Contribution to the numerical modelling of heat exchange in the steam generator of a small modular reactor (SMR)

2021 ◽  
Author(s):  
A. Elorf ◽  
A. Jean-Marie
Keyword(s):  
Heat Exchange ◽  
Numerical Modelling ◽  
Steam Generator ◽  
Small Modular Reactor

MODELING THE EFFECT OF HEAT EXCHANGE ON THE EFFICIENCY OF A THERMOELECTRIC COOLER

2020 ◽  
Vol 2 ◽  
pp. 132-135
Author(s):  
O.I. MARKOV
Keyword(s):  
Numerical Calculation ◽  
Heat Exchange ◽  
Solid State ◽  
Numerical Modelling ◽  
Temperature Difference ◽  
Maximum Temperature ◽  
Thermoelectric Cooler ◽  
Maximum Temperature Difference ◽  
Peltier Cooler ◽  
Account Heat

Numerical modelling thermal and thermoelectric processes in a branch of solid–state thermoelectric of Peltier cooler is performed, taking into account heat exchange by convection and radiation. The numerical calculation of the branch was carried out in the mode of the maximum temperature difference.

Numerical Modelling of Remote Field Eddy Current Testing of Steam Generator Tubes

2021 ◽  
pp. 239-248
Author(s):  
Ranjani Jayaraman ◽  
J. Selva Solomon ◽  
N. Sridhar ◽  
Chitti Venkata Krishnamurthy ◽  
Kavitha Arunachalam
Keyword(s):  
Numerical Modelling ◽  
Steam Generator ◽  
Eddy Current ◽  
Eddy Current Testing ◽  
Current Testing ◽  
Steam Generator Tubes

Effect of Sludge on the Stress–Strain State of Heat-Exchange Tubes of a Steam Generator

2019 ◽  
Vol 55 (1) ◽  
pp. 86-94 ◽  
Author(s):  
P. Z. Lugovoi ◽  
A. P. Shugailo ◽  
Ya. D. Kruglyi ◽  
A. M. Kolupaev
Keyword(s):  
Heat Exchange ◽  
Steam Generator ◽  
Strain State ◽  
Stress Strain ◽  
Stress Strain State

F310 DAMAGE PROBABILITY OF THE STEAM GENERATOR HEAT EXCHANGE PIPELINES IN VVER NPP

2003 ◽  
Vol 2003.3 (0) ◽  
pp. _3-427_-_3-432_
Author(s):  
V. I. Baranenko ◽  
S. G. Oleynik ◽  
V. N. Merkushev ◽  
O. E. Kostyukov ◽  
O. A. Belyakov ◽  
...  
Keyword(s):  
Heat Exchange ◽  
Steam Generator ◽  
Damage Probability

The Water Ingress Mass Analysis on Steam Generator Heat-Exchange Tube Rupture Accident of High Temperature Gas-Cooled Reactor

2009 ◽  
Author(s):  
Yan Wang ◽  
Yanhua Zheng ◽  
Fu Li ◽  
Lei Shi ◽  
Zhiwei Zhou
Keyword(s):  
High Temperature ◽  
Heat Exchange ◽  
Steam Generator ◽  
Mechanical Load ◽  
Radioactive Isotopes ◽  
Primary Circuit ◽  
Secondary Circuit ◽  
Water Ingress ◽  
Heat Exchange Tube ◽  
High Temperature Gas

The module high temperature gas-cooled reactor (HTGR) is an advanced reactor with high safety level. The steam generator heat-exchange tube rupture (SGTR) accident (or water ingress accident) is an important and particular accident which will result in water ingress to the primary circuit of reactor. Water ingress may, in turn, result in chemical reaction of graphite fuel and structure with water, causing release of radioactive isotopes and generation of explosive gaseous in large quantity. The analysis of SGTR is significant for verifying the inherent safety characteristics of HTGR. One of the key factors is to estimate the amount of water ingress mass which is used to evaluate the severity of the accident consequence. The 200MWe high temperature gas-cooled reactor, which is designed by the Institute of Nuclear and New Energy Technology of Tsinghua University, is selected as an example to analyze. The accident scenarios of double-ended rupture of both single and two heat-exchange tubes at the inlet and outlet of steam generator are simulated respectively by RETRAN-02. The results show that the amount of water ingress mass is related to the break location, the number of ruptured tubes (or the break size). The greater the number of ruptured tubes or the break size, the larger the amount of water ingress mass. It is important to design the draining pipe line with reasonable diameter, which should be optimized based on economy and safety considerations for preventing large water ingress to the reactor primary circuit, restricting the change rate of mechanical load on SG, and reducing the radioactive isotopes release to the secondary circuit.

scholarly journals METHOD AND RESULTS OF HYDRAULIC CALCULATION OF THE HEAT EXCHANGE SURFACE OF THE ONCE-THROUGH STEAM GENERATOR

2021 ◽  
Vol 1 (63) ◽  
pp. 60-77
Author(s):  
V. Kravchenko ◽  
◽  
Xiaolong Zhou ◽  
Keyword(s):  
Heat Exchange ◽  
Hydraulic Resistance ◽  
Steam Generator ◽  
Structural Parameters ◽  
Hydraulic Calculation ◽  
Working Fluid ◽  
Steam Generators ◽  
Small Modular Reactors ◽  
Heat Exchange Surface ◽  
Exchange Surface

