Application of containment and release management to a PWR ice-condenser plant



Publisher: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Publisher: Supt. of Docs., U.S. G.P.O. [distributor] in Washington, DC

Written in English
Published: Pages: 76 Downloads: 959
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Subjects:

  • Pressurized water reactors -- Accidents -- Management.,
  • Nuclear reactors -- Containment.

Edition Notes

Statementprepared by P. Neogy, J. Lehner.
ContributionsLehner, J. R., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research., Brookhaven National Laboratory.
The Physical Object
FormatMicroform
Paginationxiv, 76, [11] p.
Number of Pages76
ID Numbers
Open LibraryOL15377601M

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Application of containment and release management to a PWR ice-condenser plant Download PDF EPUB FB2

Get this from a library. Application of containment and release management to a PWR ice-condenser plant. [P Neogy; J R Lehner; U.S.

Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research.; Brookhaven National Laboratory.]. Unlike PWRs with large dry or subatmospheric containments, the DCH issue for ice condenser plants could not be resolved by a probabilistic comparison of containment loads versus containment strength.

The approach taken here is to provide an expansion of a probabilistic framework, which represents a simplification of the NUREG containment event tree.

In some cases really unique technologies can be installed. For example, the containment building of Loviisa NPP uses two ice condensers as the pressure-suppression system.

The ice condenser is a safety system designed to rapidly absorb steam and reduce containment pressure following a Loss of Coolant Accident (LOCA) or Main Steam Line Break (MSLB). PWR dry steel shell containment surrounded by concrete biological shield. Another PWR containment design is shown in Fig.

3, where an ice condenser is used to quench any release of radioactivity or steam caused maybe by an earthquake Size: 5MB. The PWR system examined in this study is a MWe system similar in design to a Westinghouse 3-loop plant with a large dry containment; the BWR is a MWe system similar in design to General.

Lehner. Brookhaven National Laboratory Application of containment and release management to a PWR ice-condenser plant. Application of containment and release management strategies to.

J.R. Lehner et aL / Containment and release management strategies The remainder of this paper presents, in an abbrevi- ated form, a description of strategy identification and assessment as well as some of the insights from the investigation of containment and release management strategies for a BWR Mark I plant, documented in ref.

[3].Author: J.R. Lehner, C.C. Lin, P. Neogy. The single function of these systems in to remove the heat and reduce the pressure in the containment building during a postulated accident. The design pressure is about 60 pounds per square inch (psi), although actually pressures over psi could likely be tolerated.

Another attractive feature of the filtered venting for the Loviisa plant is that venting rates would be comparatively low.

The beginning of venting is postponed by the ice condenser high steam suppression capability ( hours), by the large heat capacity of concrete structures and by the high containment free by: 2. - Plant type and size: PWR or BWR, to a range of size up to MWe - Safety system concept - Plant design life: 60 years - Plant siting envelope: acceptable for most available site in U.S: g SSE • Safety and investment protection - Accident resistance - Core damage preventionFile Size: KB.

relief valves in the event of a power or brine supply failure, the receiver is located in the cold store. This will prevent the pressure in the CO 2 system from exceeding a saturation pressure corresponding to the room temperature level.

DEFROST METHOD AND PLANT CONTROL CONCEPT The operation of the system is controlled directly by the room File Size: KB. PRESSURIZED WATER REACTORS J. Pongpuak Department of Chemical Engineering, University of New Brunswick, Canada Keywords: Pressurized Water Reactors, Reactor Core, Fuel Elements, Control Rods, Steam Generators Contents 1.

Introduction General Information 2. General Configuration Western Pressurized Water Reactor PWR POWER interviewed James Klein, maintenance FIN (fix-it-now) superintendent and ice condenser system subject matter expert at the Tennessee Valley Authority’s (TVA’s) Watts Bar nuclear plant.

An evaluation of a Pressurized Water Reactor (PWR) ice condenser containment was performed. In this evaluation, simplified containment event trees (SCETs) were developed that utilized the vast storehouse of information generated by the NRC's Draft NUREG effort.

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Vulnerabilities of Ice Condenser Containments. Nuclear power plants in the U.S. are required to have robust reactor containment buildings. The main purpose of these structures is to prevent the release of large quantities of radioactive materials in the event of a reactor core.

Based on the change in large early containment failure frequency (LERF) for both PWR ice condenser and BWR Mark III containment designs and on the change in risk (as measured by man-rem/ year) for the ice condenser designs, this issue passed the screening criteria and went on to the technical assessment stage.

The passive containment cooling system (PCCS) is one of the main passive safety systems in the advanced pressurized water reactor (APWR), which will utilize natural phenomena to remove the heat released from the reactor to the environment during the postulated design basic accidents for preventing the overpressure of the containment shell.

The example provided in the calculations is executed mainly by means of the data provided in the Safety Analysis Report, SAR, of an existing plant, the Indian Point Unit 3, IP3. The work is organized as follow: Sections 2 and 3 of this paper give an overview of the different types of containment built in the Size: KB.

Sequoyah ˇs nuclear reactors utilize ˝ice condenser ˛ containment structures. Ice condenser nuclear reactors utilize baskets of ice to reduce heat and pressure in the event of an accident, preventing damage to the containment and leaks of radioactive steam.

Typical nuclear power plants have concrete containment several feet thick,File Size: KB. @article{osti_, title = {Accident management information needs}, author = {Hanson, D J and Ward, L W and Nelson, W R and Meyer, O R}, abstractNote = {The tables contained in this Appendix A describe the information needs for a pressurized water reactor (PWR) with a large, dry containment.

To identify these information needs, the branch points in the safety objective. Power and the French company Dalkia.

Outline of plant facilities Table 1 shows the main equipment of heat source components at the plant. During the first stage of construction, MHI delivered one 3-MW centrifugal chiller, two 7-MW centrifugal chillers, and two MW ice storage systems. During the plant design, MHI made every effort toFile Size: KB.

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an operator is using a sling psychrometer to measure dry and wet bulb temperature on a roof of a building where the cooling tower is located.

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Cook is a two unit Ice Condenser Pressurized Water Reactor (Westinghouse). Unit 1 has completed 22 cycles and refueling outages and Unit 2 has completed 18 cycles. The Industrial Refrigeration Consortium is a collaborative effort between the University of Wisconsin Madison and industry. Our goal is to improve the safety, efficiency, and productivity of industrial refrigeration systems and technologies.

A containment building, in its most common usage, is a reinforced steel or lead structure enclosing a nuclear is designed, in any emergency, to contain the escape of radioactive steam or gas to a maximum pressure in the range of to kPa (40 to 80 psi) [citation needed].The containment is the fourth and final barrier to radioactive release (part of a.

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