Use of a natural circulation map for assessing PWR performance

D'Auria, Francesco Saverio; Frogheri, M

doi:10.1016/s0029-5493(02)00045-6

Cited by 33 publications

(7 citation statements)

References 4 publications

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“…2), includes the logical steps hereafter listed 1) Overview of previous experiments executed in PSB-VVER, part of the OECD Project (5) in progress, of similar experiments performed in other test facilities and of data available from NPP. This implied the selection of counterpart and of similar tests (6), (7), (8), (9) .…”

Section: The Procedures For Test Designmentioning

confidence: 99%

“…Moreover in the OECD database was also available a Natural Circulation (NC) test (17) carried out through stepwise reduction of the primary coolant inventory. The analysis of these experimental data (18) allowed the understanding about the relationship between natural circulation modes and the mass inventory and to provide information on the PSB-VVER natural circulation performance (and indirectly the VVER-1000 performance) using the natural circulation flow map and the database available at UNIPI (7) . Figure 6 shows the natural circulation map created by the envelop of ten experimental data obtained in six PWR simulators and putting them into a phase space (core mass flow rate over the core power versus residual Primary Side (PS) mass over PS volume).…”

Section: The Design Of the Psb-vver Experimentsmentioning

confidence: 99%

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The Design of PSB-VVER Experiments Relevant to Accident Management

Nevo

D'Auria

Mazzini

et al. 2008

JPES

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Experimental programs carried-out in integral test facilities are relevant for validating the best estimate thermal-hydraulic codes (1) , which are used for accident analyses, design of accident management procedures, licensing of nuclear power plants, etc. The validation process, in fact, is based on well designed experiments. It consists in the comparison of the measured and calculated parameters and the determination whether a computer code has an adequate capability in predicting the major phenomena expected to occur in the course of transient and/or accidents. University of Pisa was responsible of the numerical design of the 12 experiments executed in PSB-VVER facility (2) , operated at Electrogorsk Research and Engineering Center (Russia), in the framework of the TACIS 2.03/97 Contract 3.03.03 Part A, EC financed (3) . The paper describes the methodology adopted at University of Pisa, starting form the scenarios foreseen in the final test matrix until the execution of the experiments. This process considers three key topics: a) the scaling issue and the simulation, with unavoidable distortions, of the expected performance of the reference nuclear power plants; b) the code assessment process involving the identification of phenomena challenging the code models; c) the features of the concerned integral test facility (scaling limitations, control logics, data acquisition system, instrumentation, etc.). The activities performed in this respect are discussed, and emphasis is also given to the relevance of the thermal losses to the environment. This issue affects particularly the small scaled facilities and has relevance on the scaling approach related to the power and volume of the facility.

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Section: The Procedures For Test Designmentioning

confidence: 99%

Section: The Design Of the Psb-vver Experimentsmentioning

confidence: 99%

The Design of PSB-VVER Experiments Relevant to Accident Management

Nevo

D'Auria

Mazzini

et al. 2008

JPES

Self Cite

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“…A portion of it condenses and returns to the reactor core, thus the counter-current gas and liquid flow regime is present in the reactor's hot leg and SG. As a result, a possibly significant passive residual decay heat removal from the reactor's primary coolant system is established [1][2][3] . Reflux condensation can occur at high pressures 4-10 MPa, due to a loss of coolant accident (LOCA) during normal plant operation [4][5][6][7][8] or at containment pressures due to loss of residual heat removal (RHR) system during a mid-loop inventory operation [9][10][11] .…”

Section: Introductionmentioning

confidence: 99%

The use of a novel gradient heat flux sensor for characterization of reflux condensation

Janasz

Prasser

Suckow

et al. 2022

Nuclear Engineering and Design

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“…The NC in a Pressurized Water Nuclear Reactors (PWR) occurs due to the presence of the heat source (core) and the heat sink (SGs). In a gravity environment, with core located at a lower elevation than steam generators, those driving forces generate a flowrate suitable for removing nuclear fission decay power [1]. At present, the NC core power removal capability is only exploited for accident situations, basically to demonstrate the inherent safety features of the plants.…”

Section: Introduction *mentioning

confidence: 99%

Investigation of the Natural Circulation FlowMap in NuScale Small Modular Reactor

Hosseini

Akbari

Shirani

et al. 2021

IJRRS

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Natural Circulation (NC) is an important mechanism in several industrial systems, and knowledge of its behavior is of interest to nuclear reactor design, operation and safety. The main safety issue in present nuclear reactors is to ensure the sufficient removal of decay heat during accidents. Recently, Small Modular Reactors (SMRs) have increasingly received a lot of positive attention and even several types of these reactors are in different stages of design and construction. Some of these SMRs, such as NuScale, are designed to operate in full NC mode as the main mechanism of the primary coolant drive force for heat removal from the reactor core during normal operation. The present study deals with the Natural Circulation Flow Map (NCFM) investigation in the NuScale reactor as one of the SMRs that operate in full NC mode. At first, NuScale reactor elements are modeled with RELAP5 thermal-hydraulic code. Then, after the verification of the steady-state modeling, the operational point of the NuScale reactor is indicated in NCFM that is based on the database of different PWR simulators (gathered from the experimental test facilities). The evaluation of Natural Circulation Performance (NCP) of this reactor has proved the good design of NCP during normal operation in comparing typical PWRs operations in high power cases.

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Use of a natural circulation map for assessing PWR performance

Cited by 33 publications

References 4 publications

The Design of PSB-VVER Experiments Relevant to Accident Management

The Design of PSB-VVER Experiments Relevant to Accident Management

The use of a novel gradient heat flux sensor for characterization of reflux condensation

Investigation of the Natural Circulation FlowMap in NuScale Small Modular Reactor

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