The Use of TOFD for Enhancement of HDPE Pipe Fusion Inspection

2009 ◽  
Author(s):  
Clayton T. Smith ◽  
Peter den Boer ◽  
Lonnie Corley
Keyword(s):  
Water System ◽  
Cooling Water ◽  
Operating Experience ◽  
The United States ◽  
Nuclear Industry ◽  
Microbiologically Influenced Corrosion ◽  
Successful Operation ◽  
Service Water ◽  
Hdpe Pipe ◽  
Ultrasonic Time

HDPE piping has been historically used in place of steels in petrochemical, power, and mining industries to mitigate corrosion and erosion issues. Additionally as HDPE pipe is resistant to Microbiologically Influenced Corrosion (MIC) and fouling, it appears to be a perfect fit for nuclear safety related cooling water applications. To this end, HDPE was first used in an ASME Class 3 emergency service water system, in 2005 at Sizewell B, operated by British Energy, in the United Kingdom. The long successful history of non-nuclear HDPE pipe operating experience along with the successful operation at Sizewell B and other non-safety related nuclear applications has now resulted in the first use of HDPE pipe for a safety related class 3 application in the United States nuclear industry at the AmerenUE-Callaway nuclear power plant. The application of nuclear quality assurance requirements coupled with stringent procurement, manufacturing and fabrication controls create a reasonable assurance that the production fusion joint should be sound; using Ultrasonic Time of Flight Diffraction (TOFD) inspection of the fusion joints is a volumetric, nondestructive examination tool available to provide additional assurance of the fusion joint integrity.

Modern Bimodal High Density Polyethylene for the Nuclear Power Plant Piping System

2009 ◽  
Author(s):  
Adel N. Haddad
Keyword(s):  
High Density Polyethylene ◽  
Nuclear Power ◽  
Large Diameter ◽  
Water System ◽  
High Density ◽  
Nuclear Industry ◽  
Piping System ◽  
Service Water ◽  
Hdpe Pipe ◽  
Related Service

Originally introduced in the 1990s, bimodal HDPE, pipe resins are still finding new niches today, including even nuclear power plants. HDPE pipe grades are used to make strong, corrosion resistant and durable pipes. High density polyethylene, PE 4710, is the material of choice of the nuclear industry for the Safety Related Service Water System. This grade of polymer is characterized by a Hydrostatic Design Basis (HDB) of 1600 psi at 73 °F and 1000 psi at 140 °F. Additionally bimodal high density PE 4710 grades display >2000 hours slow crack growth resistance, or PENT. HD PE 4710 grades are easy to extrude into large diameter pipes; fabricate into fitting and mitered elbows and install in industrial settings. The scope of this paper is to describe the bimodal technology which produces HDPE pipe grade polymer; the USA practices of post reactor melt blending of natural resin compound with black masterbatch; and the attributes of such compound and its conformance to the nuclear industry’s Safety Related Service Water System.

Slow Crack Growth Resistance of Parent and Joint Materials From PE4710 Piping for Safety-Related Nuclear Power Plant Piping

2011 ◽  
Author(s):  
S. Kalyanam ◽  
D.-J. Shim ◽  
P. Krishnaswamy ◽  
Y. Hioe
Keyword(s):  
Crack Growth ◽  
Nuclear Power ◽  
Power Plants ◽  
Slow Crack Growth ◽  
Nuclear Industry ◽  
Pipe Material ◽  
Service Water ◽  
Hdpe Pipe ◽  
Pipe Materials ◽  
Hdpe Pipes

HDPE pipes are considered by the nuclear industry as a potential replacement option to currently employed metallic piping for service-water applications. The pipes operate under high temperatures and pressures. Hence HDPE pipes are being evaluated from perspective of design, operation, and service life requirements before routine installation in nuclear power plants. Various articles of the ASME Code Case N-755 consider the different aspects related to material performance, design, fabrication, and examination of HDPE materials. Amongst them, the material resistance (part of Article 2000) to the slow crack growth (SCG) from flaws/cracks present in HDPE pipe materials is an important concern. Experimental investigations have revealed that there is a marked difference (almost three orders less) in the time to failure when the notch/flaw is in the butt-fusion joint, as opposed to when the notch/flaw is located in the parent HDPE material. As part of ongoing studies, the material resistance to SCG was investigated earlier for unimodal materials. The current study investigated the SCG in parent and butt-fusion joint materials of bimodal HDPE (PE4710) pipe materials acquired from two different manufacturers. The various stages of the specimen deformation and failure during the creep test are characterized. Detailed photographs of the specimen side-surface were used to monitor the specimen damage accumulation and SCG. The SCG was tested using a large specimen (large creep frame) as well as using a smaller size specimen (PENT frame) and the results were compared. Further, the effect of polymer orientation or microstructure in the bimodal HDPE pipe on the SCG was studied using specimens with axial and circumferential notch orientations in the parent pipe material.

