427 research outputs found
PEMILIHAN METODE ANALISIS DELIVERABILITAS SUMUR GAS UNTUK MENGETAHUI AOF YANG AKURAT DAN QOPTIMUM SUMUR-SUMUR X-13, X-17 DAN X-18 PADA FORMASI PARIGI LAPANGAN Y
No full textFormasi Parigi merupakan reservoir penghasil gas dengan IGIP sebesar
974,36 Bscf, dan sumur-sumur pada formasi ini dilakukan pengujian sumur
secara berkala untuk mengetahui kemampuan produksi sumur. Dalam penulisan
ini yang akan dianalisa adalah sumur-sumur X-13, X-17 dan X-18. Permasalahan
yang timbul dalam penelitian ini adalah : Berapakah harga parameter Pi yang
didapat dari analisa PBU ? Berapakah harga AOF akurat dari sumur-sumur yang
dikaji dan metode apa yang digunakan? Berapakah laju alir optimum masingmasing
sumur ?
Langkah-langkah penyelesaian dalam penelitian ini yaitu : 1. Menganalisa
hasil uji tekanan ( PBU ) dengan analisa horner time untuk mendapatkan
parameter Pi. 2. Menganalisa hasil uji deliverabilitas untuk menentukan AOF dan
metode yang digunakan adalah metode konvensional, metode Jones Blunt Glaze
dan metode LIT. 3. Membuat kurva IPR berdasarkan data Pi dan AOF dari ketiga
metode. 4. Mengeplot data laju alir actual pada kurva IPR. 5. Menentukan IPR
matching (sesuai) dan AOF yang akurat dengan metode penentuan AOF yang
representative. 6. Menentukan laju alir optimum berbasis IPR yang sesuai dan
kurva tubing intake yang dikontrol dengan 30% AOF akurat.
Hasil dari analisa PBU sumur X-13 didapatkan harga Pi = 1609,24 psia,
sumur X-17 dengan Pi = 1626,17 psia dan sumur X-18 diperoleh harga Pi =
1583,52 psia. Sedangkan hasil dari analisa MIT (Modified Ischoronal Test), pada
sumur X-13 AOF yang paling akurat adalah 35,05 MMscf/d dengan metode Jones
Blunt Glaze dan diperoleh Qoptimum = 10,01 MMscf/d dengan prosentase 28,57 %
dari AOF pada ukuran tubing 3.476 ID. Pada sumur X-17 AOF yang paling akurat
adalah 25,60 MMscf/d dengan metode Jones Blunt Glaze dan diperoleh Qoptimum
= 7,43 MMscf/d dengan prosentase 29,02 % dari AOF pada ukuran tubing 2.441
ID. Sedangkan sumur X-18, AOF yang paling akurat adalah 32,72 MMscf/d
dengan metode Jones Blunt Glaze dan diperoleh Qoptimum = 9,47 MMscf/d dengan
prosentase 28,94 % dari AOF pada ukuran tubing 2.992 ID. Dasar penentuan
Qoptimum ini adalah 30% AOFP
Sub-millisecond electron density profile measurement at the JET tokamak with the fast lithium beam emission spectroscopy system
No full textPeer reviewe
Utilizing silicon photomultiplier detectors for low light level high frequency measurements in fusion diagnostics
No full textEffect of the isotope mass on pedestal structure, transport and stability in D, D/T and T plasmas at similar β N and gas rate in JET-ILW type I ELMy H-modes
No full textThe work describes the pedestal structure, transport and stability in an effective mass (A eff) scan from pure deuterium to pure tritium plasmas using a type I ELMy H-mode dataset in which key parameters that affect the pedestal behaviour (normalized pressure, ratio of the separatrix density to the pedestal density, pedestal ion Larmor radius, pedestal collisionality and rotation) are kept as constant as possible. Experimental results show a significant increase of the density at the pedestal top with increasing A eff, a modest reduction in the temperature and an increase in the pressure. The variations in the pedestal heights are mainly due to a change in the pedestal gradients while only small differences are observed in the pedestal width. A clear increase in the pedestal density and pressure gradients are observed from deuterium to tritium. The experimental results suggest a reduction of the pedestal inter-edge localized mode (inter-ELM) transport from deuterium to tritium. The reduction is likely in the pedestal inter-ELM particle transport, as suggested by the clear increase of the pedestal density gradients. The experimental results suggest also a possible reduction of the pedestal inter-ELM heat transport, however, the large experimental uncertainties do not allow conclusive claims on the heat diffusivity. The clear experimental reduction of eta e (the ratio between density and temperature gradient lengths) in the middle/top of the pedestal with increasing A eff suggests that there may be a link between increasing A eff and the reduction of electron scale turbulent transport. From the modelling point of view, an initial characterization of the behaviour of pedestal microinstabilities shows that the tritium plasma is characterized by growth rates lower than the deuterium plasmas. The pedestal stability of peeling-ballooning modes is assessed with both ideal and resistive magnetohydrodynamics (MHD). No significant effect of the isotope mass on the pedestal stability is observed using ideal MHD. Instead, resistive MHD shows a clear increase of the stability with increasing isotope mass. The resistive MHD results are in reasonable agreement with the experimental results of the normalized pedestal pressure gradient. The experimental and modelling results suggest that the main candidates to explain the change in the pedestal are a reduction in the inter-ELM transport and an improvement of the pedestal stability from deuterium to tritium
