Aging study of boiling water reactor high pressure injection systems

Cover of: Aging study of boiling water reactor high pressure injection systems |

Published by U.S. Nuclear Regulatory Commission in Washington, DC .

Written in English

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  • Boiling water reactors -- Reliability,
  • Nuclear reactors -- Cooling -- Safety measures

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Book details

StatementD.A. Conley, J.L. Edson, C.F. Fineman ; prepared for Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission.
ContributionsEdson, Jerald L., Fineman, C. F., Idaho National Engineering Laboratory., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering.
The Physical Object
Paginationxix, 93 p.
Number of Pages93
ID Numbers
Open LibraryOL17017061M

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This report presents the results of a study on aging performed for high pressure injection systems of boiling water reactor plants in the United States. The purpose of the study was to identify and evaluate the effects of aging and the effectiveness of testing and maintenance in detecting and mitigating aging Author: D.A.

Conley, J.L. Edson, C.F. Fineman. COVID Resources. Reliable information about the coronavirus (COVID) is available from the World Health Organization (current situation, international travel).Numerous and frequently-updated resource results are available from this ’s WebJunction has pulled together information and resources to assist library staff as they consider how to handle coronavirus.

This study was performed to examine the relationship between time-dependent degradation and current industry practices in the areas of maintenance, surveillance, and operation of steam turbine drives for safety-related pumps.

These pumps are located in the Auxiliary Feedwater (AFW) system for pressurized-water reactor plants and in the Reactor Core Isolation Cooling and High-Pressure Author: D.F. Cox. high pressure coolant injection system is designed to operate while the nuclear system is at high pressure.

The core spray system and low pressure coolant inj ection mode of the residual heat removal system are Reactor Concepts Manual Boiling Water Reactor Systems. Technical Report: Aging assessment of Westinghouse PWR and General Electric BWR containment isolation functions.

the reactor core. This means that a major pipe break will not uncover the reactor core. Therefore a core spray system is not needed. In Sweden, for example, after the approval of the safety authority, the core spray system has been removed in all internal pump BWRs and has been replaced by high pressure direct water injection in the Downcomer.

Abstract: In this paper, the Cumulative Usage Factor (CUF) of a High Pressure Core Cooling System (HPCS) reactor nozzle of a Boiling Water Reactor was calculated.

This fatigue damage has been caused by the sudden injection of cold water into the reactor vessel through such nozzle. For this purpose, a three-dimensional analysis was carried out. The coolant level in the reactor pressure vessel is a safety parameter of high relevance.

In case of boiling water reactors the emergency core cooling injection systems are activated by level signals. Another important task of the level measurement is the prevention of the reactor overfeed. Stan. Finally, pressure propagation inside piping systems after ISLOCA has been simulated for Hitachi-GE standard Advanced boiling water reactor (ABWR) plant.

Maximum pressure inside High Pressure Core Flooder (HPCF) systems has been less than MPa. TRACG code has been shown to be useful to predict transient behavior of pressure propagation in. Lofaro et al., Aging Study of Boiling Water Reactor Residual Heat Removal System, NUREG/CR, Brookhaven National Laboratory, June aging mechanisms and failure modes for fan cooler system components Component Major aging mechanisms Percentage (%) Major failure modes Percentage (%) Circuit breakers Short, burnout or pitting 30 Does.

DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor.

This study examines the relationship between aging, and current industry practices in areas of maintenance, surveillance, and operation of steam turbine drives for safety related pumps. These pumps are located in the Auxiliary Feedwater (AFW) system for pressurized water reactor plants, and the Reactor Core Isolation Cooling and High Pressure.

Advanced Boiling Water Reactor (ABWR) has multiple safety features to prevent core damage and mitigate the accident progression. Failures of all injection systems to the reactor (ECCS, alternative injection systems, mobile injection systems) could cause a core melt accident and the Reactor Pressure Vessel (RPV) failure.

