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Item EGE ÜNİVERSİTESİ GÜNEŞ ENERJİSİ ENSTİTÜSÜNDE SÜRDÜRÜLEN TEKNOLOJİK GELİŞMELER(Atılım Üniversitesi, 2008-12-17) İÇLİ, SıddıkItem Report on the special issue SET2012, the 10th International Conference on Sustainable Energy Technologies, _ Istanbul, Türkiye (4–7th September 2011)(Energy Conversion and Management, 2011-09-05) ŞAHİN, SümerThe Journal of Energy Conversion and Management covers a wide range of topics related to energy such as the energy efficiency and management; heat pipes; thermo-siphons and capillary pumped loops; thermal management of spacecraft; space and terrestrial power systems; hydrogen production and storage; renewable energy; nuclear power; conventional power; single and combined cycles; miniaturized energy conversion and power systems; fuel cells and advanced batteries; biomass, and water management and desalination.Item ‘‘EDITOR’S REPORT’’, IREC 2011, The International Renewable Energy Congress, Hammamet, Tunisia(Energy Conversion and Management, 2011-12-22) ŞAHİN, SümerThe Journal of Energy Conversion and Management covers a wide range of topics related to energy such as the energy efficiency and management; heat pipes; thermo-siphons and capillary pumped loops; thermal management of spacecraft; space and ter restrial power systems; hydrogen production and storage; renew able energy; nuclear power; single and combined cycles; miniaturized energy conversion and power systems; fuel cells and advanced batteries; and water management and desalination.Item Hydrogen hazard and mitigation analysis in PWR containment(Annals of Nuclear Energy, 2012-04-09) ŞAHİN, Sümer; SARWAR, Mohammed SohailThis paper describes the analytical results for the estimation of hydrogen concentration in the contain ment atmosphere based on zirconium oxidation reaction following a severe accident. The analysis pro vides useful information about the potential challenge of local hydrogen accumulation in the containment, which may be used to reduce the hydrogen detonation risk and to design the capacity and arrangements of mitigation measures. The containment analysis has been performed using computer code COGAP which uses the scenario of loss of coolant accident. The behavior of pressure and hydrogen concentrations in containment as a function of time under the severe accident condition is presented in graphical form. The mitigation measures (recombiners) are essential to maintain containment atmo sphere in the safe stable conditions. A hydrogen control system is to mitigate the hydrogen risk by com paring results from a reference accident sequence with and without recombiners. This comparison show that combustible gas occur in few local areas in the containment for a limited time span and hydrogen concentration is reduced significantly with the use of recombiners.Item Assessment of criticality and burn up behavior of candu reactors with nuclear waste trans uranium fuel(Progress in Nuclear Energy, 2012-04-23) ŞAHİN, Sümer; AHMED, Rizwan; KHAN, Mohammed JavedLarge quantities of nuclear waste plutonium and minor actinides (MAs) have been accumulated in the civilian light water reactors (LWRs) and CANDU reactors. These trans uranium (TRU) elements are all fissionable, and thus can be considered as fissile fuel materials in form of mixed fuel with thorium or nat uranium in the latter. CANDU fuel compacts made of tristructural-isotropic (TRISO) type pellets would withstand very high burn ups without fuel change. As carbide fuels allow higher fissile material density than oxide fuels, following fuel compositions have been selected for investigations: ① 90% nat-UC þ 10% TRUC, ② 70% nat-UC þ 30% TRUC and ③ 50% nat UC þ 50% TRUC. Higher TRUC charge leads to longer power plant operation periods without fuel change. The behavior of the criticality kN and the burn up values of the reactor have been pursued by full power operation for > w12 years. For these selected fuel compositions, the reactor criticality starts by kN ¼ 1.4443, 1.4872 and 1.5238, where corresponding reactor operation times and burn up values have been calculated as 2.8 years, 8 years and 