A steam injector (SI) is a simple, compact and passive pump and also acts as a high-performance direct-contact compact heater to heat up feedwater by using extracted steam from the turbine. To develop high performance compact feedwater heater, it is necessary to quantify the characteristics between physical properties of the flow ...

The Advanced Boiling Water Reactor-II (ABWR-II) is under development, based on the technologies and experiences of ABWR, to further improve the performance and economy. There are new systems and components developed or under development to incorporate into the primary system of ABWR-II. This paper introduces the primary system and ...

This LTR consists of the recommended characteristics for the main feedwater pump (an Ingersoll-Rand 4HMTA-6 or equivalent). (ERA citation 10:039230)

...2010-10-01 false Injectors and feedwater pumps. 230.57 Section 230.57 Transportation...and Appurtenances Injectors, Feedwater Pumps, and Flue Plugs § 230.57 Injectors and feedwater pumps. (a) Water delivery systems...

Subject matter includes condensate and feedwater systems (general features of condensate and feedwater systems, condenser hotwell level control, condensate flow, feedwater flow), pumps (principles of fluid flow, types of pumps, centrifugal pumps, positive displacement ...

This paper discusses the recent modifications and equipment additions to the auxiliary feedwater (AFW) system at San Onofre nuclear generating station (SONGS) Unit 1. As a result of the Three Mile Island accident, several modifications to the AFW system were required. The addition of a third auxiliary feedwater pump was necessary to ...

A frame-based technique, including physical frame, logical frame, and cognitive frame, was adopted to perform digital I and C failure events derivation and analysis for generic ABWR. The physical frame was structured with a modified PCTran-ABWR plant simulation code, which was extended and enhanced on the feedwater system, ...

The method of identifying drawings, specifications, manuals, procedures and other documentation applicable to the 10 MWe Solar Pilot Plant is established. Detailed specifications are given for the motor driven receiver feedwater pumps with specified acces...

The effectiveness of different methods for controlling the rotor rotation frequency of the feedwater pump of a 300-MW power unit during its operation at sliding steam pressure is compared.

Two advanced boiling water reactors (ABWRs) whose electric output power is 1356 MW have been commercially operated since 1996 and 1997 by the Tokyo Electric Power Company (TEPCO) in Japan. Features of an ABWR are reactor internal pumps (RIPs) placed in the lower plenum and downcomer, peripherally bottom-mounted on the reactor pressure ...

... Similar results are true for feedwater pumps in steam power applications and ... The goal of this work is to develop an on-line condition monitoring tool ...

1000 MWe Advanced Boiling Water Reactor has only two main steam lines and six reactor internal pumps, whereas 1350 MWe ABWR has four main steam lines and ten reactor internal pumps. In order to confirm how the differences affect hydrodynamic conditions in the dome and lower plenum of the reactor pressure vessel, fluid analyses have ...

A steam turbine-generator power plant is described wherein solar energy is used to preheat feedwater to a steam generator. Two parallel feedwater supply branches are proposed for preheating the feedwater upstream from the steam generator. A first preheater branch utilizes extraction steam from the steam turbine for preheating ...

This paper discusses the safety design of the Toshiba Boiling Water Reactor (TOSBWR) which was created {approx}8 years ago. The design concept is intermediate between conventional boiling water reactors (BWRs) and the advanced BWR (ABWR). It utilizes internal pumps and fine motion control rod drive, but the emergency core cooling system (ECCS) ...

A data summary of the characteristics of the PL-1 and PL-2 plants is given. Revisions were made in the plant systems to improve performance; conserve materials, weight, and space: and to provide for simple operation. Data is included on the reactor, electrical system, environment, fuel elements. core geometry, control, main stream system, condensate system, feedwater ...

To simplify maintenance, E.D.F. along with its collaborators undertook the study of mechanical seal with integrated cooler used in feed-water pumps in the nuclear power plants. The cooler, integrated to the pump acts as a thermal barrier as well as a cool...

Experience gained with nuclear power stations in service has led to new feedwater system arrangements, especially in the case of boiling water reactors. The consequences of forward pumping of condensate into the feedwater circuit and using a feedwater heater with deaerator in this type of plant are ...

... it i5 pumped either to feedwater did not ... and valve leaks and infrequent piping failures that ... tank walls with a portable rotating nozzle which delivers ...

... degrade the overall system efficiency, ii) cause excessive structural vibration, ... nuclear power industry (boiler feedwater pumps), and the U.S. ship ...

It is possible to simplify the reactor internal pump power supply system in the ABWR without affecting the core flow supply when a trip of all RIPs event occurs by eliminating the motor-generator sets and increasing the rotating inertia of the RIPs. This inertia increase due to an additional flywheel, which leads to a gain in weight and length, requires a ...

