scholarly journals MODEL SIMULATION OF GEOMETRY AND STRESS-STRAIN VARIATION OF BATAN FUEL PIN PROTOTYPE DURING IRRADIATION TEST IN RSG-GAS REACTOR

2015 ◽  
Vol 21 (1) ◽  
Author(s):  
Suwardi Suwardi ◽  
Winter Dewayatna ◽  
Sungkono Sungkono ◽  
Ridwan Ridwan ◽  
M Rifai
Keyword(s):  
Thermal Expansion ◽  
Model Simulation ◽  
Test Facility ◽  
Strain Variation ◽  
Stress Strain ◽  
Ramp Test ◽  
Irradiation Test ◽  
Fuel Pin ◽  
Computation Data ◽  
Fuel Technology

MODEL SIMULATION OF GEOMETRY AND STRESS-STRAIN VARIATION OF BATAN FUEL PIN PROTOTYPE DURING IRRADIATION TEST IN RSG-GAS REACTOR*). The first short fuel pin containing natural UO2 pellet in Zry4 cladding has been prepared at the CNFT (Center for Nuclear Fuel Technology) then a ramp test will be performed. The present work is part of designing first irradiation experiments in the PRTF (Power Ramp Test Facility) of RSG-GAS 30 MW reactor. The thermal mechanic of the pin during irradiation has simulated. The geometry variation of pellet and cladding is modeled by taking into account different phenomena such as thermal expansion, densification, swelling by fission product, thermal creep and radiation growth. The cladding variation is modeled by thermal expansion, thermal and irradiation creeps. The material properties are modeled by MATPRO and standard numerical parameter of TRANSURANUS code. Results of irradiation simulation with 9 kW/m LHR indicates that pellet-clad contacts onset from 0.090 mm initial gaps after 806 d, when pellet radius expansion attain 0.015 mm while inner cladding creep-down 0.075 mm. A newer computation data show that the maximum measured LHR of n-UO2 pin in the PRTF 12.4 kW/m. The next simulation will be done with a higher LHR, up to ~ 25 kW/m.MODEL SIMULASI VARIASI GEOMETRI DAN STRESS-STRAIN DARI PROTOTIP BAHAN BAKAR PIN BATAN SELAMA UJI IRADIASI DI REAKTOR RSG-GAS. Pusat Teknologi Bahan Bakar Nuklir (PTBBN) telah menyiapkan tangkai (pin) bahan bakar pendek perdana yang berisi pelet UO2 alam dalam kelongsong paduan zircaloy untuk dilakukan uji iradiasi daya naik. Penelitian ini merupakan bagian dari perancangan percobaan iradiasi pertama di PRTF (Power Ramp Test Fasility) yang terpasang di reaktor serbaguna RSG-GAS berdaya 30 MW. Telah dilakukan pemodelan dan simulasi kinerja termal mekanikal pin selama iradiasi. Variasi geometri pelet dan kelongsong selama pengujian dimodelkan dengan memperhatikan fenomena ekspansi termal, densifikasi, bengkak oleh produk fisi, creep termal dan pertumbuhan iradiatif. Variasi sifat kelongsong dimodelkan oleh ekspansi termal, termal dan creep iradiatif. Sifat material dimodelkan dengan MATPRO serta parameter numerik standar kode TRANSURANUS. Hasil iradiasi simulasi dengan laju daya 9 kW/m, 75% data daya aksimal, menunjukkan bahwa awal kontak fisik pelet dengan kelongsong dari celah awal 0,09 mm terjadi setelah 806 hari, ketika ekspansi jejari pelet mencapai 0,015 mm sementara jejari kelongsong menyusut 0,075 mm. Data terbaru menunjukkan bahwa perhitungan maksimal dan pengukuran laju daya linear tangkai bahan bakar berisi UO2 alam di PRTF adalah 12,4 kW/m pada daya reactor 15 kW. Penelitian selanjutnya akan dilakukan dengan LHR lebih tinggi, sampai ~ 25 kW / m, bila daya reactor 30 MW. Keywords: iradiasi, pin bahan bakar, UO2 alam, geometri, tegangan-regangan.

scholarly journals IRRADIATION CHARACTERISTIC OF NATURAL UO2 PIN PHWR TARGET AT PRTF OF RSG – GAS CORE

2017 ◽  
Vol 19 (2) ◽  
pp. 71
Author(s):  
Jati Susilo ◽  
Tagor Malem Sembiring ◽  
Winter Dewayatna
Keyword(s):  
Neutron Flux ◽  
Nuclear Power ◽  
Irradiation Time ◽  
Thermal Power ◽  
Analytical Tool ◽  
Test Facility ◽  
Nuclear Power Reactor ◽  
Ramp Test ◽  
The Core ◽  
Fuel Pin