12.5 years, and 62, 430 MW.D/MT, 176,000 and 280,000 MW.D/ MT, with fuel consumption rates of w16, 5.68 and 3.57 g/MW.D respectively. These high burn ups would reduce the nuclear waste mass per unit energy output drastically. The study has show clearly that TRU in form of TRISO fuel pellets will provide sufficient criticality as well as reasonable burn up for CANDU reactors in order to justify their consideration as alternative fuel.Item LIFE hybrid reactor as reactor grade plutonium burner(Energy Conversion and Management, 2012-05-08) ŞAHİN, Sümer; ŞAHİN, Hacı Mehmet; ACIR, AdemThe early version of the conceptual modified design of the Laser Inertial Confinement Fusion Fission Energy (LIFE) engine consists of a spherical fusion chamber of 5 m diameter, surrounded by a multi-lay ered blanket. The first wall is made of 2 cm thick ODS and followed by a Li17Pb83 zone (2 cm), acting as neutron multiplier, tritium breeding and front coolant zone. It is separated by an ODS layer (2 cm) from the FLIBE molten salt zone (50 cm), containing fissionable fuel. A 3rd ODS layer (2 cm) separates the mol ten salt zone on the right side from the graphite reflector (30 cm). Calculations have been conducted for a constant fusion driver power of 500 MWth in S8-P3 approxima tion using 238-neutron groups. Reactor grade (RG) plutonium carbide fuel in form of TRISO particles with volume fractions of 2%, 3%, 4%, 5% and 6% have been dispersed homogenously in the FLIBE coolant. Tritium breeding ratio (TBR) values per incident fusion neutron for the above cited cases start with TBR = 1.35, 1.52, 1.73, 2.02 and 2.47, respectively. With the depletion of fissionable RG-Pu isotopes, TBR decreases gradually. At startup, higher fissionable fuel content in the molten salt leads to higher blanket energy multiplication, namely M0 = 3.8, 5.5, 7.7, 10.8 and 15.4 with 2%, 3%, 4%, 5% and 6% TRISO volume fraction, respectively. Calculations have led to very high burn up values (>400,000 MD.D/MT). TRISO particles can withstand such high burn ups. Such high burn ups would lead to drastic reduction of final nuclear waste per unit energy production.Item Editor’s Report on NURER2012, The III. International Conference on Nuclear and Renewable Energy Resources, _ Istanbul, Türkiye (20–23rd May 2012)(Energy Conversion and Management, 2012-05-22) ŞAHİN, SümerThe Journal of Energy Conversion and Management covers a wide range of topics related to energy such as the energy efficiency and management; heat pipes; thermo-siphons and capillary pumped loops; thermal management of spacecraft; space and terrestrial power systems; hydrogen production and storage; renewable energy; nuclear power; conventional power; single and combined cycles; miniaturized energy conversion and power systems; fuel cells and advanced batteries; biomass, and water management and desalinationItem Commercial utilization of weapon grade plutonium as TRISO fuel in conventional CANDU reactors(Energy Conversion and Management, 2012-06-15) ŞAHİN, Sümer; ŞAHİN, Hacı Mehmet; ACIR, AdemLarge quantities of weapon grade (WG) plutonium have been accumulated in the nuclear warheads. Plutonium and heavy water moderator can give a good combination with respect to neutron economy. TRISO type fuel can withstand very high fuel burn up levels. The paper investigates the prospects of uti lization of TRISO fuel made of WG-plutonium in CANDU reactors. Three different fuel compositions have been investigated: (1): 90% ThC + 10% PuC, (2): 70% ThC + 30% PuC and (3): 50% ThC + 50% PuC. The temporal variation of the criticality k1 and the burn-up values of the reactor have been calculated by full power operation up to 17 years. Calculated startup criticalities for these fuel modes are k1,0 = 1.6403, 1.7228 and 1.7662, respectively. Attainable burn up values and reactor operation times without new fuel charge will be 94 700, 265 000 and 425 000 MW.D/MT and along with continuous operation periods of 3.5, 10 and 17 years, respec tively, for the corresponding modes. These high burn ups would reduce fuel fabrication costs and nuclear waste mass for final disposal per unit energy drastically.Item Evaluation of