In the Kuosheng nuclear power station, a turbine-driven reactor feedwater pump (TDRFP) is used to drive feedwater to the reactor pressure vessel (RPV). The performance of the TDRFP plays an important role in the safe operation of the nuclear power station as it governs the water inventory in the RPV. The dynamics of the TDRFP in the ...

Parallel turbine-driven feedwater pumps are needed when ships travel at high speed. In order to study marine steam generator feedwater control systems which use parallel turbine-driven feed pumps, a mathematical model of marine steam generator feedwater control system was developed which ...

Long-term low flow operation of feedwater pumping equipment for power plants results in different kinds of cavitation damage to first-stage impellers, noisy operation, and often severe equipment vibration. Methods for avoiding these low flow problems in the design and operation of feedwater systems for new power plants and for ...

The specifications are given for the motor driven Receiver Feedwater Pumps, drive and accessories. Requirements and procedures for documentation are also included. Equipment bid data, variable speed drive data, and motor data sheets are included. (LEW)

The specifications are provided for the motor driven receiver feedwater pump, drive and accessories of the Barstow Solar Pilot Plant. Requirements and procedures for documentation are presented. Variable speed drive and motor data are included, as are equipment bid data.

The specifications are provided for the motor driven receiver feedwater pump, drive and accessories of the Barstow Solar Pilot Plant. Requirements and procedures for documentation are presented. Variable speed drive and motor data are included, as are equ...

This report presents the results of the assessment of TRAC-BF1 (GiJ1) code with the model of the C.N. Cofrentes for simulation of the transient originated by the manual trip of one pump.

A steam-generating plant consisting of two steam generators, a common heater to superheat the steam, and a feed-water system is patented. Part of the superheated steam is fed to the generators to evaporate water and to superheat steam, and the other part is fed to one or more locations of use. The feed-water system consists of one normally ...

The establishment and development history of the Moscow Power Engineering Institute's Department of Hydromechanics and Hydraulic Machines, and the educational and scientific work presently conducted at it are briefly described. The research and design work aimed at developing the optimal construction of the flow path and blade systems for the stages of a feedwater ...

During the report period the SL-1 plant suffered 10 unscheduled shut- downsi four were the result of steam leaks, two resulted from instrumentation, and two were caused by turbine governor malfunction. Rod bank position; were obtained for various xenon conditions. Decay heat removal tests established that the system pressure buildup would not result in relief valve lifting following a ...

of the super�heated steam taken at the required reheat temperature and pressure. With all these quantities-pressure steam turbine, a moisture separator, a reheater, a condenser, feedwater heaters and feedwater pump. Illustration of a single-stage reheater. The heating steam from the reactor flows in U-pipe bundles and enters

Steam turbines are well suited as prime movers for driving boiler feedwater pumps, forced or induced-draft fans, blowers, air compressors, and other rotating equipment. This service generally calls for a backpressure non-condensing steam turbine. The low-pressure steam turbine exhaust is available for feedwater heating, preheating of ...

to the multistage feedwater heater arrangement, which provides easy access to a range of steam temperatures, a multistage steam reheater, a condenser, six feedwater heaters, a turbogenerator, and recirculation pumps heaters, also enhances the coupling of IRIS to the MSF plant since there are a range of steam temperatures

A solar heat exchanger for vaporizing virtually all the liquid entering the exchanger. The solar heat exchanger of the invention is comprised of a metal tube, a feedwater inlet tube of much smaller diameter located within the metal tube and a transparent glass envelope enclosing the metal tube. The annular space between the inner surface of the glass envelope and the outer ...

A closed cycle steam generating system is described comprising a steam boiler, and a steam turbine includes a vacuum pump of the liquid vortex type for condensing the exhaust steam from the turbine, a feedwater pump being employed for returning the condensate to the boiler. The tank of the vortex pump is maintained ...

A cogeneration plant is described comprising in combination: a first stage source of hot gas; a duct having an inlet for receiving the hot gas and an outlet stack open to the atmosphere; a second stage recovery heat steam generator including an evaporator situated in the duct, and economizer in the duct downstream of the evaporator, and steam drum fluidly connected to the evaporator and the ...

The reactor assembly consists of the reactor vessel, its internal components of the core, shroud, steam separator, dryer assemblies, feedwater spargers, internal recirculation pumps and control rod drive housings. Connected to the steam lines are the pres...

A dynamic point model of a simplified once-through boiler was developed. The model comprises economiser, evaporator, burner and feedwater pump dynamics. The reheater and superheaters are excluded, but the influence of the superheater volume on the pressur...

...OF TRANSPORTATION STEAM LOCOMOTIVE INSPECTION AND MAINTENANCE STANDARDS Boilers and Appurtenances Injectors, Feedwater Pumps, and Flue Plugs § 230.58 Flue plugs. (a) When plugging is permitted. Flues greater than 21/4 inches...

