scholarly journals Conceptual Design of Irradiation Facility with 6 MeV and 7 MeV Gamma Rays at the JSI TRIGA Mark II Research Reactor

2020 ◽  
Vol 225 ◽  
pp. 04014
Author(s):  
Andrej Žohar ◽  
Anže Pungerčič ◽  
Klemen Ambrožič ◽  
Vladimir Radulović ◽  
Anže Jazbec ◽  
...  
Keyword(s):  
Decay Rate ◽  
Conceptual Design ◽  
Gamma Rays ◽  
Research Reactor ◽  
Cooling System ◽  
Cooling Water ◽  
Decay Rates ◽  
Central Channel ◽  
Water Activation ◽  
Triga Mark Ii

Activated cooling water in nuclear facilities can present a significant radiation source around primary cooling system causing radiation damage to electrical components, increasing doses to personnel and in the case of fusion facilities additional heating to superconducting coils. As there are only few sources of gamma rays with energies in the range of 6 MeV and 7 MeV an irradiation system using activated cooling water as the source of energetic gamma rays is proposed at the Jožef Stefan Institute (JSI) TRIGA Mark II research reactor. Two different conceptual designs, one utilizing central irradiation channel and one utilizing radial piercing port for water activation, are presented and analysed in the paper. Despite an order of magnitude higher water activation in central channel compared to radial piercing port the 16N decay rate in the irradiation facility is comparable between both design (order of 108 decays per second) due to longer transient time from central channel to irradiation facility. In the irradiation facility the expected biological dose rates due to the 16N decay rate are in order of several mSv/h. From the results he conceptual design utilizing the radial piercing port currently presents the best option for the irradiation facility due to the simpler design of the irradiation loop, already present shielding of the loop and comparable number of 16N decay rates to central channel.

scholarly journals OPTIMASI DESAIN TERMOHIDROLIKA TERAS DAN SISTEM PENDINGIN REAKTOR RISET INOVATIF DAYA TINGGI

2015 ◽  
Vol 17 (3) ◽  
pp. 127 ◽  
Author(s):  
Endiah Puji Hastuti ◽  
Muhammad Subekti ◽  
Sukmanto Dibyo ◽  
M. Darwis Isnaini
Keyword(s):  
Conceptual Design ◽  
High Power ◽  
Research Reactor ◽  
Cooling System ◽  
Flow Boiling ◽  
Reactor Core ◽  
System Optimization ◽  
Hydraulic Calculation ◽  
Design System ◽  
Steady State Condition

ABSTRAK OPTIMASI DESAIN TERMOHIDROLIKA TERAS DAN SISTEM PENDINGIN REAKTOR RISET INOVATIF DAYA TINGGI. Implementasi reaktor inovasi telah diterapkan pada berbagai reaktor riset baru yang saat ini sedang dibangun.  Pada saat ini BATAN sedang merancang desain konseptual reaktor riset daya tinggi yang telah masuk pada tahap optimasi desain. Spesifikasi desain konseptual reaktor riset inovatif adalah reaktor tipe kolam berpendingin air dan reflektor D2O. Teras reaktor memiliki kisi 5x5 dengan 16 bahan bakar dan 4 batang kendali. Teras reaktor berada di dalam tabung berisi D2O yang berfungsi sebagai posisi iradiasi. Daya reaktor 50 MW didesain untuk membangkitkan fluks neutron termal sebesar 5x1014 n/cm2s. Teras reaktor berbentuk kompak dan menggunakan bahan bakar U9Mo-Al dengan tingkat muat uranium 7-9 gU/cm3. Desain termohidrolika yang mencakup pemodelan, perhitungan dan analisis kecukupan pendingin dibuat sinergi dengan desain fisika teras agar keselamatan reaktor terjamin. Makalah ini bertujuan menyampaikan hasil analisis perhitungan termohidrolika teras dan sistem reaktor riset inovatif pada kondisi tunak. Analisis dilakukan menggunakan program perhitungan yang telah tervalidasi, masing-masing adalah Caudvap, PARET-ANL, Fluent dan ChemCad 6.4.1. Hasil perhitungan menunjukkan bahwa pembangkitan panas yang tinggi dapat dipindahkan tanpa menyebabkan pendidihan dengan menerapkan desain teras reaktor bertekanan, di samping itu desain awal komponen utama sistem pembuangan panas yang terintegrasi telah dilakukan, sehingga konseptual desain termohidrolika RRI-50 dapat diselesaikan. Kata kunci : reaktor riset inovatif, Caudvap, PARET-ANL, Fluent, ChemCad 6.4.1.  ABSTRACT THERMALHYDRAULIC DESIGN AND COOLING SYSTEM OPTIMIZATION OF THE HIGH POWER INOVATIVE RESEARCH REACTOR. Reactor innovation has been implemented in a variety of new research reactors that currently are being built. At this time BATAN is designing a conceptual design of the high power research reactor which has entered the stage of design optimization. The conceptual design specifications of the innovative research reactor is a pool type reactor, water-cooled and reflected by D2O. The reactor core has a 5 x 5 grid with 16 fuels and 4 control rods, which is inserted into a tube containing D2O as an irradiation position. Reactor power of 50 MW is designed to generate thermal neutron flux of 5x1014 n/cm2s. The compact core reactor is using U9Mo-Al fuel with uranium loading of 7-9 gU/cm3. Thermal hydraulic design includes modeling, calculation and analysis of the adequacy of coolant created synergy with the physical design of reactor safety. This paper aims to deliver the results of thermal hydraulic calculation and system design analysis at steady state condition. The analysis was done using various calculation programs that have been validated, i.e. Caudvap, PARET-ANL, Fluent and ChemCad 6.4.1. The calculation results show that the heat generation can be transfered without causing a two phase flow boiling by applying pressurized reactor core design, while the main components of initial design system with an integrated heat dissipation has been done, to complete the conceptual design of the RRI-50 thermalhydraulics. Keywords : inovative research reactor, Caudvap, PARET-ANL, Fluent, ChemCad 6.4.1.