In pressurized water reactors, an essential part of the secondary water system is the feedwater system. This system returns the condensed steam from the turbine condenser to the steam generators and maintains the water inventory in the secondary system.

Each pressurized water reactor has at least two steam generators. The evaluation of the fatigue cumulative usage factor for the High Pressure Core Spray (HPCS) nozzle of a Boiling Water Reactor (BWR) reactor is developed in this paper.

Boiling Water Reactor (BWR) Public domain image by US NRC. The BWR is a Direct Cycle PlantThe BWR is a Direct Cycle Plant. St System pressure, MP MPa 7 Core thermal power, MW. Electric power, MWe Aging and Life Extension of Major Light Water Reactor Components.

Atlanta, GA: Elsevier Science, ISBN: 15 complete systems; some of these systems are used in both pressurized water and boiling water reactors.

The purpose of this survey was to identify which systems and which associated components were being most affected by aging. It is a rather gross analysis but does provide relative magnitudes of aging effects In systems and components.

The paper reviews the existing generic aging management programs (AMPs) for the reactor coolant system (RCS) components in boiling water reactors (BWRs), including the reactor pressure vessel and internals, the reactor recirculation system, and the connected piping.

The purpose of isolation condensers (ICs) in a boiling water reactor (BWR) is to passively control the reactor pressure by removing heat from the system during abnormal reactor operation.

coolant, this type of nuclear reactor is referred as to Heavy Water Reactor (HWR), whereas the term Light Water Reactor (LWR) is applied to a nuclear reactor cooled by ordinary water. Two types of LWR exist: Pressurized Water Reactor (PWR) and Boiling Water Reactor (BWR). Byabout 81% of all nuclear reactors (those generating at.

4 Reactor water purity transients (Robert Cowan) 5 Surveillance Programs (Wilfried Rühle) NWC plants Reactor water Feed water Main condensate Main steam Auxiliary systems 6 References Nomenclature Unit conversion. Reactor Coolant Recirculation System and Main Steam System Boiling water reactors (BWRs) are nuclear power reactors generating electricity by directly boiling the light water in a reactor pressure vessel to make steam that is delivered to a turbine generator.

After driving a turbine, the steam is converted into water with a condenser (cooled. Nuclear Power-> Nuclear Power Plant-> Types of Reactors-> Pressurized Water Reactor Pressurized Water Reactor – PWR. Pressurized water reactors use a reactor pressure vessel (RPV) to contain the nuclear fuel, moderator, control rods and coolant.

They are cooled and moderated by high-pressure liquid water (e.g. 16MPa). Cheng, Ling. Ph.D., Purdue University, August Evaluation of the Safety Systems in the Next Generation Boiling Water Reactor.

Major Professor: Mamoru Ishii. The thesis evaluates the safety systems in the next generation boiling water reactor by analyzing the main steam line break loss of coolant accident performed in the Purdue. NUCLEAR ENERGY MATERIALS AND REACTORS – Vol.

I - Boiling Water Reactors - R.A. Chaplin ©Encyclopedia of Life Support Systems (EOLSS) Figure 4: BWR vessel cross-section From the reactor vessel steam passes through the main steam lines to the high pressure turbines which drive the generator. Generally the steam goes from a high pressure turbine.

This paper discusses management of aging effects for reactor coolant pressure boundary components in boiling water reactors (BWRs): loss of fracture toughness due to thermal aging and neutron irradiation embrittlement of vessel internals made of cast austenitic stainless steel; cracking of the top guide due to irradiation-assisted stress corrosion cracking; cracking of the core.

This study concerns the long-term operation (LTO) of a boiling water reactor (BWR) reactor pressure vessel (RPV) and its internals.

