Burn up Study of an Innovative Natural Uranium-Thorium Fueled Reprocessing Free Fusion-Fission Hybrid Reactor Blanket with Closed Thorium-Uranium Fuel Cycle

2015 ◽  
Vol 68 (3) ◽  
pp. 566-572 ◽  
Author(s):  
S. C. Xiao ◽  
Jing Zhao ◽  
X. Heng ◽  
X. Y. Sheng ◽  
Z. Zhou ◽  
...  
Keyword(s):  
Fuel Cycle ◽  
Natural Uranium ◽  
Hybrid Reactor ◽  
Uranium Fuel

Development of Technologies and Safety Systems for Pressurized Heavy Water Reactors in India

2017 ◽  
Vol 3 (2) ◽  
Author(s):  
S. Banerjee ◽  
H. P. Gupta
Keyword(s):  
Heavy Water ◽  
Fuel Cycle ◽  
High Capacity ◽  
Natural Uranium ◽  
Closed Fuel Cycle ◽  
Uranium Fuel ◽  
Present Generation ◽  
Heavy Water Reactor ◽  
Water Reactors ◽  
Safety Features

The technology of pressurized heavy water reactors (PHWRs) which was developed with prime objectives of using natural uranium fuel, implementing on power fuelling, utilizing mined uranium most effectively, and achieving excellent neutron economy has demonstrated impressive performance in terms of high capacity factors and an impeccable safety record. The safety features and several technology advancements evolved over the years in which Indian contributions that are considerable are briefly discussed in the first part of the paper. Unique features of PHWR such as flexibility of fuel management, distribution of pressure boundaries in multiple pressure tubes (PTs), and a large inventory of coolant-moderator heat sink in close proximity of the core provide inherent safety and fuelling options to these reactors. PHWRs, in India have demonstrated to have the advantage of lower capital cost per megawatt even in small size reactors. Low burn up associated with natural uranium fuel, higher level of tritium in the heavy water coolant, and a slightly positive coolant void coefficient in present generation PHWRs have all been addressed in the design of advanced heavy water reactor (AHWR). The merit of adopting closed fuel cycle with partitioning of minor actinides in reducing the burden of radio-toxicity of nuclear waste and of deploying light water reactors (LWRs) in tandem with PHWRs in the evolving nuclear fuel cycle in India are also discussed.

Desain Study of Pb-Bi Cooled Fast Reactors with Natural Uranium as Fuel Cycle Input Using Special Shuffling Strategy in Radial Direction

2013 ◽  
Vol 772 ◽  
pp. 530-535 ◽  
Author(s):  
Zaki Su’ud ◽  
Feriska H. Irka ◽  
Taufiq Imam ◽  
H. Sekimoto ◽  
P. Sidik
Keyword(s):  
Power Distribution ◽  
Fuel Cycle ◽  
Batch Reactor ◽  
Operation Time ◽  
Axial Direction ◽  
Natural Uranium ◽  
Fast Reactors ◽  
Uranium Fuel ◽  
Slow Growing ◽  
Effective Multiplication

Design study of Pb-Bi cooled fast reactors with natural uranium as fuel cycle input using special radial shuffling strategy has been performed. The reactors utilizes UN-PUN as fuel, Eutectic Pb-Bi as coolant, and can be operated without refueling for 10 years in each batch. Reactor design optimization is performed to utilize natural uranium as fuel cycle input. This reactor subdivided into 6 regions with equal volume in radial directions. The natural uranium is initially put in region 1, and after one cycle of 10 years of burn-up it is shifted to region 2 and the region 1 is filled by fresh natural uranium fuel. This concept is basically applied to all regions. The calculation has been done by using SRAC-Citation system code and JENDL-3.2 library. The effective multiplication factor change increases monotonously during 10 years reactor operation time. There is significant power distribution change in the central part of the core during the BOC and the EOC. It is larger than that in the case of modified CANDLE case which use axial direction burning region move. The burnup level of fuel is slowly grows during the first 15 years but then grow fastly in the rest of burnup history. This pattern is a little bit different from the case of modified CANDLE burnup scheme in Axial direction in which the slow growing burnup period is relatively longer almost half of the burnup history.

A study of239Pu production rate in a water cooled natural uranium blanket mock-up of a fusion–fission hybrid reactor

2016 ◽  
Vol 56 (3) ◽  
pp. 036019 ◽  
Author(s):  
Song Feng ◽  
Rong Liu ◽  
Xinxin Lu ◽  
Yiwei Yang ◽  
Kun Xu ◽  
...  
Keyword(s):  
Production Rate ◽  
Natural Uranium ◽  
Hybrid Reactor ◽  
Uranium Blanket

Design Study of Small Lead-Cooled Fast Reactors Using SiC Cladding and Structure

2006 ◽  
Author(s):  
Abu Khalid Rivai ◽  
Minoru Takahashi
Keyword(s):  
Power Distribution ◽  
Inner Core ◽  
Fuel Cycle ◽  
Outer Core ◽  
Structure Type ◽  
Natural Uranium ◽  
Neutron Energy Spectrum ◽  
Fast Reactors ◽  
Steel Type ◽  
Type Reactor

Effects of SiC cladding and structure on neutronics of reactor core for small lead-cooled fast reactors have been investigated analytically. The fuel of this reactor was uranium nitride with 235U enrichment of 11% in inner core and 13% in outer core. The reactors were designed by optimizing the use of natural uranium blanket and nitride fuel to prolong the fuel cycle. The fuels can be used without reshuffling for 15 years. The coolant of this reactor was lead. A calculation was also conducted for steel cladding and structure type as comparison with SiC cladding and structure type. The results of calculation indicated that the neutron energy spectrum of the core using SiC was slightly softer than that using steel. The SiC type reactor was designed to have criticality at the beginning of cycle (BOC), although the steel type reactor could not have critical condition with the same size and geometry. In other words, the SiC type core can be designed smaller than the steel type core. The result of the design analysis showed that neutron flux distributions and power distribution was made flatter because the outer core enrichment was higher than inner core. The peak power densities could remain constant over the reactor operation. The consumption capability of uranium was quite high, i.e. 13% for 125 MWt reactor and 25% for 375 MWt reactor at EOC.

scholarly journals Optimized core design for small long-life gas cooled fast reactors with natural uranium-thorium-blend as fuel cycle input

2020 ◽  
Vol 1568 ◽  
pp. 012015
Author(s):  
M Ariani ◽  
Supardi ◽  
A Johan ◽  
F Monado ◽  
Z Su’ud ◽  
...  
Keyword(s):  
Fuel Cycle ◽  
Natural Uranium ◽  
Fast Reactors ◽  
Long Life
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