Shutdown decay heat removal analysis

plant case studies and special issue : summary report

Publisher: Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission in Washington, DC

Written in English
Published: Downloads: 183
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Subjects:

  • Heat -- Transmission -- Analysis.,
  • Nuclear reactors -- United States -- Cooling -- Case studies.,
  • Light water reactors -- United States -- Safety measures.

Edition Notes

Statementprepared by D.M. Ericson, Jr. ... [et al.].
ContributionsEricson, David M., Sandia National Laboratories., U.S. Nuclear Regulatory Commission. Division of Safety Issue Resolution.
The Physical Object
Pagination1 v. (various pagings) :
ID Numbers
Open LibraryOL15362174M

Passive nuclear safety is a design approach for safety features, implemented in a nuclear reactor, that does not require any active intervention on the part of the operator or electrical/electronic feedback in order to bring the reactor to a safe shutdown state, in the event of a particular type of emergency (usually overheating resulting from a. This work investigates the potential of post-LOCA decay heat removal from a GFR core to a heat sink using an external convection loop. A model was developed in the form of the LOCA-COLA (Loss of Coolant Accident - Convection Loop Analysis) computer code as a means for 1D steady state convective heat transfer loop analysis. Technical Report: Simulation of decay heat removal by natural convection in a pool type fast reactor model-ramona-with coupled 1D/2D thermal hydraulic code system Title: Simulation of decay heat removal by natural convection in a pool type fast reactor model-ramona-with coupled 1D/2D thermal hydraulic code system. The SSR operates at much higher temperatures so this heat can be rapidly transferred away from the core. In the event of a reactor shutdown and failure of all active heat-removal systems in the SSR, decay heat from the core dissipates into air cooling ducts around the .

To prevent increased temperatures and damage to the reactor core, the decay heat must continually be removed, even after shutdown. Numerous systems and back-up emergency core cooling systems are provided to ensure that reactor cooling water continues to flow through the reactor core to remove decay heat, even after the reactor has been shut. Decay heat is removed by the relief valves to the suppression pool. The suppression pool is a 1 million gallon supply of water which acts as an emergency cooling water source, and also a temporary heat sink. The suppression pool is cooled using the residual heat removal . @article{osti_, title = {Passive residual heat removal system for nuclear power plant}, author = {Bevilacqua, F and Callaghan, V M and Van Fleet, J L}, abstractNote = {An enclosed reservoir is sized and located in relation to the steam generator of a pressurized water nuclear reactor power plant so that upon a loss of feedwater flow to the steam generator, a gravity induced.   § Licensee event report system. (a) Reportable events. (1) The holder of an operating license under this part or a combined license under part 52 of this chapter (after the Commission has made the finding under § (g) of this chapter) for a nuclear power plant (licensee) shall submit a Licensee Event Report (LER) for any event of the type described in this paragraph .

  IE Circular No. , Inadequate Decay Heat Removal During Reactor Shutdown SSINS No.: Accession No.: IEC UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C. J IE Circular No. INADEQUATE DECAY HEAT REMOVAL DURING REACTOR SHUTDOWN Background: Following several losses of decay heat removal . Calculation of Decay Heat The amount of decay heat being generated in a fuel assembly at any time after shutdown can be calculated in two ways. The first way is to calculate the amount of fission products present at the time of shutdown. This is a fairly detailed process and is dependent upon power history. Passive Safety Systems and Natural Circulation in Water Cooled Nuclear Power Plants. Passive Safety Systems and Natural Circulation in Water Cooled Nuclear Power Plants. AFGHANISTAN ALBANIA ALGERIA ANGOLA ARGENTINA ARMENIA AUSTRALIA AUSTRIA PASSIVE SAFETY SYSTEMS FOR CORE DECAY HEAT REMOVAL Pre-pressurized core flooding tanks. However, since there was no decay heat removal function, the suppression pool temperature continued to rise and reached °C (°F) ~14 hours after the tsunami struck. During this time, because of the extraordinary efforts of the operating staff, Units 1, 2, and 4 recovered their decay heat removal functions; e.g., electrical cables were.