The main parts of this study are: survey on susceptibility to degradation mechanisms, and computational time limited ageing analyses (TLAAs). Several advanced water cooled reactor designs incorporate passive safety systems based on natural circulation, as described in [2,3]: some of the most relevant design concepts for natural circulation systems are described hereafter and namely as regards AP/AP, ESBWR and ABWR is important to note that the incorporation of systems based on natural circulation to.

In Boiling water reactors (BWR), the reactor pressure vessel internals (RPVI) components are submitted to both, Neutron irradiation and high oxidizing environment which lead (together, by itself or mixed with a sensitized condition) to stress corrosion cracking (SCC) [1–4].

The high-pressure coolant injection system is the first line of defense in the emergency core cooling system. HPCI is designed to inject substantial quantities of water into the reactor while it is at high pressure so as to prevent the activation of the automatic depressurization, core spray, and low-pressure coolant injection systems.

The AP obtains its emergency cooling from huge water tanks mounted above the reactor. Some of these are pressurized with nitrogen gas, allowing them to inject water even if the reactor remains at high pressure, as it may in some accident scenarios.

In most cases, neither electric power nor operator action are needed to start injection. A boiling water reactor (BWR) is a type of light water nuclear reactor used for the generation of electrical power. It is the second most common type of electricity-generating nuclear reactor after the pressurized water reactor (PWR), which is also a type of light water nuclear reactor.

The main difference between a BWR and PWR is that in a BWR, the reactor core heats water, which turns to. Aging study of boiling water reactor high pressure injection systems The piping in the HPI system includes the steamline to the turbine,the turbine exhaustline, the pump suction and injection lines, and many smaller lines.

high-temperature steam, two-phase waterhteam mixtures, room temperature water, or oil for lubrication and hydraulic. Stanford Libraries' official online search tool for books, media, journals, databases, government documents and more.

Phenomena associated with jet-plume condensation of steam-air mixtures in a large subcooled pool of water have implications in predicting global system parameters, such as the containment pressure, in light water reactors. A scaled down, reduced pressure suppression pool was designed to study condensation and mixing phenomena using scaled test.

Fig. 3 — Diagram (highly simplified) of pressurized water reactor power plant. Water is heated to 6,°F by energy released in fission reactions in the reactor (it is prevented from boiling by maintaining high pressure), and pumped into the steam generator, where its heat is transferred to a secondary water system.

Called “Oyster Creak” by some critics because of its aging problems, this boiling water reactor began running in and ranks as the country’s oldest. • Reactor core isolation cooling (RCIC) system: Used in BWR/4s, including Units at the Fukushima Daiichi plant, BWR/5s, BWR/6s, and the Advanced Boiling Water Reactor.

• High-pressure coolant injection (HPCI) system: Used in BWR/3s and BWR/4s, including Units 2. with aging were reviewed. From this background study, various types of systems failure modes that could result from simultaneous common mode failures of various combinations of reactor internals were catalogued.

This included the consideration of functional losses or significant degradations of certain inside-reactor vessel systems. Safety Assurance for Boiling Water Reactors (BWRs) Beyond Design Basis. Analysis for Low Pressure Cooling Injection System Suction Hydrodynamics for a Boiling Water Reactor.

Basar Ozar, Visualization Study on Droplet-Entrainment in a High-Speed Gas Jet Into a Liquid Pool. These reactors are situated at 65 nuclear power plant sites across the United States; a plant site may have 1, 2, or 3 reactors. The fleet of operating reactors in the United States is composed of the following: 69 pressurized water reactors (PWRs) and.

34 boiling water reactors (BWRs). The variations of ΔRT NDT result in the differences of failure probability of reactor pressure vessel.

In this study, the structural integrity of Chinshan boiling water reactor RPV shell welds was evaluated by probabilistic fracture mechanics code .the high pressure coolant injection system and the reactor core isolation cooling system, as well as an automatic start of emergency diesel generators.

Small leaks may be compensated by the redundant high pressure reactor core isolation cooling system (RCIC) or the redundant alternate low pressure system .

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