioactive Waste Management AP1000 Design Control Document

11. Radioactive Waste Management AP1000 Design Control Document CHAPTER 11 RADIOACTIVE WASTE MANAGEMENT 11.1 Source Terms This section addresses the sources of radioactivity that are treated by the liquid and gaseous radwaste systems. Radioactive materials are generated

More information

Polymer plants continue to seek ways to increase production and efficiency without compromising safety.

Polymer plants continue to seek ways to increase production and efficiency without compromising safety. Polyethylene Polypropylene APPLICATION NOTE NOTE Polymer plants continue to seek ways to increase production and efficiency without compromising safety. Process gas analysis is integral to the control

More information

THERMAL STRATIFICATION MONITORING OF ANGRA 2 STEAM GENERATOR MAIN FEEDWATER NOZZLES

THERMAL STRATIFICATION MONITORING OF ANGRA 2 STEAM GENERATOR MAIN FEEDWATER NOZZLES 2009 International Nuclear Atlantic Conference - INAC 2009 Rio de Janeiro,RJ, Brazil, September27 to October 2, 2009 ASSOCIAÇÃO BRASILEIRA DE ENERGIA NUCLEAR - ABEN ISBN: 978-85-99141-03-8 THERMAL STRATIFICATION

More information

Mass flow of steam through condenser m k, kg/s

Mass flow of steam through condenser m k, kg/s UTICAJ KLIMATSKE KRIVE NA RADNI REŽIM TURBINE U TEC "BITOLA INFLUENCE OF CLIMATIC CURVE VALUES ON THE OPERATING REGIME OF THE TURBINE AT TPP "BITOLA" V. Mijakovski*, K. Popovski* *Faculty of Technical

More information