Commercial applications will be developed in fuel and chemical mixing technology . ...... nuclear power industry (boiler feedwater pumps), and the U.S. ship ...... Clean Air Act: Support of industry and local/regional governments for ...

This paper describes investigations on auxiliary feedwater pumps being done under the Nuclear Plant Aging Research (NPAR) Program. Objectives of these studies are: to identify and evaluate practical, cost-effective methods for detecting, monitoring, and assessing the severity of time-dependent degradation (aging and service wear); recommend inspection and ...

The purpose of this paper is to provide the quantitative evaluation method with regard to the Digital Protection systems (DPSs) that were newly adopted in the ABWR plants and to show the results of level-1 PSA of the ABWR plants. (authors)

It is necessary to determine how the collector feedwater supply affects the disposition of the stability limits and the instability period for the power distribution in such a reactor. The main reason for the fluctuations in feedwater flow rate were shown by additional calculations with the general power regulator switched out to be due to instability on ...

Automatic water level control in steam generators is currently achieved via a three-element controller. This algorithm is based on the measurements of level, steam flow, and feedwater flow. Unfortunately, at low power the feedwater flow signal is highly unreliable, forcing the transfer to manual control. A large number of reactor trips occur under these ...

The common cause failures of the auxiliary feed water pumps could have significant impacts on the availability of the auxiliary feed water system and plant safety. In order to minimize the common cause failure of the auxiliary feed water pumps, an advanced nuclear power plants should incorporate lessons learned from previous common cause failure events and ...

A reactor core isolation cooling system includes a reactor pressure vessel containing a reactor core, a drywell vessel, a containment vessel, and an isolation pool containing an isolation condenser. A turbine is operatively joined to the pressure vessel outlet steamline and powers a pump operatively joined to the pressure vessel feedwater line. In ...

A reactor core isolation cooling system includes a reactor pressure vessel containing a reactor core, a drywell vessel, a containment vessel, and an isolation pool containing an isolation condenser. A turbine is operatively joined to the pressure vessel outlet steamline and powers a pump operatively joined to the pressure vessel feedwater line. In ...

This paper presents the effects produced on pressurized water reactor (PWR) core melt frequency by the inclusion of primary feed-and-bleed as a decay heat removal mechanism. An analysis is performed for a standard PWR design in which the dominant accident sequences taken from probabilistic risk assessments (PRAs) are developed with and without primary feed-and-bleed. The change in core melt ...

An economizer system is described for heating feedwater in a heat recovery steam generator which consists of: at least first and second economizer tube planes; each of the economizer tube planes including a plurality of generally parallel tubes; the tubes being generally vertically disposed; each of the economizer tube planes including a top header and a bottom header; all of ...

This report presents the results of the assessment of TRAC-BF1 (GiJ1) code with the model of the C.N. Cofrentes for simulation of the transient originated by the manual trip of one pump.

The report presents the results of the assessment of TRAC-BF1 (G1J1) code with the model of the C. N. Cofrentes BWR/G power plant for simulation of the transient originated by the manual trip of one pump.

This Volume, Piping, Feedwater Heater Operation, and Pumps is the ninth of nine Proceedings Volumes of technical papers published for the Pressure Vessels and Piping Conference, held June 23 through 27, 1985 in New Orleans, Louisiana. The contributions are made through the Presssure Vessel and Piping Operations, Application, and Components Committee and ...

Eight hundred MWe class PWR turbine-generators operated smoothly and continuously at sudden load reduction from full load to house load, maintaining NPSH of the feedwater booster pumps through transition even though the available NPSH never exceeded zero. NPSH of the pump at 151.3�C, at which the available NPSH was minimal during ...

A Steam Injector (SI) is a simple, compact and passive pump and also acts as a high-performance direct-contact heater. This provides SI with capability to serve also as a direct-contact feed-water heater that heats up feed-water by using extracted steam from turbine. Our technology development aims to significantly simplify equipment ...

On November 21, 1985, a water hammer event occurred in horizontal feedwater line B at San Onofre Nuclear Generation Site (SONGS) Unit 1. The SONGS Unit 1 is a three-loop pressurized water reactor designed by Westinghouse Electric Corp. The event was initiated by a differential current trip on the bus of auxiliary transformer C. The root cause of the event was a simultaneous ...

Safety assessment of design-basis events and other postulated events assume the unavailability of the auxiliary feedwater (AFW) system during such occurrences. The AFW is essential for mitigating the consequences of certain design-basis events and normally provides plant cooldown to shutdown cooling conditions. In the event AFW is unavailable concurrent with loss of main ...