Shutdown decay heat removal analysis Download PDF EPUB FB2

Editorial Reviews. This report addresses events which take place either during cold shutdown with the residual heat removal system (RHRS) operating to remove decay heat, or during late stages of normal plant cooldown at the time when the RHRS is placed in service.

Events which occur during these periods are often prompted or made worse by complex. Get this from a library. Shutdown decay heat removal analysis of a combustion engineering 2-loop pressurized water reactor: case study.

[Wallis R Cramond; David M Ericson; Gary A Sanders; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Reactor and Plant Systems.; Sandia National Laboratories.]. Get this from a library. Shutdown decay heat removal analysis: plant case studies and special issue: summary report.

[David M Ericson; Sandia National Laboratories.; U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulatory Research. Division of Safety Issue Resolution.;]. Get this from a library. Shutdown decay heat removal analysis of a Babcock and Wilcox pressurized water reactor: case study.

[Wallis R Cramond; David M Ericson; Gary A Sanders; U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Safety Review and Oversight.; Sandia National Laboratories.].

Get this from a library. Shutdown decay heat removal analysis of a General Electric BWR4/Mark I: case study. [Steven W Hatch; David M Ericson; Gary A Sanders; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Reactor. Decay heat removal is performed by combination of steam generator and DHRS units afterward.

At the later stage, the simulation shows that after Shutdown decay heat removal analysis book of reactor trip, the temperature and pressure in the primary system tends to decrease which shows that the DHRS capable to remove decay heat from the primary system and maintain safe : Susyadi, Andi S.

Ekariansyah, Hendro Tjahjono, D. Sony Tjahyani. Decay heat in the SMART reactor is generated mainly from short-lived fission products; the fast decay of these radionuclides results in an extreme drop in the decay heat generation hours after shutdown.

In the first day after reactor shutdown, the ratio of decay heat to. The performed analysis demonstrated, that the decay heat from shutdown and partially reloaded reactor RBMK can by removed by natural circulation of air through fuel channels with the fuel assemblies, natural circulation of air through adjacent channels without fuel assemblies, heat removal from stem water piping by air ventilation in drum Cited by: 3.

Radioactivity and decay heat analysis of the MNSR with HEU and LEU fuels using the GETERA code Decay heat removal rate for the MNSR after reactor shutdown was investigated due Shutdown decay heat removal analysis book its.

Decay Heat Estimates for MNR 1 Introduction Decay heat removal is essential in preventing fuel overheating and possible fission product release. This report provides estimates of decay heat production for use in MNR safety analysis.

2 A Simple Expression for Decay HeatFile Size: KB. DECAY POWER AFTER SHUTDOWN If we want to take into consideration the operating time of a given core, and calculate the heat release after shutdown, we consider the time scale shown in Fig.

2 and adopt the following analysis. Figure2. Time sequence after reactor shutdown for decay heat calculation. Reactor power is P 0 in Size: KB. Shutdown decay heat removal analysis of a Combustion Engineering 2-loop pressurized water reactor: Case study Technical Report Cramond, W R ; Ericson, Jr, D M ; Sanders, G A This is one of six case studies for USI A Decay Heat Removal (DHR) Requirements.

Post shutdown decay heat removal in a fast reactor is one of the most important safety functions which must be accomplished with a very high reliability. To achieve high reliability, the fast breeder reactor design has emphasized on passive or near passive decay heat removal systems utilizing the natural convection in the heat removal by:   Loss of flow and heat sink accident is one of the most serious accidents for SFRs.

Therefore, the decay heat removal capacity after emergency shutdown is of great importance. This paper has developed a one-dimensional code named Decay heat Removal Analysis Code for Sodium-cooled Fast Reactor (DRAC-SFR) to analyze the decay heat removal : Ping Song, Dalin Zhang, Tangtao Feng, Shibao Wang, Yapei Zhang, Mingjun Wang, Suizheng Qiu, G.

Post shut-down decay heat removal from nuclear reactor core by natural convection loops in sodium pool. (SGDHRS) which aids to remove decay heat after shut down phase. Immediately after reactor shut down the fission products in the core continue to generate heat due to beta decay which exponentially decreases with by: 3.

Post shutdown decay heat removal in a fast reactor is one of the most important safety functions which must be accomplished with a very high reliability.