integral quantities in an accelerator driven system using different nuclear models implemented in the MCNPX Monte Carlo transport code(Annals of Nuclear Energy, 2012-07-27) ŞARER, Başar; ŞAHİN, Sümer; ÇELİK, Yurdunaz; GÜNAY, MehtapThe MCNPX code offers options based on physics packages; the Bertini, ISABEL, INCL4 intra-nuclear mod els, and Dresner, ABLA evaporation–fission models and CEM2k cascade-exciton model. This study ana lyzes the main quantities determining ADS performance, such as neutron yield, neutron leakage spectra, heating and neutron and proton spectra in the target and in the beam window calculated by the MCNPX-2.5.0 Monte Carlo transport code, which is a combination of LAHET and MCNP codes. The results obtained by simulating different models cited above and implemented in MCNPX are compared with each other. The investigated system is composed of a natural lead cylindrical target and stainless steel (HT9) beam window. The target has been optimized to produce maximum number of neutrons with a radius of 20 cm and 70 cm of height. The target is bombarded with a high intensity linear accelerator by a 1 GeV, 1 mA proton beam. The protons are assumed uniformly distributed across the beam of radius 3 cm, and entering the target through a hole of 5.3 cm radius. The proton beam has an outer radius of 5.3 cm and an inner radius of 5.0 cm. The maximum value of the neutron flux in the target is observed on the axis 10 cm below the beam window, where the maximum difference between 7 different models is 15%. The total neutron leakage of the target calculated with the Bertini/ABLA is 1.83 1017 n/s, and is about 14% higher than the value calculated by the INCL4/Dresner (1.60 1017 n/s). Bertini/ABLA calcu lates top, bottom and side neutron leakage fractions as 20%, 2.3%, 77.6% of the total leakage, respectively, whereas, the calculated fractions are 18.6%, 2.3%, 79.4%, respectively, with INCL4/Dresner combination. The largest heat deposition density by considering all particles in the beam window calculated with CEM2k model is 104 W/cm3 /mA, which is 9.0% greater than the lowest value predicted with INCL4/Dres ner model (95.4 W/cm3 /mA). The maximum average heat deposition density for all particles in the target is calculated as 6.87 W/cm3 /mA with INCL4/ABLA.Item Editorial notes on the 2012 International Youth Nuclear Congress (IYNC), Charlotte, North Carolina, USA (5–11 August 2012)(Energy Conversion and Management, 2012-08-05) ŞAHİN, SümerPrimary purpose of the International Youth Nuclear Congress (IYNC) series is to transfer knowledge from the current generation of leading scientists and engineers to the next generation. Scien tific, political, public and corporate views regarding the develop ment of different nuclear issues are presented to provide comprehensive discussions on all sides of the subject. With this aim, The 2012 International Youth Nuclear Congress has been held in Charlotte, North Carolina. IYNC2012 was focused on the use of nuclear energy more than ever after the accident at Fukushima power plant and also in the framework of the nuclear renaissance in many developing countries and world powers as well. IYNC2012 offered the opportunity to share knowledge, experience, best prac tices and information about nuclear energy between generations and also between peers in the ongoing mission to promote the peaceful use of nuclear power.Item 10. KALKINMA PLANI HEDEFLERİ VE NÜKLEER SANTRALLER(Bilim ve Teknoloji, 2013-09-06) BALKU, ŞaziyeTürkiye Cumhuriyeti 10. Beş Yıllık Kalkınma Planı (2014-2018) resmi hazırlık süreci 5 Haziran 2012 tarihli 14 sayılı Başbakanlık Genelgesiyle başlatılmış ve kurulan Özel İhtisas Komisyonları arasında Enerji Güvenliği ve Verimliliği de yer almıştır. Komisyonu oluşturan akademisyenler, kamu kurum ve kuruluşları ile özel sektör ve sivil toplum kuruluşlarının temsilcileri enerji arz güvenliği, fiyatlarının yüksekliği ve belirsizliği, çevresel sorunlar, iklim değişikliği, yüksek yatırımda finansman ihtiyacı, enerjinin verimsiz kullanılması, dışa bağımlılığı gibi temel sorunlar ve gelişmeler göz önünde tutularak, ülkemiz enerji sektörü için durum analizi