scholarly journals Predominance Diagrams of Spent Nuclear Fuel Materials in LiCl-KCl and NaCl-KCl Molten Salt Eutectics

2016 ◽  
pp. 10417-10435 ◽  
Author(s):  
Rema Abdulaziz ◽  
Keyword(s):  
Molten Salt ◽  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Predominance Diagrams

Molten Salt Physics and Chemistry in the Current Development of Spent Nuclear Fuel Management

2012 ◽  
pp. 265-278
Author(s):  
Toru Ogawa ◽  
Kazuo Minato ◽  
Yasuo Arai
Keyword(s):  
Molten Salt ◽  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Fuel Management ◽  
Current Development

Development of trail, a simulation code for the molten salt electrorefining of spent nuclear fuel

1993 ◽  
Vol 197 (1) ◽  
pp. 7-16 ◽  
Author(s):  
Tsuguyuki Kobayashi ◽  
Moriyasu Tokiwai
Keyword(s):  
Molten Salt ◽  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Simulation Code

scholarly journals MODERATOR TO FUEL RATIO AND URANIUM FRACTION ANALYSIS OF SQUARE LATTICE MOLTEN SALT TRANSATOMIC POWER

2017 ◽  
Vol 19 (1) ◽  
pp. 1
Author(s):  
Dion Bagus Nugraha B ◽  
Andang Widi Harto ◽  
Sihana Sihana
Keyword(s):  
Molten Salt ◽  
Nuclear Fuel ◽  
Mole Fraction ◽  
Spent Nuclear Fuel ◽  
Light Water Reactor ◽  
Zirconium Hydride ◽  
Molten Salt Reactor ◽  
Inherent Safety ◽  
Light Water ◽  
Optimum Variation

Molten Salt Reactor Transatomic Power (MSR TAP) is a further development of the nuclear reactor Generation IV Reactor Molten Salt Reactor (MSR). MSR TAP generates clean electric power. It has a passive safety, resistance to proliferation, and low cost. MSR TAP can consume the rest of the nuclear fuel/spent nuclear fuel (SNF) of a commercial Light Water Reactor (LWR) fuel or use the main fuel, a salt solution UF4 - LiF - BeF2. MSR TAP uses Zirconium Hydride material for the moderator. This research has a purpose to determine the optimal size of uranium mole fraction on fuel and moderator radius from core design in order to produce optimum enrichment with the value 1 < keff <1.0065 using MCNP5 program. On the other hand, this research also aims to look for the optimum enrichment, which have inherent safety characteristics with αVoid < 0. Variations were made including the changes in the geometry of the moderator radius with a variation of 0.5 cm, 1 cm, 1.5 cm, 2 cm, 2.5 cm, 3 cm, 3.5 cm, 4 cm, and 4.5 cm; and the changes in the fuel uranium molar UF4 - LiF - BeF2 with molar variation of 15%, 20%, 25% and 30%. The geometry of Transatomic Power (MSR TAP) of companies Transatomic Power Corporation was used. The results show that the optimum variation is the salt solution UF4 - LiF - BeF2 with 25 % uranium mole fraction, 2.6 % enrichment and moderator radius of 1.5 cm. The optimum variation gives the keff value of 1.00124 ± 0.00078. The optimum value of reactivity void coefficient is -0.0684. It indicates an inherently safe design.Keywords : Molten Salt Reactor Transatomic Power, MCNP5, Uranium Fuel Mole Fraction, Optimum Variation, Moderator, Inherent Safety. ANALISIS FRAKSI URANIUM DAN RASIO MODERATOR – BAHAN BAKAR PADA SQUARE LATTICED MOLTEN SALT TRANSATOMIC POWER. Molten Salt Reactor Transatomic Power (MSR TAP) merupakan reaktor nuklir pengembangan lebih lanjut dari Reaktor Generasi IV Molten Salt Reactor (MSR). Reaktor MSR TAP ini menghasilkan daya listrik yang bersih, memiliki keselamatan pasif, mempunyai resistensi terhadap proliferasi, dan memiliki biaya yang rendah. Reaktor ini dapat mengkonsumsi bahan bakar nuklir sisa/spent nuclear fuel (SNF) dari penggunaan bahan bakar Light Water Reactor (LWR) yang komersial atau menggunakan bahan bakar utama yaitu larutan garam UF4 – LiF – BeF2. Moderator yang digunakan pada MSR TAP ini adalah moderator berbahan Zirconium Hydride. Penelitian ini bertujuan untuk menentukan ukuran perbandingan nilai fraski mol uranium dan jari-jari moderator yang optimal dari dari desain teras Reaktor MSR TAP agar dihasilkan pengayaan yang optimum dengan nilai 1 < keff < 1,0065 menggunakan program MCNP5. Selain itu penelitian ini juga bertujuan mecari pengayaan optimum yang mempunyai sifat keselamatan melekat dengan . Variasi yang dilakukan meliputi perubahan geometri jari-jari moderator dengan variasi 0,5 cm, 1 cm, 1,5 cm, 2 cm, 2,5 cm, 3 cm, 3,5 cm, 4 cm, dan 4,5 cm; dan perubahan molar uranium pada bahan bakar UF4 – LiF – BeF2  dengan variasi persen molar 15%, 20%, 25%, dan 30%. Geometri reaktor yang digunakan dalam silmulasi adalah MSR TAP dari perusahaan Transatomic Power Corporation. Hasil penelitian menunjukkan variasi optimum perbandingan moderator bahan dan fraksi mol bahan bakar larutan garam UF4 – LiF – BeF2 pada fraksi mol uranium bahan bakar pada variasi molar uranium 25% dengan pengayaan 2,6% dan jari-jari moderator 1,5 cm, dengan nilai keff 1,00124±0,00078. Koefisien reaktivitas void yang didapatkan dari variasi optimum tersebut adalah -0,0684 yang menandakan bahwa desain ini telah memenuhi syarat keselamatan melekat.Kata kunci: Molten Salt Reactor Transatomic Power, MCNP5, Fraksi mol uranium, Variasi optimum, Moderator, Keselamatan melekat. 

Numerical Analysis of Electrorefiner for Spent Nuclear Fuel and Measuring the Composition of Molten Salt by Using the LIBS

PRICM ◽  
2013 ◽  
pp. 3127-3134
Author(s):  
Seung-Hyun Kim ◽  
Sung-Bin Park ◽  
Sung-Jae Lee ◽  
Jeong-Guk Kim ◽  
Han-Soo Lee ◽  
...  
Keyword(s):  
Numerical Analysis ◽  
Molten Salt ◽  
Nuclear Fuel ◽  
Spent Nuclear Fuel

Numerical Analysis of Electrorefiner for Spent Nuclear Fuel and Measuring the Composition of Molten Salt by using the LIBS

2013 ◽  
pp. 3127-3134
Author(s):  
Seung-Hyun Kim ◽  
Sung-Bin Park ◽  
Sung-Jae Lee ◽  
Jeong-Guk Kim ◽  
Han-Soo Lee ◽  
...  
Keyword(s):  
Numerical Analysis ◽  
Molten Salt ◽  
Nuclear Fuel ◽  
Spent Nuclear Fuel
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