A MODEL FOR THE ANALYSIS OF LOSS OF DECAY HEAT REMOVAL ACCIDENT IN MTR POOL TYPE RESEARCH REACTORS. The loss of shutdown heat removal accident is a subject of great importance for the. In this study, a typical VVER reactor residual heat removal system has been evaluated using RELAP5 thermal hydraulic loop code during cool-down.

Reactor cooling down starts from hot state temperature and then continues to the cool-down stages with °C and 70 °C, by: 6. A set of baseline expectations was established from NUREG, "Regulatory and Backfit Analysis: Unresolved Safety Issue A, Shutdown Decay Heat Removal Requirements," Novemberand NUREG/CR, "Shutdown Decay Heat Removal Analysis: Plant Case Studies and Special Issues," Apriland the actual outcomes were obtained from the.

"Shutdown Decay Heat Removal Analysis: Plant Case Studies and Special Issues," Apriland the actual outcomes were obtained from the individual plant examinations and individual plant examination of external events In the areas of total core damage frequency, decay heat removal risk categories and decay heat removal vulnerability.

Get this from a library. Regulatory and backfit analysis: unresolved safety issue A, shutdown decay heat removal requirements. [U.S. Nuclear Regulatory Commission. Division of Safety Issue Resolution.;]. Heat Exchanger Design hand Book.

Post shutdown decay heat removal in a fast reactor is one of the most important safety functions which must be accomplished with a very high reliability. There is an extra energy source known as decay heat, that contributes to thermal power in power operation, but dominates in shutdown mode.

Decay heat is the heat released as a result of radioactive decay of fission products accumulated in the fuel.

To understand the processes that are after reactor shutdown. Covers the fundamentals of neutronic analysis for nuclear reactor systems to help understand nuclear reactor theory he performed thermal hydraulic analysis and natural circulation for Inherent Shutdown Heat Removal System (ISHRS) in the core of a Liquid Metal Fast Breeder Reactor (LMFBR).

and Laser Activated Radioactive Decay. He is the Brand: Springer International Publishing. Introduction The principal objectives of the present study are; i) to develop methodologies applicable to the analysis of the decay heat removal (DHR) with failures in shutdown heat removal system, and ii) to investigate the coolability of the re actor core under the adverse thermal conditions postulated in a typical loop type liquid metal.

Nuclear Data Requirements for Decay Heat Calculations 67 1. INTRODUCTION Neutron-induced fission within the fuel of a reactor core, and the subsequent conversion of mass to energy constitutes a principal means of generating power.

The resulting energy arises from the following phenomena: kinetic energies of the fission products and neutrons. The paper discusses possibility of heat removal from the RBMK core at shutdown condition by natural circulation of water (1) and air (2) inside the fuel channels.

This system is known as either shutdown cooling or residual heat removal and can be configured in several operating modes to remove decay heat. For example, suppression pool cooling could be used as an indirect decay heat removal system, removing heat from the reactor vessel via the SRVs and the suppression pool.

When one of these shuts down, decay heat should be generated in an amount around 50 MW (or more) immediately after shutdown based on the % heat of operational output.

50 MW is an immense amount of power (enough to power ab average U.S. homes) and I would think this would well exceed the rated output of even the largest (or a bank.

Decay heat is the heat released as a result of radioactive decay. This heat is produced as an effect of radiation on materials: the energy of the alpha, beta or gamma radiation is converted into the thermal movement of atoms.

Decay heat occurs naturally from decay of long-lived radioisotopes that are primordially present from the Earth's formation. Decay heat may decrease to about 2% of the pre-shutdown power level within the first hour after shutdown and to 1% within the first day.

Decay heat will continue to decrease, but it will decrease at a much slower rate. Decay heat will be significant weeks and even months after the reactor is shut down.The adequacy of shutdown-decay-heat removal in pressurized water reactors (PWRs) is currently under investigation by the Nuclear Regulatory Commission.

One part of this effort is the review of feed-and-bleed procedures that could be used if the normal cooling mode .Decay heat removal using feed-and-bleed method. The feed-and-bleed method for decay heat removal becomes necessary method in some pressurized water reactors (PWRs) if there is a loss of steam generator heat sink capability.