An innovative reactor core concept applying spectral shift rods (SSRs) is proposed to improve the plant economy and the operability of the 1700 MWe ABWR-II reactor. The SSR is a new type of water rod, in which a water level is naturally developed during operation and changed according to the coolant flow rate through the channel. By taking advantage of the largeness of the ...

The ABWR Design Verification Program is aimed at restoring confidence in the US licensing process by demonstrating its workability by obtaining USNRC preapproval of GE's ABWR Standard Plant. The purpose of this work is to achieve full NRC approval of the ABWR through the award of an NRC Staff final design approval (FDA) and ...

Selected core reflooding situations were investigated in the case of a Finnish boiling water reactor with three severe accident analysis computer codes (MAAP, MELCOR, and SCDAP/RELAP5). The unmitigated base case accident scenario was a 10% steam-line break without water makeup to the reactor pressure vessel initially. The pumping of water to the core was started with the ...

The hydrodynamics section of the RELAP5-3D computer program has been recently improved. Changes were made as follows: (1) improved turbine model, (2) spray model for the pressurizer model, (3) feedwater heater model, (4) radiological transport model, (5) improved pump model, and (6) compressor model.

Makeup Water Key: = Heat Recovery Steam Generator = Flue Gas Desulfurization = Induced Draft Fan = Plant, and boiler feed water pump. A regression model based on the SO2 concentration in the flue gas and the flue recovery steam generator, flue gas desulfurization, fabric filter, boiler feedwater treatment, induced

The Materials Transport Study has several interrelated principal purposes: to confirm the effects of pumped forward heater drains on feedwater corrosion levels; to verify that the water chemistry could be kept within fuel warranty limits; to determine the sources and effects of corrosion products that become deposited on the interior surfaces of plant ...

Vessel Reheater Preheater Steam Generator Superheater HTF Pump ~HP- LP- Condenser Deaerator HP- Feedwater inlet temperature at the condenser, the steam or water mass flow rate in the power plant, Steamm, the steam mass flow rate and the heat exchanger water inlet temperature was added to equation (11). Hence

This report describes a plant model of the advanced BWR (ABWR) plant. The model has been jointly developed by CRIEPI and General Electric Company (GE). This model is designed for combining it with the CRIEPI power system dynamics analysis program and for ...

Employing the PIUS design principle, pressurized water reactors can be provided with unique characteristics that make their safety independent of conventional safety systems and virtually immune to human error during operation. A basic feature of this principle is the self-protective thermohydraulic design of the primary system, which prevents core power from exceeding the cooling capability of ...

A steam injector (SI) is a simple, compact and passive pump and also acts as a high-performance direct-contact compact heater. This provides SI with capability to serve also as a direct-contact feed-water heater that heats up feed-water by using extracted steam from turbine. Our technology development aims to significantly simplify ...

An in-pile loop that can simulate boiling water reactor (BWR) coolant conditions has been operated in the Massachusetts Institute of Technology research reactor in a program supported by Hitachi, the Electric Power Research Institute and Empire State Electric Energy Research Company to study {sup 16}N chemistry as one of its research objectives. The facility consists of a charging tank equipped ...

Design and operating features of the Monticello and Vermont Yankee BWRs were compared in an attempt to explain why shutdown radiation levels at Vermont Yankee were significantly higher than at Monticello. The plants were shown to be similar in many respects, for example, condenser and feedwater system design and materials, condensate treatment system design, ...

Scoping studies for a power conversion system based on a direct-cycle supercritical water reactor have been conducted. The electric power range of interest is 5-30 MWe with a design point of 20 MWe. The overall design objective is to develop a system that has minimized physical size and performs satisfactorily over a broad range of operating conditions. The design constraints are as follows: Net ...

This paper describes an effort by Tokyo Electric Power Company (TEPCO) to shorten the construction time in a drastic manner for the Advanced Boiling Water Reactors (ABWR), thereby aiming at reducing construction costs. First an outline of the actual construction records for the five BWR Units and the two ABWR Units at the Kashiwazaki-Kariwa site is ...

Thermal-hydraulic calculations using RELAP5/MOD2 are performed to simulate the responses of the Maanshan pressurized water reactor (PWR) power plant when the secondary heat sink is lost. The loss of heat sink transient of primary interest in this study is the loss of off-site power coincident with a loss-of-all-feedwater event. This transient is selected because it is one of ...

An analysis is presented for the availability of the electrical power supplies upon reactor shutdown. Successful power supply is defined in terms of the ability of the associated pumps (pump motors) to provide forced circulation and to deliver sufficient feedwater for proper cooldown of the core. Previous investigations of the ...

... Accession Number : AD0612809. Title : RAINMAKER FEEDWATER AND STEAM CONDENSATE QUALITY OF NAVAL SHORE INSTALLATIONS. ...

