Stability Margin Analysis of Gas-Cooled Reactor Design Models

To determined the safety margin of different Gas-Cooled Reactor Design, linear regression analysis is applied on three typical Gas-Cooled Nuclear Reactor design models, viz Gas-Cooled Reactor Design I (GCRD I), Gas-cooled Reactor Design II (GCRD II) and Gas-cooled Reactor Design III (GCRD III). Empirical expressions are obtained for GCRD I model, GCRD II model and GCRD III model. The results of the statistical analyses on these three types of nuclear reactor models reveal that the GCRD III promises to be most stable and therefore safer. The implication of this research effort to Nigeria’s nuclear power project is discussed. Keywords: Linear Regression Analysis, Gas-Cooled Reactor Design Models, Safety Margin, Safety Factor, ?, Optimization, Stability Margin in Nuclear Power Reactor Design Models

Study of Pressurized Water Reactor Design Models

This study of pressurized water reactor design models involves the application of linear regression analysis on two typical Water-Cooled Nuclear Reactor design models, viz Pressurized Water Reactor Design I (PWRD I) and Pressurized Water Reactor Design II (PWRD II). Empirical expressions are obtained for PWRD I model and PWRD II model. The results of the statistical analyses on these two types of nuclear reactor models reveal that the PWRD II promises to be more stable and therefore safer. The implication of this research effort to Nigeria’s nuclear power project is discussed. Keywords: Linear Regression Analysis, Pressurized Water Reactor Design Models, Safety Factor, ?, Optimization, Stability Margin in Nuclear Power Reactor Design

Comparative Analysis of Water-Cooled Reactor Design Models and Gas-Cooled Reactor Design Models

To determined the most stable and probably the safest reactor between water-cooled reactor designs and gas-cooled reactor designs in terms of their coolant, Linear Regression Analysis is applied on four typical nuclear reactor design models, viz water-cooled reactor design I (WCRD I), water-cooled reactor design II (WCRD II), gas-cooled reactor design I (GCRD I) and gas-cooled reactor design II (GCRD II). Empirical expressions are obtained for WCRD I model, WCRD II model, GCRD I model and GCRD II model. The results of the statistical analyses on these four types of nuclear reactor models reveal that the GCRD II promises to be most stable. The implication of this research effort to Nigeria’s nuclear power project is discussed. Keywords: Linear Regression Analysis, Water-Cooled Reactor Design Models, Gas-Cooled Reactor Design Models, Safety Factor, ?, Optimization, Stability Margin in Nuclear Power Reactor Design

The Nigeria Energy Challenge and the Nuclear Energy Option

Nigeria and other nations are looking for solution to their energy crisis and nuclear energy seem to be an option as Federal Government have mandated NAEC, an apex arm of government charge with development of nuclear energy programme for the country to look at the possibility of using nuclear power to generate electricity. The study investigated risk management of nuclear project so as to guide against wastage or loss in the economy. More also, this paper look at the challenges involved in nuclear power industry, assessed the prospects in Nigeria, examined nuclear power plant safety in the country by taken cognizant of Nigeria maintenance culture and environmental challenges. Furthermore, the study examined the advantages of nuclear power plants because historically they are highly complex and prime innovators of new technology. The research implication was that adequate preparation on nuclear safety, education, strong public sensitization, foundational public awareness creation and acceptances, and then coupled with strong legislative nuclear power policy are necessary factors for the development of the sector in Nigeria. Keywords: Nigeria energy crisis, nuclear energy option for Nigeria, nuclear power plants challenges and prospects, safety aspect of nuclear power plant in Nigeria, maintenance culture and environmental challenges, nuclear power plants advantages and cost implication

Parity deduction from cross section analysis of isotopes of some transuranium elements

Coupled-channels optical model code OPTMAN is used as an alternative to experimental approach to evaluate the total reaction cross section for eight selected isotopes of heavy rotational nuclei of the transuranium elements over an energy range of 10 to 20 MeV. The selected isotopes are the 93Np237, 94Pu238, 94Pu240, 94Pu241, 94Pu242, 95Am243, 96Cm244 and 95Am245. Their choice is as a result of their importance in the modern day nuclear reactor and the energy range 10 – 20 MeV is the energy range of neutron produced in neutron generators and the maximum energy possessed by neutrons which are born in fission reaction. Results show that the percentage deviation of total cross section from ENDF values obtained for this work is less than 1% at 14 MeV and above for 93Np237 and at 16 MeV and above for 94Pu238, 94Pu240, 94Pu241 and 95Am243 while at 18 MeV and above for 94Pu242, 96Cm244 and 95Am245. This work observed that the nucleus of transuranium elements is symmetric and the activities of rotation and vibrations (β–quadrupole, octupole vibrations and γ-quadrupole vibrations) cannot be ignored. Deductions in terms of parity in the transuranium elements revealed that the effects of the collective characteristics are exhibited by the neutrons and countered by the protons. This work compared well with the 6 % of Basunia in 2009 and 5 % of Paradela in 2011 using indirect measurement based on the surrogate ratio method and ECIS code respectively and is found to agree with about 1.3 % increase in accuracy