Proposal for an Experimental Fast ADS Using Th–Pu MOX Fuel for Higher Actinide Transmutation

2019 ◽  
pp. 195-203
Author(s):  
Amar Sinha ◽  
Tushar Roy ◽  
Y. S. Kashyap ◽  
S. Bajpai ◽  
M. Shukla
2003 ◽  
Vol 40 (12) ◽  
pp. 998-1013 ◽  
Author(s):  
Shin-ichi KOYAMA ◽  
Masahiko OSAKA ◽  
Takashi SEKINE ◽  
Katsufumi MOROZUMI ◽  
Takashi NAMEKAWA ◽  
...  
Keyword(s):  
Mox Fuel ◽  

2003 ◽  
Vol 40 (2) ◽  
pp. 104-113 ◽  
Author(s):  
Isamu SATO ◽  
Toshio NAKAGIRI ◽  
Takashi HIROSAWA ◽  
Sinya MIYAHARA ◽  
Takashi NAMEKAWA

2019 ◽  
Vol 12 (4) ◽  
pp. 50-61
Author(s):  
А. Harutyunyan ◽  
S.B. Vygovskiy ◽  
A. Khachatryan

2020 ◽  
Vol 86 (12) ◽  
pp. 15-22
Author(s):  
N. A. Bulayev ◽  
E. V. Chukhlantseva ◽  
O. V. Starovoytova ◽  
A. A. Tarasenko

The content of uranium and plutonium is the main characteristic of mixed uranium-plutonium oxide fuel, which is strictly controlled and has a very narrow range of the permissible values. We focused on developing a technique for measuring mass fractions of uranium and plutonium by controlled potential coulometry using a coulometric unit UPK-19 in set with a R-40Kh potentiostat-galvanostat. Under conditions of sealed enclosures, a special design of the support stand which minimized the effect of fluctuations in ambient conditions on the signal stability was developed. Optimal conditions for coulometric determination of plutonium and uranium mass fractions were specified. The sulfuric acid solution with a molar concentration of 0.5 mol/dm3 was used as a medium. Lead ions were introduced into the background electrolyte to decrease the minimum voltage of hydrogen reduction to –190 mV. The addition of aluminum nitride reduced the effect of fluoride ions participating as a catalyst in dissolving MOX fuel samples, and the interfering effect of nitrite ions was eliminated by introducing a sulfamic acid solution into the cell. The total content of uranium and plutonium was determined by evaluation of the amount of electricity consumed at the stage of uranium and plutonium co-oxidation. Plutonium content was measured at the potentials, at which uranium remains in the stable state, which makes it possible to subtract the contribution of plutonium oxidation current from the total oxidation current. The error characteristics of the developed measurement technique were evaluated using the standard sample method and the real MOX fuel pellets. The error limits match the requirements set out in the specifications for MOX fuel. The technique for measuring mass fractions of uranium and plutonium in uranium-plutonium oxide nuclear fuel was certified. The relative measurement error of the mass fraction of plutonium and uranium was ±0.0070 and ±0.0095, respectively. The relative error of the ratio of the plutonium mass fraction to the sum of mass fractions of uranium and plutonium was ±0.0085.


2016 ◽  
Vol 473 ◽  
pp. 157-166 ◽  
Author(s):  
J. Jayaraj ◽  
P. Krishnaveni ◽  
D. Nanda Gopala Krishna ◽  
C. Mallika ◽  
U. Kamachi Mudali
Keyword(s):  

2015 ◽  
Vol 71 ◽  
pp. 282-292 ◽  
Author(s):  
Kosuke Tanaka ◽  
Hiroshi Yoshimochi ◽  
Hiroshi Obayashi ◽  
Shin-ichi Koyama

2014 ◽  
Vol 2014 ◽  
pp. 1-9 ◽  
Author(s):  
Andrius Slavickas ◽  
Raimondas Pabarčius ◽  
Aurimas Tonkūnas ◽  
Gediminas Stankūnas

The decomposition analysis of void reactivity coefficient for innovative BWR assemblies is presented in this paper. The innovative assemblies were loaded with high enrichment UO2and MOX fuels. Additionally the impact of the moderation enhancement on the void reactivity coefficient through a full fuel burnup discharge interval was investigated for the innovative assembly with MOX fuel. For the numerical analysis the TRITON functional module of SCALE code with ENDF/B-VI cross section library was applied. The obtained results indicate the influence of the most important isotopes to the void reactivity behaviour over a fuel burnup interval of 70 GWd/t for both UO2and MOX fuels. From the neutronic safety concern positive void reactivity coefficient values are observed for MOX fuel at the beginning of the fuel irradiation cycle. For extra-moderated assembly designs, implementing 8 and 12 water holes, the neutron spectrum softening is achieved and consequently the lower void reactivity values. Variations in void reactivity coefficient values are explained by fulfilled decomposition analysis based on neutrons absorption reactions for separate isotopes.


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