In nuclear power plants using PWR or BWR type reactors the low steam conditions lead to the use of physically much larger turbine sets than in conventional base load plants. Superheating cannot be used and the steam is nearly always wet. The large steam volumes for a given power output necessitate very large turbine blades at the LP exit and this is the limiting factor in design. The ...

This paper summarizes the loss-of-off-site-power-and-water-hammer event that occurred at San Onofre Unit 1 on November 21, 1985. Unit 1 is a 450-MW(electric) pressurized water reactor, supplied by Westinghouse, that began commercial operation in January 1968. In the early morning hours of November 21, 1985, a loss of ac electrical power occurred when the transformer for the plant's ...

This article describes a polytetrafluoroethylene/aramid packing for boiler feedwater pumps which has saved DuPont Company's Savannah River Plant over $2000/yr. Although the packing is more expensive than the material previously used, the one year minimal service life, compared to less than 8 weeks for the packing previously used, has already saved ...

The objective of this study was to develop and demonstrate techniques for measuring the quantities of cobalt released to the primary coolant by wear of high-cobalt alloys. Without detailed pre-wear measurements being available for existing components, the approach was to measure the amount of wear relative to nearby unworn reference surfaces by developing in situ measurement techniques. Making ...

ORNL is conducting aging assessments of auxiliary feedwater pumps to provide recommendations for monitoring and assessing the severity of time-dependent degradation as well as to recommend maintenance and replacement practices. Cornerstones of these activities are the identification of failure modes and causes and ranking of causes. Failure modes and ...

This manual provides in-depth coverage of topics related to boiler operations. The assignments contain an objective, descriptive information, reference sources, procedures, and assignments. Sixteen units are provided and address topics such as: (1) steam engineering concepts; (2) boiler fittings; (3) feed-water, steam, and combustion accessories; (4) combustion; (5) ...

Consideration is given to a 10-megawatt solar thermal power plant to be built in 1980-1981 using central receiver concepts of generating electricity from incident solar energy. The system will consist of a turbine-generator, cooling tower condenser, feed-water heaters and pumps, and a control room. The turbine will accept steam directly from the receiver ...

An electronic device which automatically corrects the measurement of the pH of ammonia dosed power station boiler feedwater for changes in alkalinity brought about by the temperature dependence of the association of ammonia is described. It is noted that the pH depends on the temperature of the sample and that in a typical boiler plant where pH may be measured at the ...

The design of a boiling water reactor using a combination of natural and forced circulation of coolant is patented. The reactor is supplied with subcooled feedwater, which is proportioned between separate regions of the reactor. The steam is separated from the water at separate locations for each region and conveyed to a point of use. The power output of the reactor ...

The response of a four-loop Westinghouse pressurized water reactor to SBLOCAs initiated as a result of an anticipated transient without scram (ATWS) has been analyzed using the RELAP5 computer code. The ATWS is initiated by a loss-of-feedwater, and the small breaks were due to either one or three stuck-open safety valves or reactor coolant pump seal ...

At the request of the US Nuclear Regulatory Commission (NRC), we performed a rapid-response analysis of the loss-of-feedwater (LOFW) event that occurred at the Toledo Edison Davis-Besse plant on June 9, 1985. The initial 831 s of the plant transient were simulated and, in addition, four postulated transients were calculated to determine how the plant would have responded if ...

Recent severe accident sequence analysis (SASA) work in LASL's Multifault Accident Analysis Section has focused on loss-of-feedwater (LOFW) transients at a 4-loop Westinghouse nuclear power reactor. In all transients studied, the initiator was loss of main feedwater and reactor coolant pump (RCP) trip, caused by temporary loss ...

An innovative reactor core concept applying spectral shift rods (SSRs) is proposed to improve the plant economy and the operability of the 1700-MW(electric) Advanced Boiling Water Reactor II (ABWR-II). The SSR is a new type of water rod in which a water level is naturally developed during operation and changed according to the coolant flow rate through the channel. By taking ...

The conceptual design of the 100 MW solar tower focus commercial power plants is described in detail. Sodium is pumped up to the top of the tall tower where the receiver is located. The sodium is heated in the receiver and then flows down the tower, through a pressure reducing device, and into a large, hot storage tank made to meet a specific thermal energy storage capacity ...

Nine selected Anticipated Transients Without Scram (ATWS) have been simulated on the BNL Engineering Plant Analyzer (EPA), to determine how power and flow oscillations, similar to those that did or could have occurred at the LaSalle-2 boiling Water Reactor (BWR), could affect the rate of Pressure Suppression Pool heating. It has been determined that the pool can reach its temperature limit of ...

The objective of this study is to measure the amount of cobalt released to the primary coolant by wear of components in the primary circuit of nuclear power plants. Since detailed measurement data prior to wear were not available for field components, the measurements were made relative to nearby unworn reference surfaces. In most cases a profilometer was used to ascertain the worn profiles. Wear ...

