scholarly journals Description of the Canadian particulate-fill waste-package (WP) system for spent-nuclear fuel (SNF) and its applicability to light-water reactor SNF WPs with depleted uranium-dioxide fill

1997 ◽  
Author(s):  
C.W. Forsberg
Keyword(s):  
Nuclear Fuel ◽  
Uranium Dioxide ◽  
Spent Nuclear Fuel ◽  
Depleted Uranium ◽  
Light Water Reactor ◽  
Light Water ◽  
Waste Package ◽  
Water Reactor

Depleted Uranium Dioxide Waste Package for Spent Nuclear Fuel

2002 ◽  
Vol 713 ◽  
Author(s):  
Charles W. Forsberg ◽  
Leslie R. Dole
Keyword(s):  
Crystal Structure ◽  
Nuclear Fuel ◽  
Uranium Dioxide ◽  
Spent Nuclear Fuel ◽  
Natural Uranium ◽  
Depleted Uranium ◽  
Radiation Shielding ◽  
Waste Package ◽  
Uranium Ore ◽  
Ore Bodies

ABSTRACTDepleted uranium dioxide (DUO2) waste packages (WPs) for disposal of spent nuclear fuel (SNF) are being investigated to (1) reduce radionuclide releases from WPs, (2) decrease the potential for repository nuclear criticality events, (3) provide radiation shielding, and (4) provide a means to beneficially use excess depleted uranium (DU). The DUO2 is incorporated into the WP as (1) a particulate fill for void spaces within the package and (2) a component of a DUO2-steel cermet (DUO2 embedded in steel) that replaces the steel components of the WP. Depending upon the design, there is 3 to 8 times as much DUO2 as SNF UO2 in the WP. Most radionuclides in the SNF cannot be released until the UO2 crystal structure is destroyed. The DUO2 surrounding the SNF slows the degradation of the SNF UO2 in the interior. This behavior is similar to the mechanisms that slow the degradation of natural uranium ore bodies containing UO2. The results of initial investigations and the expected thermodynamic WP behavior are described.

scholarly journals Depleted Uranium Oxides and Silicates as Spent Nuclear Fuel Waste Package Fill Materials

1996 ◽  
Vol 465 ◽  
Author(s):  
C. W. Forsberg
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Chemical Species ◽  
Fission Products ◽  
Depleted Uranium ◽  
Improve Performance ◽  
Waste Package ◽  
Reducing Conditions ◽  
Nuclear Fuel Waste

ABSTRACTA new repository waste package (WP) concept for spent nuclear fuel (SNF) is being investigated. The WP uses depleted uranium (DU) to improve performance and reduce the uncertainties of geological disposal of SNF. The WP would be loaded with SNF. Void spaces would then be filled with DU (∼0.2 wt % 235U) dioxide (UO2) or DU silicate-glass beads.Fission products and actinides can not escape the SNF UO2 crystals until the UO2 dissolves or is transformed into other chemical species. After WP failure, the DU fill material slows dissolution by three mechanisms: (1) saturation of WP groundwater with DU and suppression of SNF dissolution, (2) maintenance of chemically reducing conditions in the WP that minimize SNF solubility by sacrificial oxidation of DU from the +4 valence state, and (3) evolution of DU to lower-density hydrated uranium silicates. The fill expansion minimizes water flow in the degraded WP. The DU also isotopically exchanges with SNF uranium as the SNF degrades to reduce long-term nuclear-criticality concerns.

Apex Nuclear Fuel Cycle for Production of Light Water Reactor Fuel and Elimination of Radioactive Waste

1982 ◽  
Vol 58 (3) ◽  
pp. 437-446 ◽  
Author(s):  
Meyer Steinberg ◽  
James R. Powell ◽  
Hiroshi Takahashi
Keyword(s):  
Radioactive Waste ◽  
Nuclear Fuel ◽  
Fuel Cycle ◽  
Nuclear Fuel Cycle ◽  
Reactor Fuel ◽  
Light Water Reactor ◽  
Light Water ◽  
Water Reactor

Effect of Depleted-Uranium Dioxide Particulate Fill on Spent-Nuclear-Fuel Waste Packages

2000 ◽  
Vol 131 (3) ◽  
pp. 337-353 ◽  
Author(s):  
Charles W. Forsberg
Keyword(s):  
Nuclear Fuel ◽  
Uranium Dioxide ◽  
Spent Nuclear Fuel ◽  
Depleted Uranium ◽  
Nuclear Fuel Waste

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. 

Light Water Reactor Nuclear Fuel Cycle

1983 ◽  
Vol 60 (2) ◽  
pp. 334-335 ◽  
Author(s):  
Bernard L. Cohen
Keyword(s):  
Nuclear Fuel ◽  
Fuel Cycle ◽  
Nuclear Fuel Cycle ◽  
Light Water Reactor ◽  
Light Water ◽  
Water Reactor
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