Design Optimization of Hydraulic Networks Using Mixed Integer Linear Programming

1982 ◽  
Vol 104 (4) ◽  
pp. 837-843
Author(s):  
T. F. Conry ◽  
J. A. Werhane
Keyword(s):  
Linear Programming ◽  
Integer Linear Programming ◽  
Design Problem ◽  
Mixed Integer Linear Programming ◽  
Computer Aided Design ◽  
Water System ◽  
Cooling Water ◽  
Problem Formulation ◽  
Mixed Integer ◽  
Service Water

The optimum design problem is formulated for the selection of pipe sizes in a hydraulic network such as a power plant service water or bearing cooling water system. The flows in each branch of the network are taken to be known, which makes the design problem linear in the variables. The optimization problem is formulated as a mixed integer linear programming problem. A design example is given. The role of this problem formulation and solution method in an interactive computer aided design (CAD) system is discussed.

Chiller Condenser Service Water Cooling Valve Maintenance

2008 ◽  
Author(s):  
Ken Boughton ◽  
Paul N. Hansen
Keyword(s):  
Flow Control ◽  
Water Flow ◽  
Water System ◽  
Cooling Water ◽  
Control Valves ◽  
Service Water ◽  
Low Load ◽  
Chilled Water ◽  
Chilled Water System ◽  
Load Conditions

This paper presents issues associated with Chilled water system operations at a Nuclear facility that experiences problems with the cooling water flow control valves during the cold season under low load conditions. The system is used to provide safety related functions of cooling rooms such as the control rooms due to radioactive and toxic gas hazards. The valves experience excessive cycling under low load conditions during the cold seasons leading to maintenance and availability problems with the system. This problem is driven by the current system design and the need to utilize a chilled water system during times when natural ambient temperature conditions are low. The Chilled water system uses refrigeration units to cool the chilled water and service water to provide the heat sink for the refrigeration condensing units. The focus of the discussion is the cooling water (service water) flow control valves, which are the major source of the maintenance problem. The paper presents the integrated behavior of the Chilled water system to properly characterize the issue and the solutions. The paper will present the system details and performance parameters necessary to evaluate the problem. The behavior of the valves will be evaluated based on the system operations. This paper evaluates the technical merits of several options to provide stable control of the flow control valves, prevent high-pressure chiller unit trips and solve flow control valve actuator excessive wear.

Oriented Spray Cooling System Ultimate Heat Sink for Future Nuclear Plants

2008 ◽  
Author(s):  
Charles F. Bowman
Keyword(s):  
Analytical Model ◽  
Heat Sink ◽  
Cooling System ◽  
Air Flow ◽  
Water System ◽  
The United States ◽  
Spray Cooling ◽  
Nuclear Plant ◽  
Nuclear Plants ◽  
Service Water

The reference safety-related ultimate heat sink (UHS) for the evolutionary advanced light water reactor nuclear plants that require a safety-related reactor service water system (RSWS) is a spray pond. Spray ponds offer significant advantages over mechanical draft cooling towers including superior simplicity and operability, lower preferred power requirements, and lower capital and maintenance costs. The UHS for the Columbia Generating Station (CGS), one of the last nuclear plants that was licensed during the last round of nuclear plant construction in the United States of America (USA), is the Oriented Spray Cooling System (OSCS), an evolutionary spray pond design. Unlike a conventional spray pond in which spray nozzles are arranged in a flat bed and spray upward, the OSCS nozzles are mounted on spray trees arranged in a circle and are tilted at an angle oriented towards the center of the circle. As a result, the water droplets drag air into the spray region while the warm air that is concentrated in the center of the circle rises. Both of these effects work together to increase air flow through the spray region. Increased air flow reduces the local wet-bulb temperature (LWBT) of the air in the spray pattern, promoting heat transfer and more efficient cooling. During the late 1970’s while working for the Tennessee Valley Authority, the author developed a purely analytical model to predict the thermal performance of the OSCS which was successfully compared with the OSCS at the CGS in the mid 1980’s. This paper describes the OSCS and the analytical model that is used to predict its performance and compares the predicted performance of the OSCS at the CGS with the full-scale field test results. The paper describes how this technology has been successfully used to design the UHS for a future nuclear plant that requires a safety-related RSWS that must not exceed a peak temperature of 95 °F.