The results of an extensive study of turbine cycle analyses for steam power plants are presented. Applications of the results of this study for practical design and feasibility analyses for the most desirable turbine cycle are also presented. The First Law and Second Law of Thermodynamics are applied to a series of possible steam power plant configurations operating at various conditions. These ...

The mixing of sea and river water can be used as a renewable energy source. The Gibbs free energy that is released when salt and fresh water mix can be captured in a process called reverse electrodialysis (RED). This research investigates the effect of the intermembrane distance and the feedwater flow rate in RED as a route to double the power density output. Intermembrane ...

Natural gas and electricity are expensive to the extent that annual fuel and power costs can approach the initial cost of an industrial boiler plant. Within this context, this paper examines several cost-effective efficiency advancements that were implemented during a recently completed boiler plant replacement project at a large semiconductor manufacturing complex.

The Decay Heat Removal Systems for the Clinch River Breeder Reactor Plant (CRBRP) are designed to adequately remove sensible and decay heat from the reactor following normal shutdown, operational occurrences, and postulated accidents on both a short term and a long term basis. The Decay Heat Removal Systems are composed of the Main Heat Transport System, the Main Condenser and ...

This paper discusses the experimental results for two anticipated transients without scram (ATWS) experiments, and compares computer code predictions with the experimental data. Experiment L9-3 simulated an ATWS in a commercial pressurized water reactor (PWR) initiated by a complete loss of feedwater and Experiment L9-4 simulated a loss-of-offsite-power-initiated (loss of ...

The dynamic behavior of boiler feed pumps is analyzed with respect to the effects of the hydraulic and mechanical system of which the pump is a part of. In a first section, methods are demonstrated for modelling the hydraulic system dynamically. The basis of this model are transfer matrices of all components in the system, pipes, valves, ...

General Electric Company`s (GE`s) Advanced Boiling Water Reactor (ABWR) has been approved for operation in Japan, and the final design approval (FDA) by the U.S. Nuclear Regulatory Commission is scheduled for mid-1994. One possible utilization of the ABWR would be to operate with mixed oxide (MOX) fuel with the plutonium made available from the U.S. ...

The current Army Boiling-Water Reactor program is reviewed. Plant design, core analysis, reactor theory development, and health physics studies are discussed for the Portable Low-Power Plants (PL-1 and PL-2). Plans for installing a PL-2 plant in a snow tunnel at Byrd Station in Antarctica are described. (B.O.G.)

...by the applicant's exemptions and departures...and updates to the plant-specific DCD required...Include, in the plant-specific DCD, the...referenced in the U.S. ABWR DCD. B...document for the U.S. ABWR, dated December 1994, for plants referencing this...

The report presents the results of the review of the Auxiliary Feedwater System reliability analysis for the Vogtle Electric Generating Plant (VEGP) Units 1 and 2. The objective of this report is to estimate the probability that the Auxiliary Feedwater Sy...

This report presents the results of a review of the Auxiliary Feedwater System Reliability Analysis for Catawba Units 1 and 2. The objective of this report is to estimate the probability that the Auxiliary Feedwater System will fail to perform its mission...

During the yearly fuel reload, the pressure vessel is inspected by an underwater periscope within the normal scope of routine inspections. Thereby cracks have been discovered at the feedwater sparger rings. Because the feedwater sparger rings are placed a...

Results are reported of a study for the Nuclear Regulatory Commission (NRC) to provide a general understanding of pressure transient (water hammer) propagation in pressurized water reactor (PWR) steam generator feedwater piping systems. A typical feedwate...

... ADD419326. Title : The Application of Solar Energy to Boiler Feedwater Heating in Steam-Electric Power Plants,. Corporate Author : ...

... Accession Number : ADD335801. Title : Remote Field Testing of Carbon Steel Feedwater Heater Tubes,. Corporate Author : ...

... The crack was found where the feedwater pipe connects to the reactor pressure vessel, an arm's length inside the nozzle - the most impossible ...

Results of a utility survey of high-pressure feedwater heaters are compiled and evaluated, and recommendations are made for the design of heaters for future power plants or for retrofits of existing plants. 2 figs., 20 tabs.

... 1970s, discovery of cracking in the feedwater nozzles of BWR's with nozzle/sparger systems initiated a Regulatory requirement (NUREG 0619) ...

This paper examines several cost-effective steam conservation and boiler plant efficiency advancements that were implemented during a recently completed central steam boiler plant replacement project at a very large semiconductor manufacturing complex. The measures include:

The current emergency operating procedures (EOPs) for a three-loop pressurized water reactor on a total loss-of-feedwater (LOFW) incident are experimentally evaluated at the Institute of Nuclear Energy Research Integral System Test (IIST) facility. Four experiments were conducted with a different number of pressurizer power-operated relief valves (PORVs) and centrifugal ...