Decommissioning the Georgia Tech Research Reactor

2001 ◽  
Author(s):  
Robert Eby ◽  
Lark Lundberg ◽  
Steve Marske ◽  
Nolan Hertel ◽  
Rod Ice
Keyword(s):  
Nuclear Reactor ◽  
Research Reactor ◽  
Cooling System ◽  
Cooling Water ◽  
Nuclear Regulatory Commission ◽  
Georgia Tech ◽  
Spent Fuel ◽  
Survey Report ◽  
Institute Of Technology ◽  
Regulatory Commission

Abstract The Georgia Tech Research Reactor (GTRR) is a 5-megawatt (MW) heavy-water-cooled nuclear reactor located on the Georgia Institute of Technology (Georgia Tech) campus in downtown Atlanta, Georgia. On July 1, 1997, Georgia Tech administration notified the U.S. Nuclear Regulatory Commission (NRC) of their intent to decommission the GTRR. In the summer of 1999, the NRC issued a license amendment to decommission the GTRR in accordance with NRC’s Regulatory Guide 1.86. In the spring of 1999, Georgia Tech and the State of Georgia contracted CH2M HILL to serve as the Executive Engineer to manage the decommissioning project. Later in the summer of 1999, the IT Corporation was selected as the Decommissioning Contractor. The Decommissioning Contractor began the dismantlement process at the Georgia Tech site in November, 1999. By February, 2000, reactor support systems such as the primary and secondary cooling water systems, and the bismuth cooling system were removed and packaged for off-site disposal. Reactor internals were removed in April, 2000. Removal of the bioshield occurred from May through November, 2000. Throughout January, 2001, various concrete structures, including the Spent Fuel Storage Hole, were decontaminated. Dismantlement and decontamination activities were completed by April, 2001. The Final Survey Report to the NRC is planned to be submitted to the NRC December, 2001, 2001. Final license termination by the NRC is anticipated in the spring of 2002.

scholarly journals Comparison between measurement and calculations for a 14 MeV neutron water activation experiment

2020 ◽  
Vol 239 ◽  
pp. 21002
Author(s):  
F. Andreoli ◽  
M. Angelone ◽  
A. Colangeli ◽  
U. Besi Vetrella ◽  
S. Fiore ◽  
...  
Keyword(s):  
Gamma Rays ◽  
Cooling Water ◽  
Nuclear Data ◽  
Monte Carlo Code ◽  
First Wall ◽  
Nuclear Heat ◽  
Nuclear Data Library ◽  
Water Activation ◽  
Calculation Results ◽  
Dependent Transport

The nuclear heat loads due to gamma rays emitted from the decay of 16N and delayed neutrons from17N, generated by the activation of water in cooling circuits, are critical for ITER design. The assessment of nuclear heating from activated water is complex; it requires temporal and spatial dependent transport and activation calculations taking into account variation of irradiation, water flow conditions and cooling circuits’ parameters. A water activation experiment has been recently conducted at the14 MeV Frascati Neutron Generator (FNG) in order to validate the methodology for water activation assessment used for ITER and to reduce the safety factors applied to the calculation results, which have a large impact on the schedule, commissioning and licensing. Water circulating inside an ITER First Wall (FW) mock-up was irradiated with 14 MeV neutrons and then measured using a large CsI scintillator detector. The system consists of a closed water loop where the cooling water, transiting through an ITER FW mock-up, is irradiated by FNG. The induced 16N activity via 14 MeV neutrons interactions with 16O via the 16O(n,p)16N reaction is measured in a dedicated counting station via an expansion volume. The water then passes to a much larger holding delay tank, and after several 16N half-lives decay time, it is then recirculated and exposed again to neutrons in the ITER First Wall (FW) mock-up. The measured 16N activity is obtained measuring the emitted characteristic 6.13 and 7.12 MeV gamma-rays. Calculations were performed in an accurate model of the FW mock-up using the MCNP Monte Carlo code and FENDL-3.1 nuclear data library to obtain the predicted flux impinging on the water. The EASY-2007 inventory code was used to predict the 16N activity. In this work, a comparison between measurements and calculations is reported together with associated uncertainty analysis.