The RSG-GAS reactor has a facility for irradiation of the fuel pin of nuclear power reactor, namely Power Ramp Test Facility (PRTF). The in-house fabrication PWR fuel pin has prepared for irradiations in the PRTF facility, currently, while the various enrichments of uranium are analyzed using the analytical tool. In the next step, it is planned to perform an irradiation of PHWR fuel pin sample of natural UO2 in the facility. Before irradiation in the core, it should be analyzed by using the analytical tool. The objectives of this paper are to optimize irradiation time based on the burn-up, the generated linear power and the neutron flux level at the target. The 3-dimension calculations have been carried out by using the CITATION code in the SRAC2006 code system. Since the coolant of the reactor is H2O, the effect of moderators in the pressurized tube, H2O and D2O, were analyzed, as well as pellet radius and moderator densities. The calculation results show that the higher linear power as irradiation time longer is occurred preferably in the D2O moderator than in H2O. For the D2O moderator, the higher pressure affects the lower density and longer irradiation time. The maximum irradiation time for natural UO2 fuel pin with the pressurized D2O moderator is about 9.5×104 h, with the linear power of 700 W/cm. During irradiation, neutronic parameters of the core such as excess reactivity and ppf show a very small change, still far below design value.Keywords:  PHWR, Neutron Flux, Thermal Power, PRTF, RSG-GAS KARAKTERISTIK IRADIASI TARGET PIN PHWR UO2 ALAM PADA PRTF TERAS RSG – GAS. Teras RSG-GAS dilengkapi dengan fasilitas untuk uji iradiasi bahan bakar nuklir atau disebut dengan Power Ramp Test Fasility (PRTF). Saat ini sedang dilpersiapkan untuk dilakukan uji sample pin bahan bakar PWR pada fasilitas PRTF. Analisis terhadap uji iradiasi sample pellet UO2 dengan berbagai pengkayaan telah dilakukan menggunakan paket program komputer. Dimasa yang akan datang, uji iradiasi pin bahan bakar PHWR UO2 alam juga sedang dalam perencanaan. Sebelum diiradiasi di dalam teras, maka terlebih dahulu harus dilakukan analisis dengan menggunakan paket program komputer. Tujuan dari penelitian ini adalah optimasi uji iradiasi pin bahan bakar UO2 alam sebagai fungsi waktu iradiasi berdasarkan burn-up, daya linier dan fluks neutron. Perhitungan teras RSG-GAS dilakukan dengan paket program SRAC2006 modul CITATION dalam bentuk geometri 3 dimensi. Analisis dilakukan terhadap pengaruh penggunaan jenis moderator pada tabung tekan iradiasi (H2O dan D2O), perubahan ukuran pelllet UO2 dan perubahan besarnya densitas moderator D2O. Dari analisis hasil perhitungan diketahui bahwa semakin lama waktu iradiasi akan menghasilkan daya termal yang semakin besar jika menggunakan moderator D2O dibandingkan H2O. Semakin tinggi tekanan atau semakin kecil densitas moderator, maka akan menghasilkan daya termal yang semakin besar seiring bertambah lamanya waktu iradiasi. Batas maksimal waktu iradiasi untuk pin bahan bakar UO2 alam dengan moderator D2O bertekanan adalah sekitar 9,5×104 jam, dengan batasan daya linier desain kemampuan peralatan, 700 W/cm. Selama iradiasi, nilai parameter neutronik teras reaktor seperti reaktivitas lebih dan ppf hanya menunjukkan perubahan yang sangat kecil, masih jauh dibawah batas yang ditetapkan dalam desain.Kata kunci: PHWR, Fluks Neutron, Daya Termal, PRTF, RSG-GAS

scholarly journals Perhitungan Perubahan Reaktivitas Pada Reaktor Serba Guna G.A. Siwabessy Akibat Pengoperasian Power Ramp Test Facility

2019 ◽  
Vol 4 ◽  
pp. 121
Author(s):  
A Suparmi ◽  
Tuti Dwi Setyaningsih ◽  
Suharyana Suharyana ◽  
Fuad Anwar ◽  
Riyatun Riyatun
Keyword(s):  
Reactor Core ◽  
Test Facility ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Water Reactor ◽  
Ramp Test ◽  
Fuel Pin ◽  
Safe Limit ◽  
Reactor Operating ◽  
Test Fuel