The Phase 1 Auxiliary Feedwater (AFW) System Aging Study, NUREG/CR-5404 V1, focused on how and to what extent the various AFW system component types fail, how the failures have been and can be detected, and on the value of current testing requirements and practices. This follow-on study, which will be provided in full in NUREG/CR-5404 V2, provides a closure to the Phase 1 ...

A control system for a combined cycle electric power plant is described. It contains: at least one gas turbine including an exit through which heated exhaust gases pass; means for generating steam coupled to said gas turbine exit for transferring heat from the exhaust gases to a fluid passing through the steam generator; a steam turbine coupled to the steam generator and driven by the steam ...

Solar preheated water is supplied to a commercial laundry plant by an active system consisting of 6528 square feet of single glazed flat-plate collectors, 12,500-gallon fiberglass storage tank, auxiliary steam boilers, and a 16,500-gallon water pump with tube-shell heat exchanger for feedwater preheat. The system is designed to provide 20% of the water ...

The Army Ammunition Plants use significant quantities of fossil fuels. To reduce dependence on these scarce, costly, and non-renewable fuels, a study was conducted to investigate potential solar energy applications at the AAPs. Solar energy is a low-level energy source which is best applied to low temperature applications. It can be used at the AAPs to preheat boiler ...

The Army Ammunition Plants (AAPs) use significant quantities of fossil fuels. To reduce dependence on these scarce, costly, and non-renewable fuels, a study was conducted to investigate potential solar energy applications at the AAPs. Solar energy is a low-level energy source which is best applied to low temperature applications. It can be used at the AAPs to preheat boiler ...

Shutdown heat removal by a RVACS for an unprotected loss of flow case in a modular sized LMR has been analyzed with the SASSYS-1 LMR systems analysis code. For this case it was assumed that all power was lost to the primary and intermediate sodium pumps, and feedwater flow to the steam generators was lost. The control rods failed to scram, but reactivity ...

Part I of this handbook contains the basic scientific facts which are the rock-bottom data of power engineering presented in the form that engineers understand. The tables, charts, and formulas related to mechanics and mechanisms, strength of materials, heat fundamentals, steam tables, basic electricity, hydraulics and pumping, and piping and tanks can be used for the solution ...

An analysis of Plutonium Recycle Test Reactor operating requirements under conditions of electrical power failure has shown that the necessary levels of safety, experimental flexibility, and economy and ease of operation will be retained by: installing a 300-kw diesel-generator for emergency electrical power, increasing the storage capacity for compressed instrument air, installing a low- ...

The procedure used for the care and maintenance of the various components of oil field steam generators generally depends upon particular applications. However, it is possible to set forth some guidelines to ensure satisfactory functioning of all parts. This article attempts to establish such guidelines by discussing the operation of the major boiler components, chief sources of trouble, and ...

Failures in the shutdown heat removal system of an LMFBR might lead to flow stagnation and coolant boiling in the reactor core. At normal operating power, the onset of sodium boiling will lead to film dryout and melting of the cladding and fuel within a few seconds. On the other hand, both calculations and currently available experimental data indicate that at heat fluxes corresponding to decay ...

The Utilities Department provides utility services to Monsanto and Cain Chemical Company production units at Chocolate Bayou. Over two years ago the department recognized that a significant reduction in waste and rework could be achieved by improving steam boiler and boiler feedwater system operations. The processes were experiencing high maintenance cost due to metering ...

The inspectors determined that failure to identify and perform preventive maintenance tasks for instrument air dryer 1IA-D-1 in accordance with manufacturer recommendations was the root cause of the June 22, 2001, Unit 1 loss of instrument air (LOIA) and subsequent manual reactor trip. The LOIA increased the likelihood that mitigation equipment (specifically the power conversion system, auxiliary ...

The Gentilly 1 station, a 250-MW(e) light-water-cooled and heavy-water-moderated nuclear reactor, is being decommissioned to a static state (variant of stage 1) condition by Atomic Energy of Canada Limited (AECL). The scope of the decontamination program at the Gentilly 1 site includes the fuel pool and associated systems, the decontamination center, the laundry, the feedwater ...

A high output, high pressure direct contact steam generator for producing high quality steam particularly suited for use with low grade, low cost fuel. When used in a system incorporating heat recovery and conversion of carryover water enthalpy into shaft horsepower, the unit disclosed provides high quality, high pressure steam for ''steam drive'' or thermal ...

The BWR Plant Analyzer has been developed for realistic and accurate simulations of normal and severe abnormal transients in BWR power plants at high simulation speeds, low capital and operating costs and with outstanding user conveniences. The simulation encompasses neutron kinetics, heat conduction in fuel structures, nonequilibrium, nonhomogeneous coolant dynamics, steam line acoustics, and the ...