yapmak, bir vizyon geliştirmek ve yol haritası oluşturmak üzere çalışmalarını sürdürmüşler ve mevcut durumun değerlendirmesi, sektördeki gelişme eğilimleri ve muhtemel yansımaları, geleceğe dönük beklentiler, güçlü ve zayıf taraflar, fırsatlar-tehditler, sorunlar ve çözüm önerileri, politika ve strateji önerileri ile plana katkıda bulunmuşlardır.Item Neutronic investigations of a laser fusion driven lithium cooled thorium breeder(Progress in Nuclear Energy, 2014-02-02) ŞAHİN, Sümer; ŞARER, Başar; ÇELİK, YurdunazThe paper investigates the main parameters of a Laser Inertial Confinement Fusion Fission Energy (LIFE) driven thorium breeder. A similar blanket to the (LIFE) engine design in Lawrence Livermore National Laboratory is chosen in order to allow mutual feedback between two geographically separated teams towards a more advanced and improved design under consideration of totally independent views. In the basic design, frozen (D,T) fusion fuel ice is shot to the center of 5 m diameter spherical fusion reactor chamber cavity in pulsed mode (10e30 Hz). Fusion fuel burns through direct or indirect laser beam irradiation. The first wall surrounds the fusion chamber and is made of S-304 steel (2 cm). The fusion reactor cavity is kept in high vacuum. It is followed by a natural lithium coolant zone. A 2nd S-304 layer (2 cm) separates the lithium zone on the right side from the graphite reflector (30 cm). The outer boundary of the graphite reflector is also covered with a 3rd S-304 layer (2 cm). The calculations have been performed for a fusion driver power of 500 MWth with the last available version of MCNP, namely with MCNPX-2.7.0. In the first calculation phase, the thickness of the natural lithium coolant-tritium breeder zone (DRLi) has been varied as 50, 60, 70, 80, 90 and 100 cm to select the coolant thickness DRLi to have a satisfactory tritium breeding ratio (TBR) for continuous fusion reactor operation. For a pure fusion blanket without any fissionable elements in the coolant, TBR values are calculated as 1.237, 1.312, 1.370, 1.415, 1.449 and 1.476, respectively, for corresponding coolant thick nesses. A DRLi value of 50 cm would keep TBR > 1.05 for self-sustaining tritium supply. These DRLi values lead to blanket energy multiplication values of M ¼ 1.209, 1.216, 1.219, 1.222, 1.223 and 1.224, respec tively, and have been calculated, as a result of exoenergetic neutron absorption in 6 Li. For coolant thickness values >50 cm, the increase of “M” would remain minor. In the second phase, ThO2 has been suspended in the form of micro-size tristructural-isotropic (TRISO) particles in the lithium coolant for 233U breeding. TRISO fuel has the great advantage of high mechanical stability. Furthermore, fission products will be separated from the coolant. TRISO particles have been dispersed homogenously in the lithium coolant with volume fractions Vtr ¼ 1, 2, 3, 4, 5 and 10 vol-%. Calculations with DRLi ¼ 50 cm and by variable Vtr result with TBR ¼ 1.229, 1.222, 1.214, 1.206, 1.1997 and 1.1622, respectively. Parasitic neutron absorption in Thorium decreases the TBR values. For Vtr < 5 vol-% TRISO in the coolant, the increase of the neutron absorption in thorium will be compensated to a great degree through neutron multiplications via 232Th(n,f) and 232Th(n,2n) reactions so that the sacrifice on TBR remains acceptable. However, for Vtr > 5 TRISO vol-%, neutron absorption in thorium reduces TBR drastically. On the other hand, the blanket energy multiplication M increases with thorium volume fraction, namely as M ¼ 1.2206, 1.2322, 1.2426, 1.2536, 1.2636, 1.3112 for respective TRISO volume frac tions due to the contribution of fission energy. Fissile fuel productions in the blanket are calculated as 17.23, 33.09, 48.66, 64.21, 79.77 and 159.71 233U (kg/year), respectively.Item TEKNOLOJİ DEVRİM YARATACAK MUCİZE MALZEME-GRAFEN(Bilim ve Teknoloji, 2014-03-13) DEVRİM, YılserKarbon elementinin bal peteği örgülü yapıları olan grafen, iki boyutlu düzlemsel yapıların çok ender örneklerinden biri olarak kabul edilmektedir. Grafen maddesi ilk olarak 2004 yılında, Manchester Üniversitesi'nden Andre Geim ve Konstantin