<p><strong>Abstract: </strong>Power Ramp Test Facility (PRTF) is one of the irradiation facility contained in the Multipurpose Reactor GA Siwabessy. This facility is used to test the reactor fuel element pin-type Pressurized Water Reactor. As a result of the entry of foreign bodies cause changes reactor conditions, one of which is expressed with the amount of reactivity to assess the safety of the reactor due to the operation PRTF. PRTF operation simulation and calculation is done using software neutronics MCNP6. Test UO2 fuel enriched assumed at 5% with constant power reactor operating at 15 MW and test fuel pin placed on PRTF within 0, 20, 40, 60, 80, 100, 120, and 140 mm from the centre of the reactor core. Change of reactivity values required in order to secure the reactor, maximal value is 0,5%<em></em>.  The calculation were obtained at each position is (<em></em><em></em>;  <em></em>;  <em></em>; <em></em>;<em></em>; <em></em>; <em></em>; <em></em>). Change of reactivity values smaller than the safe limit. Therefore, the study of reactivity changes PRTF operation to test fuel pin is secure.</p><p><strong>Abstrak: </strong>Power Ramp Test Facility (PRTF) merupakan salah satu fasilitas iradiasi yang terdapat pada Reaktor Serba Guna G.A. Siwabessy. Fasilitas ini digunakan untuk menguji pin elemen bahan bakar reaktor tipe Pressurized Water Reactor. Akibat dari masuknya benda asing menyebabkan perubahan kondisi reaktor, salah satunya dinyatakan dengan besaran reaktivitas untuk mengkaji keselamatan reaktor akibat pengoperasian PRTF. Simulasi pengoperasian PRTF dan perhitungan netronik dilakukan menggunakan perangkat lunak MCNP6. Bahan bakar uji UO2 diasumsikan diperkaya sebesar 5% dengan daya operasi reaktor konstan sebesar 15 MW. Pin bahan bakar uji diletakkan pada PRTF berjarak 0, 20, 40, 60, 80, 100, 120, dan 140 mm dari arah pusat teras reaktor. Nilai perubahan reaktivitas yang dipersyaratkan agar reaktor aman adalah , sedangkan nilai perubahan reaktivitas dari penelitian pada masing-masing posisi dari pusat reactor adalah (;  ;  ; ;; ; ; ) . Nilai perubahan reaktivitas akibat masuknya pin bahan bakar di PRTF mempunyai nilai perubahan reaktivitas 1/10 kali lebih kecil daripada batas aman. Oleh karena itu, ditinjau dari kajian  nilai perubahan reaktivitas maka pengoperasian PRTF untuk uji pin bahan bakar adalah aman.</p>

Thermo-Mechanical Analysis of Chosen Epoxy Resins Used in Aviation Technology

2015 ◽  
Vol 1126 ◽  
pp. 187-193
Author(s):  
Kamil Prusak ◽  
Janusz Zmywaczyk ◽  
Piotr Koniorczyk ◽  
Jan Godzimirski ◽  
Marcin Cegła
Keyword(s):  
Thermal Expansion ◽  
Epoxy Resins ◽  
Loss Modulus ◽  
Testing Machine ◽  
Mechanical Analysis ◽  
Stress Strain ◽  
Temperature Range ◽  
Heating And Cooling ◽  
Tan Δ ◽  
Material Testing Machine

In this paper the results of storage modulus (E’), loss modulus (E’’) and damping parameter tan (δ)=E''/E' of epoxy resins Epidian 57 and L285 with curing agents Z1 and LH285, respectively are presented. In addition to this the stress-strain and thermal expansion characteristics of Epidian 53, 57 and L285 were obtained experimentally in order to compare Dynamic Mechanical Analysis (DMA) results. Temperature range of DMA investigations using Netzsch (Germany) DMA 242C analyzer was from-120 °C to +110 °C at the heating rate of 1 K/min with frequency of {0.1, 1, 10} Hz, respectively. Netzsch DIL 402C dilatometer was used to study the thermal expansion of the tested samples within temperature range from 30 °C to 80 °C at 1 K/min of heating and cooling rates, respectively and Huang TA computer servo control material testing machine HT-2402 was applied to determine the stress-strain characteristics. Measurements of sample elongation ΔL and physical α* were performed twice in heating and cooling cycles. The glass transition temperature Tg determined from maximum of tan (δ) curve at f = 1Hz was equal to 76.7 °C for E57 and 87.2 °C for L285. It has been observed durable deformed shape of L285 sample with deflection in the middle about 5 mm just after finishing the DMA first run of heating which significantly affected DMA results during the second run of heating

scholarly journals Fmit-The Fusion Materials Irradiation Test Facility

1981 ◽  
Vol 28 (2) ◽  
pp. 1304-1307 ◽  
Author(s):  
Don Liska ◽  
Milton D. Machalek
Keyword(s):  
Test Facility ◽  
Fusion Materials ◽  
Irradiation Test

