scholarly journals Analisis Burn Up pada Reaktor Pembiak Cepat Berpendingin Pb-Bi dengan Variasi Fraksi Bahan Bakar dan Bahan Pendingin

2019 ◽  
Vol 8 (2) ◽  
pp. 184-190
Author(s):  
Nurkholilah Nurkholilah ◽  
Dian Fitriyani
Keyword(s):  
Breeding Ratio

Telah dilakukan simulasi pada desain Reaktor Pembiak Cepat Berpendingin Logam Cair (Pb-Bi), menggunakan kode simulasi berbasis bahasa pemograman Delphi 7.0 untuk menganalisis pembiakan bahan fisil 239Pu. Perhitungan diterapkan pada teras reaktor 2-D (dua dimensi) geometri r-z (silinder) dengan menempatkan bahan fertil (blanket) pada teras bagian luar. Teras reaktor dirancang beroperasi pada daya 150 MWt dengan bahan bakar campuran uranium dan plutonium nitrida dan pendingin logam cair Pb-Bi.  Simulasi dilakukan terhadap beberapa variasi fraksi bahan bakar (35%, 40% dan 45%) dan bahan pendingin yang diawali dengan penyelesaian persamaan difusi untuk mendapatkan nilai faktor multiplikasi, fluks neutron dan distribusi daya.  Nilai fluks yang diperoleh digunakan untuk menghitung perubahan densitas atom selama reaktor beroperasi yang diperlukan untuk menganalisis susutan bahan bakar.  Hasil perhitungan menunjukkan bahwa nilai faktor multiplikasi neutron (keff) untuk semua fraksi berada dalam kondisi kritis. Untuk mencapai kondisi kritis diperlukan pengaturan enrichment, pada fraksi bahan bakar yang rendah diperlukan enrichment yang besar dan untuk fraksi bahan bakar yang tinggi diperlukan enrichment yang kecil. Pengaturan enrichment berpengaruh juga pada nilai distribusi fluks neutron, distribusi daya, densitas bahan bakar, breeding ratio dan burn up. Kinerja neutronik yang paling optimal diperoleh pada fraksi bahan bakar 45% dan pendingin 35%. Densitas plutonium tertinggi diperoleh pada fraksi bahan bakar 45% yang merupakan hasil reaksi fisi bahan bakar setelah 1 siklus (4 tahun) operasi. Nilai pertambahan densitas isotop diketahui dari nilai Breeding Ratio (BR) yang besar dari 1.Kata kunci: breeding ratio, bahan fisil, burn up, reaktor pembiak cepat

scholarly journals Statistical Analysis of Tritium Breeding Ratio Deviations in the DEMO Due to Nuclear Data Uncertainties

2021 ◽  
Vol 11 (11) ◽  
pp. 5234
Author(s):  
Jin Hun Park ◽  
Pavel Pereslavtsev ◽  
Alexandre Konobeev ◽  
Christian Wegmann
Keyword(s):  
Monte Carlo ◽  
Fusion Reactor ◽  
Nuclear Data ◽  
Data File ◽  
Nuclear Model ◽  
Model Parameters ◽  
Tritium Breeding ◽  
Tritium Breeding Ratio ◽  
Nuclear Data Library ◽  
Breeding Ratio

For the stable and self-sufficient functioning of the DEMO fusion reactor, one of the most important parameters that must be demonstrated is the Tritium Breeding Ratio (TBR). The reliable assessment of the TBR with safety margins is a matter of fusion reactor viability. The uncertainty of the TBR in the neutronic simulations includes many different aspects such as the uncertainty due to the simplification of the geometry models used, the uncertainty of the reactor layout and the uncertainty introduced due to neutronic calculations. The last one can be reduced by applying high fidelity Monte Carlo simulations for TBR estimations. Nevertheless, these calculations have inherent statistical errors controlled by the number of neutron histories, straightforward for a quantity such as that of TBR underlying errors due to nuclear data uncertainties. In fact, every evaluated nuclear data file involved in the MCNP calculations can be replaced with the set of the random data files representing the particular deviation of the nuclear model parameters, each of them being correct and valid for applications. To account for the uncertainty of the nuclear model parameters introduced in the evaluated data file, a total Monte Carlo (TMC) method can be used to analyze the uncertainty of TBR owing to the nuclear data used for calculations. To this end, two 3D fully heterogeneous geometry models of the helium cooled pebble bed (HCPB) and water cooled lithium lead (WCLL) European DEMOs were utilized for the calculations of the TBR. The TMC calculations were performed, making use of the TENDL-2017 nuclear data library random files with high enough statistics providing a well-resolved Gaussian distribution of the TBR value. The assessment was done for the estimation of the TBR uncertainty due to the nuclear data for entire material compositions and for separate materials: structural, breeder and neutron multipliers. The overall TBR uncertainty for the nuclear data was estimated to be 3~4% for the HCPB and WCLL DEMOs, respectively.

scholarly journals Cross-section sensitivity of breeding ratio in a fusion-reactor blanket

1973 ◽  
Author(s):  
D. E. Bartine ◽  
Jr., R. G. Alsmiller ◽  
E. M. Oblow ◽  
F. R. Mynatt
Keyword(s):  
Cross Section ◽  
Fusion Reactor ◽  
Fusion Reactor Blanket ◽  
Breeding Ratio

scholarly journals THE BREEDING RATIO OF A PLUTOMIUM LOADING IN EBR-I

1964 ◽  
Author(s):  
R.R. Smith ◽  
R.O. Haroldsen ◽  
R.E. Horne ◽  
R.G. Matlock
Keyword(s):  
Breeding Ratio