Utilizing Silicon Photomultiplier Detectors for Low Light Level High Frequency Measurements in Fusion Diagnostics
No full textThe core-edge integrated neon-seeded scenario in deuterium-tritium at JET
No full textThis paper reports the first experiment carried out in deuterium-tritium addressing the integration of a radiative divertor for heat-load control with good confinement. Neon seeding was carried out for the first time in a D-T plasma as part of the second D-T campaign of JET with its Be/W wall environment. The technical difficulties linked to the re-ionisation heat load are reported in T and D-T. This paper compares the impact of neon seeding on D-T plasmas and their D counterpart on the divertor detachment, localisation of the radiation, scrape-off profiles, pedestal structure, edge localised modes and global confinement
Overview of T and D-T results in JET with ITER-like wall
No full textIn 2021 JET exploited its unique capabilities to operate with T and D–T fuel with an ITER-like Be/W wall (JET-ILW). This second major JET D–T campaign (DTE2), after DTE1 in 1997, represented the culmination of a series of JET enhancements—new fusion diagnostics, new T injection capabilities, refurbishment of the T plant, increased auxiliary heating, in-vessel calibration of 14 MeV neutron yield monitors—as well as significant advances in plasma theory and modelling in the fusion community. DTE2 was complemented by a sequence of isotope physics campaigns encompassing operation in pure tritium at high T-NBI power. Carefully conducted for safe operation with tritium, the new T and D–T experiments used 1 kg of T (vs 100 g in DTE1), yielding the most fusion reactor relevant D–T plasmas to date and expanding our understanding of isotopes and D–T mixture physics. Furthermore, since the JET T and DTE2 campaigns occurred almost 25 years after the last major D–T tokamak experiment, it was also a strategic goal of the European fusion programme to refresh operational experience of a nuclear tokamak to prepare staff for ITER operation. The key physics results of the JET T and DTE2 experiments, carried out within the EUROfusion JET1 work package, are reported in this paper. Progress in the technological exploitation of JET D–T operations, development and validation of nuclear codes, neutronic tools and techniques for ITER operations carried out by EUROfusion (started within the Horizon 2020 Framework Programme and continuing under the Horizon Europe FP) are reported in (Litaudon et al Nucl. Fusion accepted), while JET experience on T and D–T operations is presented in (King et al Nucl. Fusion submitted)
Determination of isotope ratio in the divertor of JET-ILW by high-resolution H alpha spectroscopy: H-D experiment and implications for D-T experiment
No full textThe data of the H alpha high-resolution spectroscopy, collected on the multiple lines of sight, which cover the entire divertor space in poloidal cross-section, during the recent hydrogen-deuterium experiments in JET-ILW (ITER-like wall), are processed. A strong spatial inhomogeneity of the hydrogen concentration, H/(H + D), in divertor is found in many pulses. Namely, the H/(H + D) ratio may be lower in the inner divertor than that in the outer divertor by the values of 0.15-0.35, depending on the conditions of gas puffing and plasma heating. This effect suggests the necessity of spatially-resolved measurements of isotope ratio in the divertor in the upcoming deuterium-tritium experiments. Also, separation of the overlapped T alpha and D alpha spectral lines is shown to be a challenging task especially when the local Doppler-broadened (Gaussian) line shapes are noticeably distorted by the net inward flux of fast non-Maxwellian neutral atoms. We use the respective, formerly developed model of an asymmetric spectral line shape, while analysing the data of the first deuterium-tritium experiment in JET-C (carbon wall), and test the model via comparing the isotope ratio results with another diagnostic's measurements. This model is shown to increase the accuracy of tritium concentration measurements in the divertor
Investigation of Edge Quasi-Coherent Fluctuations in Wendelstein 7-X Stellarator Plasma Using Alkali Beam Diagnostics
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