Fusion Materials Irradiation Test Facility a Facility for Fusion Materials Qualification

1983 ◽  
Vol 4 (2P2) ◽  
pp. 695-700 ◽  
Author(s):  
A. L. Trego ◽  
J. W. Hagan ◽  
E. K. Opperman ◽  
R. J. Burke
Keyword(s):  
Test Facility ◽  
Fusion Materials ◽  
Irradiation Test

Influence of Inclusion Microgeometry on Some Thermomechanical Properties of Isotropic Polymer-Matrix Composites

1997 ◽  
Vol 119 (3) ◽  
pp. 242-250 ◽  
Author(s):  
J. Li ◽  
G. J. Weng
Keyword(s):  
Thermal Expansion ◽  
Thermal Expansion Coefficient ◽  
Expansion Coefficient ◽  
Polymer Matrix Composites ◽  
Cyclic Creep ◽  
Cyclic Stress ◽  
Thermomechanical Properties ◽  
Stress Strain ◽  
Inclusion Shape ◽  
Effective Thermal Expansion

The influence of inclusion shape on some selected thermomechanical properties of isotropic viscoelastic composites is investigated by a micromechanical theory. These properties include: (i) the cyclic stress-strain behavior; (ii) cyclic creep; (iii) the master compliance curve; and (iv) the effective thermal expansion coefficient. It is found that these viscoelastic properties are all strongly dependent upon the inclusion shape. Specifically, under a strain-controlled cyclic loading the transient stress-strain curves of the composites all exhibit cyclic hardening behavior, but the level of flow stress reached is controlled by the inclusion shape. Except for the disk-reinforced case the per-cycle energy loss of the composite at 20 percent of inclusion concentration is found to be greater than the loss of the pure viscoelastic matrix. The complex shear modulus of the composite with various inclusion shapes is shown to lie on or within Milton and Berryman’s bounds (1997). Creep under cyclic stress tends to oscillate around the creep curve under a constant, mean stress for all inclusion shapes, with disks showing the greatest resistance. To uncover the influence of temperature, the creep compliance of the composite with a thermorheologically simple matrix is investigated and it is demonstrated that the compliance curves at various temperatures can all be plotted into a single master one on a reduced time scale. Finally, the effective thermal expansion coefficient of the composite is shown to be generally time-dependent, but the degree of time-dependence is low with spherical inclusions and very high with disks, others lying in-between.

RELAP5 Code Analysis of LSTF Small Break LOCA Tests With Steam Generator Intentional Depressurization as an Accident Management Procedure: Investigation on Base Case Result Appropriate for the Best Estimate Plus Uncertainty (BEPU) Application

2014 ◽  
Author(s):  
Ikuo Kinoshita ◽  
Toshihide Torige ◽  
Michio Murase ◽  
Yoshitaka Yoshida ◽  
Takeshi Takeda ◽  
...  
Keyword(s):  
Steam Generator ◽  
Large Scale ◽  
Model Simulation ◽  
Test Facility ◽  
Base Case ◽  
Best Estimate ◽  
Management Procedure ◽  
Accident Management ◽  
Characteristic Features ◽  
Secondary Side

The application of the Best Estimate Plus Uncertainty (BEPU) method is made to analysis of the “Intentional depressurization of steam generator secondary side” which is an accident management procedure in a small-break loss-of-coolant accident (SBLOCA) with high pressure injection (HPI) system failure. RELAP5/MOD3.2 is used as the analysis code. By applying the BEPU method, the uncertainties of the analysis results can be estimated quantitatively. However, the accuracy of the analysis results depends primarily on the base case result predicted by the best estimate code. In this study, in order to investigate the appropriate base case model, simulation analyses using the RELAP5/MOD3.2 were carried out for the ROSA Large Scale Test Facility (ROSA/LSTF) secondary-side depressurization tests. It was found that the code predicted well the major event progressions such as pressure responses, core liquid level responses, and rod surface temperatures, as well as important phenomena such as formation and clearing of loop seals, accumulation of water from condensation, and countercurrent flow limitation (CCFL) at the inlet of the U-tubes, which are characteristic features of this accident scenario.

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