Sergeevich Novoselov isimli iki bilim adamının çalışmaları sonucu bulunmuştur. Bu araştırmaları 2010 Nobel Fizik Ödülü’ne layık görülmüştür. Bilim dünyasında oldukça fazla heyecan yaratan grafen aslında çok nadir bulunan bir malzeme değildir. Kullandığımız kurşun kalemlerin içindeki grafit, grafen tabakalarının üst üste binmesinden oluşmaktadır. Grafen, karbon atomlarının tek düzlemde altıgen yapıda dizilmesiyle oluşan iki boyutlu, bir atom kalınlığında karbon allotropu bir yapıdır. Grafenin bu yapısı sayesinde olağanüstü özelliklere sahiptir, örneğin dijital teknolojinin süper starı silikon, grafen ile karşılaştırıldığında elektronların silikon içindeki hızlarının grafen içindeki hızlarına göre 100 kez daha yavaş olduğu görülmektedir. Elektronlar bu tek atom kalınlığındaki karbon tabakasında sanki kütleleri yokmuş gibi hareket etmektedirler. Grafen ısıyı çok iyi ileten malzemedir. Grafen bilinen en ince malzeme olmasına rağmen güçlü karbon bağları ona yeryüzündeki bilinen en sağlam malzemelerden biri olma özelliğini kazandırmıştır. Çelikten yaklaşık 100 kat daha güçlüdür ve kolayca esneyebilerek farklı formlardaki malzemelerin yüzeylerine de kolaylıkla kaplanabilmektedir. Tüm bu özellikleriyle gelecekte dünyada pek çok önemli teknolojik değişikliklere neden olabilecek bir maddedir.Item TÜRKİYE’NİN ENERJİ GÖRÜNÜMÜ VE TORYUMUN ÖNEMİ(Bilim ve Teknoloji, 2014-10-03) BALKU, ŞaziyeEnerji, yüzyıllar boyunca dünyadaki en önemli konular arasında yer almış ve almaya devam etmektedir. Sayısal olarak ifade etmek istersek, 2010 yılında dünyada 524 katrilyon Btu* enerji tüketilmiştir (1) ve her yıl bu rakam ortalama % 1.5 oranında artmaktadır. Bu enerjinin % 53’ü endüstride, % 26’sı ulaşım ve taşımacılık sektöründe, % 13’ü evlerde % 8’i ise ticaret sektöründe kullanılmaktadır. Toplam enerjinin % 55.37 si elektrik olarak tüketilmektedir. Dünyada kullanılan enerjinin kaynaklarına göre dağılımı Şekil 1’de verilmektedir ve % 87’si (TEP** cinsinden) fosil kaynaklıdır (petrol, kömür ve doğalgaz). Dünya’da birincil enerji kaynağı olarak en fazla kullanılan fosil kaynakların oranının 2040 yılında %78’lere gerilemesi beklenmektedir. Bu gerileme, kullanım miktarında beklenen bir düşüş değil, yenilenebilir kaynak kullanımının artması ile fosil kullanım payının azalması anlamına gelmektedir.Item Energy multiplication and fissile fuel breeding limits of accelerator-driven systems with uranium and thorium targets(International Journal of Hydrogen Energy, 2015-01-25) ŞAHİN, Sümer; ŞARER, Başar; ÇELİK, YurdunazThe study analyses the integral 233U and 239Pu breeding rates, neutron multiplication ratio through (n,xn)- and fission-reactions, heat release, energy multiplication and consequently the energy gain factor in infinite size thorium and uranium as breeder material in an accelerator driven systems (ADS), irradiated by a 1-GeV proton source. Energy gain factor has been calculated as Menergy ¼ 1.67, 4.03 and 5.45 for thorium, depleted uranium (100% 238U) and natural uranium, respectively, where the infinite criticality values are k∞ ¼ 0.40, 0.752 and 0.816. Fissile fuel material production is calculated as 53 232Th(n,g) 233U, 80.24 and 90.65 238U(n,g) 239Pu atoms per incident proton, respectively. The neutron spectrum maximum is by ~1 MeV. Lower energy neutrons E < 1 MeV have major contribution on fissile fuel material breeding (>97.5%), whereas their share on energy multiplication is negligible (0.2%) for thorium, depleted uranium. Major fission events occur in the energy interval 1MeV < E < 50 MeV.Item Influence of void fraction on BWR spent fuel direct recycling scenario(International Journal of Hydrogen Energy, 2015-06-10) ŞAHİN, Sümer; WARIS, Abdul; SU'UD, Zaki; ŞAHİN, Hacı Mehmet; KURT, ErolPreliminary study on influence of changing void fraction (VF) on SUPEL (Straight Utilization of sPEnt LWR fuel in LWR system) scenario for boiling water reactor (BWR) spent fuel direct recycling scheme has been carried out. Several VF values of BWR have been investigated to determine the criticality of reactor. The VF values range from 20% to 60%. The fraction of spent fuel to the total loaded fuel was changed from 5% to 20%. The