Seismic and Concurrent Load Design Criteria for Buried High Density Polyethylene Pipe in ASME BPVC Section III, Division 1, Applications: Part I — Piping Design Basis Criteria

2007 ◽  
Author(s):  
Timothy M. Adams ◽  
Jack Spanner ◽  
Rudolph J. Scavuzzo ◽  
George Gary Thomas
Keyword(s):  
High Density Polyethylene ◽  
The United States ◽  
High Density ◽  
Design Criteria ◽  
Low Carbon ◽  
Modes Of Failure ◽  
Service Water ◽  
Hdpe Pipe ◽  
Asme Code ◽  
Water Piping

The commercial Light Water Reactors operating within the United States have been in service from about 20 to 35 years. These plants include buried Service Water piping systems primarily made from low carbon steel. This piping has been subject to aging over the years, resulting in degradation and corrosion that will require replacement of the piping. Due to the advantageous cost and durability of High Density Polyethylene (HDPE) piping (as demonstrated in other commercial industries), ASME code inclusion of this piping is logical. Duke Power industry has expressed interest in replacing a portion of their steel buried Service Water Piping in Nuclear Power Stations with HDPE pipe. To assist in this effort EPRI has funded and supported the work summarized in this paper to develop design criteria for HPDE Pipe and has teamed with EPRI to develop appropriate ASME Code requirements. Other nuclear utilities will follow once HDPE piping is included in the ASME Code. This paper includes proposed allowable limits of all modes of failure and provides design criteria for HDPE pipe made from PE 3408 resin. It also provides the technical basis for the proposed criteria. This paper deals primarily with the actual design of the piping. The methods included comply with ASME Power Piping Code, B31.1-2004 and Section III of the ASME Boiler and Pressure Vessel Code. Extensive use was made of industrial research, data and experience over 40 years of use of high-density polyethylene piping. Allowable stresses are based on data published in these sources for Design and Service Levels A-D.

Seismic and Concurrent Load Design Criteria for Buried High Density Polyethylene Pipe in ASME BPVC Section III, Division 1, Applications: Part II — Piping Soil Interaction Design Basis Criteria

2007 ◽  
Author(s):  
George Gary Thomas ◽  
Jack R. Spanner ◽  
Rudolph J. Scavuzzo ◽  
Timothy M. Adams
Keyword(s):  
Interaction Design ◽  
High Density Polyethylene ◽  
Nuclear Power ◽  
The United States ◽  
High Density ◽  
Design Criteria ◽  
Analysis Methodology ◽  
Service Water ◽  
Hdpe Pipe ◽  
Water Piping

The commercial Light Water Reactors operating within the United States have been in service from about 20 to 35 years. These plants include buried Service Water piping systems primarily made from low carbon steel. This piping at several plants has been subject to aging over the years, resulting in degradation and corrosion that may require replacement of the piping. Due to the advantageous cost and durability of High Density Polyethylene (HDPE) piping (as demonstrated in other commercial industries), the nuclear power industry has expressed interest in replacing steel buried Service Water Piping in Nuclear Power Stations with HDPE Pipe. To assist in this effort EPRI has funded and supported the work summarized in this paper to develop design criteria for HPDE Pipe. The paper provides design criteria for High Density Polyethylene (HDPE) pipe made from PE 3408 resin. It also provides the technical basis for the proposed criteria. This paper deals primarily with the design of the piping in relation to its interface with the soil in which it is buried. The criteria primarily is derived from current analysis methodology for steel and concrete buried pipe while incorporating changes required to account for the properties and behavior of HDPE pipe. The proposed analysis methodology described herein has evolved into a proposed ASME Boiler and Pressure Vessel Code, Section III, Division I, Design Code Case for consideration by the Section III, Subcommittee on Nuclear Power.

scholarly journals Operating experience and ways to improve the performance of the service water supply system at the Novovoronezh NPP II (Units 1 and 2)

2020 ◽  
Vol 6 (4) ◽  
pp. 253-260
Author(s):  
Vladimir P. Povarov ◽  
Dmitry B. Statsura ◽  
Dmitry Ye. Usachev
Keyword(s):  
Distribution System ◽  
Water Distribution ◽  
Cooling Tower ◽  
Water Distribution System ◽  
Cooling System ◽  
Cooling Water ◽  
Operating Experience ◽  
Supply System ◽  
Summer Period ◽  
Service Water

