Potentiometric determination of uranium in phosphate-perchlorate medium and its applicability in the natural uranium fuel cycle

1986 ◽  
Vol 99 (2) ◽  
pp. 397-406 ◽  
Author(s):  
A. K. Pandey ◽  
R. C. Sharma ◽  
R. H. Iyer

2015 ◽  
Vol 68 (3) ◽  
pp. 566-572 ◽  
Author(s):  
S. C. Xiao ◽  
Jing Zhao ◽  
X. Heng ◽  
X. Y. Sheng ◽  
Z. Zhou ◽  
...  


2017 ◽  
Vol 3 (2) ◽  
Author(s):  
S. Banerjee ◽  
H. P. Gupta

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.



2013 ◽  
Vol 772 ◽  
pp. 530-535 ◽  
Author(s):  
Zaki Su’ud ◽  
Feriska H. Irka ◽  
Taufiq Imam ◽  
H. Sekimoto ◽  
P. Sidik

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.



2016 ◽  
Vol 12 (3) ◽  
pp. 177-184 ◽  
Author(s):  
Gamal Abdel-Hafiz Mostafa ◽  
Mohammed Hefnawy ◽  
Mohammed Abounassif ◽  
Amer Alanazi ◽  
Abdulrahman Al-Majed ◽  
...  


2019 ◽  
Vol 151 ◽  
pp. 104222 ◽  
Author(s):  
Sally E.A. Elashery ◽  
Nour F. Attia ◽  
M.M. Omar ◽  
Hager M.I. Tayea




1975 ◽  
Vol 2 (4) ◽  
pp. 348-350 ◽  
Author(s):  
Shang J. Yao ◽  
Sidney K. Wolfson ◽  
Joyce M. Tokarsky


1936 ◽  
Vol 8 (1) ◽  
pp. 16-19 ◽  
Author(s):  
Miroslav W. Tamele ◽  
Lloyd B. Ryland


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