required uranium enrichment for criticality becomes higher with the increasing of VF as well as the enlarging of the fraction of spent fuel in loaded fuel. The neutron spectra become harder with the augmenting of VF. The plutonium and minor actinides isotopes are produced more in the reactor.Item Editor’s notes on ICENES’2013, 16th International Conference on Emerging Nuclear Energy Systems(Progress in Nuclear Energy, 2015-08-05) ŞAHİN, SümerThe 16th ICENES 2013 was held in Madrid (Spain) on May 26e 30, 2013, by Universidad Politécnica of Madrid (UPM), according to a scientific tradition of 35 years, started in 1978 as an autono mous, self-organized event, when a group of independent nuclear scientists met in Graz, Austria in order to find new routes for improving the use of the immense energy of the atomic nucleus. Throughout the years, ICENES became a very important series of well established conferences and acted as an open forum for inno vation and challenges in the field as long as they were based on sound deliberations and were addressing the key issue of providing energy for humankind.Item ENERJİ ÜRETİMİNDE ARITMA ÇAMURLARININ ÖNEMİ(Bilim ve Teknoloji, 2015-09-29) BALKU, Şaziye; SAĞLAMCI, Mehmetİnsanların sağlıklı ve sosyal bir çevrede yaşayabilmeleri için enerji talebinin sürekli, güvenilir, kaliteli ve ekonomik bir şekilde karşılanabilmesi gerekmektedir. 2012 yılı verilerine göre dünya enerji üretiminin yaklaşık % 87’si, ülkemizin ise yaklaşık % 88’i fosil kaynaklıdır. Bilindiği üzere ülkemiz fosil kaynaklar bakımından, özellikle doğal gaz ve petrol açısından, dışarıya bağımlıdır. Son yıllarda ithal kömüre dayalı santraller kurulmakta olup, ülkemizin kömür ithalatının da artması beklenmektedir. 2014 yılı sonu itibarıyla (geçici değerler), 41.801,8 MW’ı termik, 23.643,2 MW’ı hidrolik, 404,9 MW’ı jeotermal, 3.629,7 MW’ı rüzgâr ve 40,2 MW’ı güneş olmak üzere Türkiye’nin toplam kurulu gücü 69.519,8 MW’a ulaşmıştır. Yine aynı yılda elektrik enerjisi talebi bir önceki yıla göre yaklaşık % 3,7’lik bir artış ile 255,5 milyar kWh, puant güç talebi ise 41.002,9 MW olarak gerçekleşmiştir. Toplam 250,4 Milyar kWh üretim gerçekleştirilirken, 7,8 Milyar kWh ithalat yapılmış, arz edilen toplam elektrik enerjisinden 2,7 Milyar kWh ihracat gerçekleştirilmiştir (1). Yenilenebilir enerji kaynakları kullanılarak yapılan üretimde, özellikle hidrolik enerjide -kurulu kapasite yüksek görünse de doğal koşullara bağımlılık nedeni ile fiili üretimde payları daha düşüktür.Item Utilization of Reactor Grade Plutonium as Energy Multiplier in the LIFE Engine(Fusion Science and Technology, 2017-08-10) ŞAHİN, Sümer; ŞAHİN, Hacı Mehmet; ACIR, AdemThe accumulated reactor grade (RG)-plutonium as nuclear waste of conventional reactors is estimated to exceed 1700 tonnes. Laser Inertial Confinement Fusion Fission Energy (LIFE) engine is considered to incinerate RG-plutonium in stockpiles. Calculations have been conducted for a constant fusion driver power of 500 MWth in S8-P3 approximation using 238-neutron groups. RG plutonium out of the nuclear waste of LWRs is used in form of fissile carbide fuel in TRISO particles with volume fractions of 2, 3, 4, 5 and 6 %, homogenously dispersed in the Flibe coolant. Respective tritium breeding ratio (TBR) values per incident fusion neutron are calculated as TBR = 1.35, 1.52, 1.73, 2.02 and 2.47 at start-up. With the burn up of fissionable RG-Pu isotopes in the coolant, TBR decreases gradually. Similarly, blanket energy multiplications are calculated as M0 = 3.8, 5.5, 7.7, 10.8 and 15.4 at start-up, respectively. Calculations have indicated prospects of achievability of very high burn up values (> 400 000 MD.D/MT).Item Atılan 1 Ton Çöp Değil 1 MW Elektrik(2022-02-09) Devrim, Yılser; Sağlam, ArifeMaddenin katı, sıvı, gaz ve plazma olmak üzere dört hali olduğu bilinmektedir. Maddenin plazma hali bir enerji kaynağı olarak görüldüğünden maddenin diğer üç halinden ayrı tutulmaktadır. Plazma teknolojisi ilk olarak 1929 yılında Amerikalı bilim adamı Irving Langmuir tarafından elektrik deşarjı sırasında salınım yapan elektron bulutunu tanımlamak üzere “plazma” teriminin kullanması ile başladı.