Breeding Ratio For Fast Reactors

1971 ◽  
Vol 10 (2) ◽  
pp. 101-102
Author(s):  
P. Goldschmidt
Keyword(s):  
Fast Reactors ◽  
Breeding Ratio

Design and simulation of a blanket module for TOKAMAK reactors

2019 ◽  
Vol 34 (13) ◽  
pp. 1950103 ◽  
Author(s):  
H. Sadeghi ◽  
M. Habibi
Keyword(s):  
Comsol Multiphysics ◽  
Fusion Reactors ◽  
Tritium Breeding ◽  
Mcnpx Code ◽  
Self Sufficiency ◽  
Proposed Model ◽  
Tokamak Reactors ◽  
Breeding Ratio ◽  
Neutron Multiplier ◽  
Temperature And Pressure

In this paper, we simulated an appropriate model for an advanced breeding blanket of future TOKAMAK fusion reactors with solid breeder (Li4SiO4) building material in the form of pebble beds, ODS ferritic steel as structural material and Beryllium as neutron multiplier. With the MCNPX code, the efficiency of this proposed model for the production and self-sufficiency of tritium was investigated. Total tritium breeding ratio of 1.15 is achieved. The helium-cooled pebble bed system and parameters of temperature and pressure are investigated by COMSOL multiphysics simulating software. The temperature of helium as cooling gas never exceeded 530[Formula: see text]C and the tolerable temperature of beryllium was obtained at 650[Formula: see text]C. In the proposed design, it is adequate to enrich the 6Li to 40%.

scholarly journals Rabbit production under intensive system in rural condition

2016 ◽  
Vol 19 (1-2) ◽  
pp. 107-111
Author(s):  
R Khatun ◽  
MN Islam ◽  
MA Rashid ◽  
S Ahmed
Keyword(s):  
Cost Effectiveness ◽  
Litter Size ◽  
Sexual Maturity ◽  
Gestation Period ◽  
Feed Cost ◽  
Breeding Ratio ◽  
Rabbit Meat ◽  
Production Response ◽  
Intensive System

A total 20 (sixteen female and four male) growing rabbits aged 120 days have been distributed at each farmer’s level in 5 location of Bangladesh; F1 (Dhaka-Pollobi), F2 (Savar-Parbotinagor), F3 (Magura-Boralidhaho), F4 (Magura-Pannandualli), F5 (Magura-Radhanagor) to know the production response and cost effectiveness under intensive in rural condition. The rabbits were reared in their own arrangement. Age of sexual maturity, age of first kidding, percentage of does kidded, gestation period, litter size, weaning period, breeding ratio were not significantly different (P>0.05) among the locations. Feed cost per month was Tk. 903, Tk. 732, Tk. 772, Tk. 1221.96 and Tk. 976 for F1, F2, F3, F4 and F5 respectively for 20 rabbits rearing. Monthly consumption of rabbit meat per family was 4.5kg, 3kg, 2.4 kg, 6.0 kg, in F1, F2, F3, and F5 respectively. Kid mortality (0-10 days) was significantly different (P<0.01) among the locations and this value was recorded 8.47%, 11.11%,12.00%, 8.82% and 13.11% in F1, F2, F3, F4 and F5 respectively. Farmer earned some money by selling their rabbit which was Tk 10200, Tk7600, Tk8400, Tk12400 and Tk7200 /batch and can earn profit around the 49,564; 39,316; 38,536; 62,336 and 35,688 Tk/year in rearing (7batchs/year) 20 rabbit at in F1, F2, F3, F4 and F5, respectively. Rabbit production could be an important micro-livestock component to produce for meeting up extra demand of the country.Bangladesh J. of Livestock Res. 19(1-2): 107-111, Jan-Dec 2012

Effect of Pin and Subassembly Heterogenity in Sodium Void Worth Calculations

2010 ◽  
Author(s):  
G. Raghu Kumar ◽  
C. P. Reddy ◽  
V. Sathyamoorthy
Keyword(s):  
Monte Carlo Code ◽  
Reactor Accident ◽  
Fast Reactors ◽  
Neutron Spectra ◽  
Energy Scenario ◽  
Higher Power ◽  
Breeding Ratio ◽  
Short Doubling Time ◽  
Undesirable Feature ◽  
Total Sodium

Metal fuelled sodium cooled fast reactors are known to have high breeding ratio and short doubling time. Due to these features they play a very important role in the energy scenario, where higher power growth is required. Large sodium cooled fast reactors have positive sodium void coefficient, which is considered to be undesirable feature even though reactor safety can be established for all design based accidents like loss of flow and transient over power accidents. These types of fast reactors, which have harder neutron spectra are having higher sodium void coefficient compared to ceramic fuelled fast reactors. In many of the safety analysis the total sodium void is calculated and it is used in the safely evaluation. However the sodium in the metal fuelled reactor has got three parts, namely bonding sodium, coolant sodium and the sodium in the inter space of subassembly hexagonal cans. In the reactor accident scenario the behavior of these three components of sodium will be different and will effect the sequence of the accident. The finer details, of the fuel sub assembly, are modeled in to Monte Carlo code and the sodium void coefficient is calculated for each of the component for the fuel zones. This study will be helpful in improving safety of the reactor and also reducing the conservatism in the safely features.

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