On March 28, 1979, two feedwater pumps tripped and the accident at Three Mile Island, Unit 2 (TMI-2) was underway. This accident has become one of the most intensely studied technological mishaps in history. The accident was initiated by malfunctions of a pressure release valve and propagated by operator errors because of inadequate information about the ...

The Saxton Nuclear Facility will consist of a 20 Mw(th) light water pressurized reactor, one primary coolant loop including one pump, one secondary heat removal system including one steam generator, steam piping, and feedwater system, required auxiliary systems, service bnilding, and a vapor container. The steam generator will be designed to ...

A domestic nuclear power plant has experienced problems with low steam generator final feedwater temperatures during plant start-up. The low feedwater temperatures have led to instabilities in steam generator level control. Also, long term thermal fatigue of the steam generator feedwater nozzles is a concern. A solution to the problem ...

This paper reports on the current development status of the ABWR-II project, a next generation reactor design based on the ABWR. In the early 90's, a program to develop the next generation reactor for the 21. century was launched, at a time when the first ABWR was still under construction. At the initial stage of this project, ...

Condensate polishers are used in power plant condensate system to remove both particulate matter and ionized corrodents. Their conventional location is just downstream of the hotwell pumps (condensate pumps). Most polisher installations have enough flow capacity to polish 100% of the condensate. This inline configuration has some disadvantage, including a ...

This summary delineates the sequence of a water hammer event that occurred on November 21, 1985, and presents the results of an analysis that identifies the conditions necessary to initiate a water hammer in a long, horizontal feedwater line. Based on the findings of the analysis, it has been determined that a water hammer in a partially voided feedwater ...

A typical embodiment of the invention provides a combination feedwater and "cooldown" water spray head that is centrally disposed in the lower portion of a nuclear power plant steam drum. This structure not only discharges the feedwater in the hottest part of the steam drum, but also increases the time required for the feedwater to ...

An important factor in the efficient, effective, and reliable operation of thermal power plant heat transfer equipment is the quality of the feedwater. The quality of the feedwater is determined by the removal of various types of impurities. Ferriferous inpurities exert a significant, and in a number of cases, a decisive influence on the quality of the ...

A system for protecting components including the heat exchangers of a fluidized bed boiler against thermal mismatch. The system includes an injection tank containing an emergency supply of heated and pressurized feedwater. A heater is associated with the injection tank to maintain the temperature of the feedwater in the tank at or about the same ...

A feedwater temperature control system for a condensing steam turbine plant is described in which the feedwater temperature is automatically adjusted to any value desired for the actual load condition. This is accomplished by controlling the pressure in the feedwater de-aerator by means of live or bled steam. (C.E.S.)

...2010-10-01 false Feedwater supply (modifies PG-61). 52... MARINE ENGINEERING POWER BOILERS General Requirements...52.01-115 Feedwater supply (modifies PG-61). Boiler feedwater supply must meet the...

In mid-1979 cracking was discovered in one of the feedwater lines of an operating PWR system. This paper presents the results of the 3-D stress analysis performed to determine the contribution of thermally stratified flow conditions to the feedwater line cracking. Excessive fatigue damages are predicted at locations which correlate well with the observed ...

A system is described for increasing the temperature of a working fluid heated by a nuclear reactor. The system consists of: a high temperature gas cooled nuclear reactor having a core and a primary cooling loop through which a coolant is circulated so as to undergo an increase in temperature, a closed secondary loop having a working fluid therein, the cooling and secondary loops having ...

Severe water ingress accidents in the 200-MW HTR-module were assessed to determine the safety margins of modular pebble-bed high-temperature gas-cooled reactors (HTR-module). The 200-MW HTR-module was designed by Siemens under the criteria that no active safety protection systems were necessary because of its inherent safe nature. For simulating the behavior of the HTR-module during severe water ...

S>A control system for a boiling reactor is offered which correlates power level to power demands and regulates feedwater temperature. Two feedwater distributor rings are placed above the Core in the pressure vessel. The flow to the two rings is regulated by steam demand. An excessive steam demand causes a portion of the ...

The feedwater for once-through boilers, the feedwater and boiler water of drum boilers, and the attemperation water must satisfy specific requirements for a smooth, save, and economic operation of steam generators and for supplying pure steam to the connected turbines and other systems. The paper deals with the VGB guidelines on ...

An improved arrangement is described for preheating feedwater in a steam boiler system prior to the feedwater entering a fuel economizer in order to prevent corrosion due to condensation of flue gas in the fuel economizer and in the exhaust of the boiler system. The feedwater, prior to entering the fuel economizer, is heated in a ...