The operating experience of Novovoronezh NPP II-1 shows that, in the summer period, the temperature of the cooling water exceeds the design value: this indicates the insufficient performance of the service water supply system. The main factor that has a negative impact on the performance of this system is the formation of carbonate deposits on the cooling tower filler. At Novovoronezh NPP II-1, the cooling tower water distribution system was cleaned from carbonate deposits by the method of combined vibration and aerohydraulic impact. The tested method of cleaning the filler cannot be considered optimal, since the main stage that determines the entire cleaning duration is the assembly/disassembly of the cooling tower filler. It is necessary to continue research on the choice of a strategy for controlling the carbonate deposition rate, taking into account the revealed influence of the design features of the main cooling water pipelines and pipelines of the cooling tower water distribution system on the mechanism of deposit formation in the peripheral spraying area. As compensating measures to ensure the required temperature regime of the turbine plant equipment at Novovoronezh NPP II-1, it is practiced during the summer period to put the standby heat exchangers of the lubrication system and the standby pump of the nonessential services cooling water system into parallel operation. This solution is fraught with the risk of an unplanned decrease in the electrical load if this equipment is turned off in the event of a malfunction. To increase the operating stability of Novovoronezh NPP II-1 and -2 in the summer period, it is proposed to carry out a number of measures aimed at mitigating the negative consequences caused by the elevated service water temperature. Equipment upgrade options are evaluated, e.g., by installing an additional pump for the turbine building services cooling system and (or) laying an additional pipeline to supply part of the makeup water from the Don River directly to the suction pipelines of the pumps of the turbine building services cooling system.

An Integrated Cooling Water Intake System Enhancement Strategy

2005 ◽  
Author(s):  
Jeffrey M. Jones ◽  
Bert Mayer
Keyword(s):  
Heat Exchanger ◽  
Water Intake ◽  
Water System ◽  
Cooling Water ◽  
Integrated Approach ◽  
Operating Efficiency ◽  
Circulating Water ◽  
Service Water ◽  
Debris Transport ◽  
The Subject

Cooling water intake problems come in many forms. These problems can include large schools of fish or jellyfish, seaweed, lake grass, sand, and silt buildup or carryover in the cooling water intake and screen house. Lower lake levels and higher average temperatures, zebra mussel infestation, and non-uniform flow rates between traveling water screen (TWS) bays and circulating water pump bays due to under-sized intake structures can also affect cooling water intake. Downstream of the cooling water intake, flow imbalances caused by entrained debris challenge heat exchanger designs and aging equipment. One Midwestern plant developed an integrated approach to improve the overall performance of the cooling water intake which will result in increased operating efficiency. For the subject plant, this paper will discuss specific modifications planned or undertaken and their benefits and limitations, flow modeling and design margin analyses completed and in process, anticipated reduction in debris carryover, impingement, and entrainment, and suggested further improvements. The majority of modifications undertaken or planned at the subject plant are generally intended to minimize debris carryover and to reduce problems associated with system blockages and heat exchanger tube fouling. Specific modifications to be discussed include: an acoustic fish deterrent system at the inlet tunnel entrance, replacement of the flow-through TWS’s with an industry first-of-a-kind design screen technology, screen wash, and debris transport and removal system modifications, service water system strainer basket modifications, service water system heat exchanger repairs and modifications, and installation of a sodium hypochlorite system.

Use of HDPE Piping in the Callaway Nuclear Plant Essential Service Water System

2009 ◽  
Author(s):  
Shannon L. Abel ◽  
Matthew D. Brandes ◽  
Lonnie J. Corley ◽  
Joseph L. Fortman ◽  
Thomas M. Musto ◽  
...  
Keyword(s):  
Water System ◽  
The United States ◽  
Nuclear Plant ◽  
Lessons Learned ◽  
Metallic Materials ◽  
Service Water ◽  
Design Qualification ◽  
Qualification Testing ◽  
Microbiologically Induced Corrosion ◽  
Essential Service

Callaway Nuclear Plant is the first nuclear plant in the United States to utilize high density polyethylene (HDPE) piping in a nuclear safety-related application. HDPE is being installed in buried sections of the plant’s ASME Section III, Class 3 Essential Service Water (ESW) system. Due to its resistance to erosion, corrosion and microbiologically induced corrosion (MIC), HDPE is well suited to raw water system applications. As with any other first of a kind project, the use of HDPE piping in the Callaway ESW system has presented challenges in all phases of the project. Design, qualification and installation considerations for thermally-fused HDPE in an ASME Class 3 system differ significantly from those for traditional metallic materials. This paper will examine the challenges and lessons learned in the design, qualification testing, installation, examination and pressure testing of the HDPE piping at Callaway Nuclear Plant.

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