Ukraine with her developed machine-building potential can take the deserving place in the production of small modular reactors. One of basic elements of small modular reactors equipment is steam generator. Among different types a deserving place is occupied by once-through steam generator. small modular reactors can exemplify to transport nuclear installation, for example KLT-40S. The calculation of hydraulic resistance is included in designing of steam generators, that it is necessary for the choice of pumps and optimization of structural parameters. In the presented article methodology of hydraulic calculation of once-through steam generator is examined with the coiling surface of heating. As a result of analysis of literature formulas were selected for the calculation of hydraulic resistance for four modes of flow: transverse flow of the coolant over horizontal coils, movement in bent tubes of a single-phase working fluid, boiling water and superheated steam. Results over of calculation of steam generators are brought by power 45 МВт with different structural parameters: diameter of coils, horizontal and vertical pitches of coils location in a bunch, speed of feedwater and coolant. The got results were verified by comparing to data of calculation on the code of ASPEN-TECH. It was found out as a result of research that increase of diameter of coils, as well as the increase of pitches of coils location in a bunch does not reduce hydraulic resistances, as expected, but increases them as a result of worsening of heat exchange and, accordingly, increase of heat-exchange surface. The increase of speed of coolant results in the height of resistance on the side of coolant and does not influence on resistance of working body. The increase of speed of feedwater increases resistance on the side of working fluid and does not influence on resistance of coolant.

Steam Generator Secondary Side Chemical Cleaning During Reactor Plant Cooling Down

2013 ◽  
Author(s):  
Xiaojiao Xia ◽  
Juhua Wen ◽  
Weigang Ma
Keyword(s):  
Heat Exchange ◽  
Steam Generator ◽  
Exchange Capacity ◽  
General Corrosion ◽  
Test Results ◽  
Steam Generators ◽  
Chemical Cleaning ◽  
Safety Test ◽  
Cleaning Technology ◽  
Secondary Side

For safe and reliable operation of NPP steam generators, it is required to remove the sludge from heat exchanging tubes and steam generator (SG) volume in due time. Chemical cleaning technology of SG secondary side during NPP cooling down will be used in Tianwan NPP, which was used to remove iron and copper oxides from steam generators secondary side in Russia NPPs and to resume the heat exchange capacity of heat exchange tubes. To validate and evaluate the effectiveness and safety of the SG cleaning formula during NPP cooling down provided by Russia (RF) for Tianwan NPP, cleaning effective tests and safety tests were done in autoclave with the chemical cleaning process parameters simulated. To compared with RF, cleaning effective tests and safety tests were done with A3B1 under the same condition. Cleaning effective test results showed that the simulated sludge for Tianwan NPP can be more effectively dissolved and removed with A3B1 than with RF. Cleaning safety test results showed that the general corrosion amount of 0Cr18Ni10Ti stainless steel was very low but the general corrosion amount of SA508-III steel was high both with A3B1 formula and the formula provided by Russia.

An Overview of the Westinghouse Small Modular Reactor

2011 ◽  
Author(s):  
Robert J. Fetterman ◽  
Alexander W. Harkness ◽  
Matthew C. Smith ◽  
Creed Taylor
Keyword(s):  
Steam Generator ◽  
Pressure Vessel ◽  
Straight Tube ◽  
Plant Design ◽  
Operating Cycle ◽  
Pressurized Water ◽  
Power Sources ◽  
Containment Vessel ◽  
Small Modular Reactor ◽  
Safety Systems

The Westinghouse Small Modular Reactor (SMR) incorporates an integral pressurized water reactor (iPWR) design in which all components associated with the nuclear steam supply system are housed within one pressure vessel. The Westinghouse SMR design also utilizes many of the key features from the AP1000® plant, including passive safety systems. The Westinghouse SMR will be fueled by a derivative of the successful 17×17 Robust Fuel Assembly (RFA) product. An 89 assembly core with an active height of 8 feet will provide a 24 month operating cycle with a power output of 800 MWt. Derived from the AP1000 plant and adapted to operate inside the reactor pressure vessel, 37 control rod drive mechanisms provide reactor shutdown and reactivity control capabilities. Eight seal less pumps provide a nominal reactor coolant flow of 100,000 gallons per minute. An innovative evolution of a straight tube steam generator produces a saturated mixture that is delivered to a steam separating drum located outside of the containment vessel. The steam generator along with the integral pressurizer is attached to the reactor vessel with a single closure flange located near the center of gravity of the reactor assembly and is designed to be removed during refueling operations. Like the AP1000 plant, the Westinghouse SMR relies on the natural forces of gravity and natural circulation to provide core and containment cooling during accident conditions. The passive cooling systems provide sufficient heat removal for seven days without the need for offsite AC power sources. The Westinghouse SMR also includes traditional active components such as diesel generators and pumps; however these components are not required for the safe shutdown of the plant. At a diameter of 32 feet, approximately 25 of the Westinghouse SMR containment vessels can fit within the envelope of the AP1000 containment building. This compact containment will be completely submerged in water during power operation providing a heat sink for postulated accidents. For protection against external threats, the containment vessel and plant safety systems are located below ground level. At approximately one fifth the net electrical output of the AP1000 plant, the Westinghouse SMR is designed to address infrastructure challenges associated with replacing America’s aging fossil fuel plants by providing a safe, clean and reliable energy source. The challenges associated with economies of scale are offset with a compact and simplified plant design, rail shippable components and modular construction.

Sign in / Sign up

Export Citation Format

Share Document