ANALYSIS OF COMPETING VARIANTS OF AIR CONDITIONING SYSTEMS WITHOUT AIR EXTRACTION FROM ENGINES AT THE STAGE OF PASSENGER AIRCRAFT ONBOARD SYSTEMS CONCEPTUAL DESIGN

2019 ◽  
Vol 6 (3) ◽  
pp. 80-85
Author(s):  
Denis Igorevich Smagin ◽  
Konstantin Igorevich Starostin ◽  
Roman Sergeevich Savelyev ◽  
Anatoly Anatolyevich Satin ◽  
Anastasiya Romanovna Neveshkina ◽  
...  
Keyword(s):  
Conceptual Design ◽  
Air Conditioning ◽  
Research University ◽  
Cooling System ◽  
Fuel Efficiency ◽  
Air Cooling ◽  
Moscow Aviation Institute ◽  
Air Conditioning System ◽  
Low Efficiency ◽  
Air Conditioning Systems

One of the ways to achieve safety and comfort is to improve on-board air conditioning systems.The use of air cooling machine determines the air pressure high level at the point of selection from the aircraft engine compressor. Because of the aircraft operation in different modes and especially in the modes of small gas engines, deliberately high stages of selection have to be used for ensuring proper operation of the refrigeration machine in the modes of the aircraft small gas engines. Into force of this, most modes of aircraft operation have to throttle the pressure of the selected stage of selection, which, together with the low efficiency of the air cycle cooling system, makes the currently used air conditioning systems energy inefficient.A key feature of the architecture without air extraction from the main engines compressors is the use of electric drive compressors as a source of compressed air.A comparative analysis of competing variants of on-board air conditioning system without air extraction from engines for longrange aircraft projects was performed at the Moscow Aviation Institute (National Research University).The article deals with the main approaches to the decision-making process on the appearance of a promising aircraft on-board air conditioning system at the stage of its conceptual design and formulated the basic requirements for the structure of a complex criterion at different life cycle stages.The level of technical and technological risk, together with a larger installation weight, will require significant costs for development, testing, debugging and subsequent implementation, but at the same time on-board air conditioning system scheme without air extraction from the engines will achieve a significant increase in fuel efficiency at the level of the entire aircraft.

Assessment of thermal behavior of a cooling system to reduce thermal fatigue cracks in aluminum injection molds

2020 ◽  
pp. 75-86
Author(s):  
Sergio Antonio Camargo ◽  
Lauro Correa Romeiro ◽  
Carlos Alberto Mendes Moraes
Keyword(s):  
Thermal Fatigue ◽  
Cooling System ◽  
Fatigue Cracks ◽  
Cooling Water ◽  
Thermal Conditions ◽  
Thermal Gradients ◽  
Ansys Software ◽  
Cooling Systems ◽  
Thermal Fatigue Cracks ◽  
Number Of Cycles

The present article aimed to test changes in cooling water temperatures of males, present in aluminum injection molds, to reduce failures due to thermal fatigue. In order to carry out this work, cooling systems were studied, including their geometries, thermal gradients and the expected theoretical durability in relation to fatigue failure. The cooling system tests were developed with the aid of simulations in the ANSYS software and with fatigue calculations, using the method of Goodman. The study of the cooling system included its geometries, flow and temperature of this fluid. The results pointed to a significant increase in fatigue life of the mold component for the thermal conditions that were proposed, with a significant increase in the number of cycles, to happen failures due to thermal fatigue.

Hydraulic model of a water cooling system in a chemical plant

1988 ◽  
Vol 53 (4) ◽  
pp. 788-806
Author(s):  
Miloslav Hošťálek ◽  
Jiří Výborný ◽  
František Madron
Keyword(s):  
Flow Rate ◽  
Cooling System ◽  
Cooling Water ◽  
Graph Algorithm ◽  
Automatic Generation ◽  
Hydraulic Calculation ◽  
Return Flow ◽  
Flow Rates ◽  
Pressure Losses ◽  
Controlled Flow

Steady state hydraulic calculation has been described of an extensive pipeline network based on a new graph algorithm for setting up and decomposition of balance equations of the model. The parameters of the model are characteristics of individual sections of the network (pumps, pipes, and heat exchangers with armatures). In case of sections with controlled flow rate (variable characteristic), or sections with measured flow rate, the flow rates are direct inputs. The interactions of the network with the surroundings are accounted for by appropriate sources and sinks of individual nodes. The result of the calculation is the knowledge of all flow rates and pressure losses in the network. Automatic generation of the model equations utilizes an efficient (vector) fixing of the network topology and predominantly logical, not numerical operations based on the graph theory. The calculation proper utilizes a modification of the model by the method of linearization of characteristics, while the properties of the modified set of equations permit further decrease of the requirements on the computer. The described approach is suitable for the solution of practical problems even on lower category personal computers. The calculations are illustrated on an example of a simple network with uncontrolled and controlled flow rates of cooling water while one of the sections of the network is also a gravitational return flow of the cooling water.

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