International Journal of Nuclear Energy Science and Technology http://www.inderscience.com/browse/index.php?journalID=94&year=2011&vol=6&issue=4 Inderscience Publishers Ltd en-uk International Journal of Nuclear Energy Science and Technology 1741-6361 1741-637X © 2011 Inderscience Publishers Ltd editor@inderscience.com https://www.inderscience.com/images/files/coverImgs/ijnest_scoverijnest.jpg http://www.inderscience.com/browse/index.php?journalID=94&year=2011&vol=6&issue=4 http://www.inderscience.com/link.php?id=45096 This paper describes the development of a new methodology to support strategic planning. It makes use of Technological Roadmapping (TRM) associated with a simplified technique for detecting emerging research fronts by drilling into databases of scientific publications and patents. The customisation of the TRM process to a radio pharmacy unit and its association with an Emerging Research Fronts Detection (ERFD) technique renders a more robust tool for strategic planning for this kind of business, since it combines an inside-out natured process (TRM) with ERFD that is outside-in. The former is very good to capture market and customers expectation trends and the latter is superior to gather insights for technology and product trends. The business unit DIRF (Diretoria de Radiofarmácia) of IPEN-CNEN/SP, located in São Paulo, Brazil, was used as the base of the study and implementation of the methodology presented in this work. A different technology roadmapping methodology applied to a radiopharmacy industry
Robert Joseph Didio; Antonio Carlos Oliveira Barroso
International Journal of Nuclear Energy Science and Technology, Vol. 6, No. 4 (2011) pp. 253 - 270
This paper describes the development of a new methodology to support strategic planning. It makes use of Technological Roadmapping (TRM) associated with a simplified technique for detecting emerging research fronts by drilling into databases of scientific publications and patents. The customisation of the TRM process to a radio pharmacy unit and its association with an Emerging Research Fronts Detection (ERFD) technique renders a more robust tool for strategic planning for this kind of business, since it combines an inside-out natured process (TRM) with ERFD that is outside-in. The former is very good to capture market and customers expectation trends and the latter is superior to gather insights for technology and product trends. The business unit DIRF (Diretoria de Radiofarmácia) of IPEN-CNEN/SP, located in São Paulo, Brazil, was used as the base of the study and implementation of the methodology presented in this work.

]]> 10.1504/IJNEST.2011.045096 International Journal of Nuclear Energy Science and Technology, Vol. 6, No. 4 (2011) pp. 253 - 270 Robert Joseph Didio; Antonio Carlos Oliveira Barroso Faculdades Oswaldo Cruz, Rua Brigadeiro Galvão, 540 – Barra Funda, São Paulo, Brazil. ' Instituto de Pesquisas Energéticas e Nucleares, Comissão Nacional de Energia Nuclear, Av. Prof. Lineu Prestes, 2242, Cid. Universitária, CEP 05508-000 SP, Brazil technological roadmapping emerging research fronts radiopharmacy scientific publications patents. 2012-01-24T23:20:50-05:00 6 4 253 270 2012-01-24T23:20:50-05:00 http://www.inderscience.com/link.php?id=45097 Thermal analysis of a nuclear reactor is very important in determining its design. It can produce desired thermal power without exceeding limitations on core components, which could lead to fuel failure and radioactive release into the environment. In this paper, thermal hydraulic studies of a small nuclear reactor core have been carried out by using two well-known thermal hydraulic codes, Relap5 and THEATRe. The Relap5 code can deal with plate-type fuel elements but the THEATRe code works only for pin-type fuel elements. For this purpose, the THEATRe code has been modified for the plate-type fuel element and then used in the current research. The results obtained from both codes agree well, confirming the accuracy of simulation. Thermal hydraulic analysis of small nuclear reactor core by using comparative approach of THEATRe and Relap5 code
Salah Ud-Din Khan; Minjun Peng; Shahab Ud-Din Khan
International Journal of Nuclear Energy Science and Technology, Vol. 6, No. 4 (2011) pp. 271 - 283
Thermal analysis of a nuclear reactor is very important in determining its design. It can produce desired thermal power without exceeding limitations on core components, which could lead to fuel failure and radioactive release into the environment. In this paper, thermal hydraulic studies of a small nuclear reactor core have been carried out by using two well-known thermal hydraulic codes, Relap5 and THEATRe. The Relap5 code can deal with plate-type fuel elements but the THEATRe code works only for pin-type fuel elements. For this purpose, the THEATRe code has been modified for the plate-type fuel element and then used in the current research. The results obtained from both codes agree well, confirming the accuracy of simulation.

]]> 10.1504/IJNEST.2011.045097 International Journal of Nuclear Energy Science and Technology, Vol. 6, No. 4 (2011) pp. 271 - 283 Salah Ud-Din Khan; Minjun Peng; Shahab Ud-Din Khan College of Nuclear Science and Technology, Harbin Engineering University, Harbin, China. ' College of Nuclear Science and Technology, Harbin Engineering University, Harbin, China. ' College of Mathematics and Statistics, Chongqing University, Chongqing, China thermal hydraulic studies Relap5 code THEATRe code comparative analysis code modification simulation accuracy nuclear reactors reactor core nuclear energy nuclear power. 2012-01-24T23:20:50-05:00 6 4 271 283 2012-01-24T23:20:50-05:00 http://www.inderscience.com/link.php?id=45098 The ignition behaviour of sodium droplets in the atmospheric air has been studied numerically with two available models of pre-ignition stage combustion. Surface reaction is very important in the pre-ignition stage, and the different reaction rate-controlling processes involved in this stage are explained using the shrinking core model. The droplet ignition behaviour is studied by considering the energy balance at the droplet surface in terms of rate of heat generation from the surface oxidation reaction and rate of heat loss to the ambient air. Ignition delay times are evaluated numerically using the two pre-ignition models with different ranges of values to the main parameters that can affect the ignition behaviour of the sodium droplets. Based on these results, the relative capability of the models has been brought out in predicting the droplet ignition behaviour, so that the better model could be chosen for the sodium spray fire analysis code being developed. Analysis results show that the reaction kinetics limited pre-ignition model predicts the limit of ignitability for sodium droplets under different initial and convective conditions, whereas the mass transfer limited pre-ignition model predicts this only under very low oxygen concentrations. Numerical investigation of sodium droplet ignition in the atmospheric air
S. Muthu Saravanan; P. Mangarjuna Rao; B.K. Nashine; P. Chellapandi
International Journal of Nuclear Energy Science and Technology, Vol. 6, No. 4 (2011) pp. 284 - 297
The ignition behaviour of sodium droplets in the atmospheric air has been studied numerically with two available models of pre-ignition stage combustion. Surface reaction is very important in the pre-ignition stage, and the different reaction rate-controlling processes involved in this stage are explained using the shrinking core model. The droplet ignition behaviour is studied by considering the energy balance at the droplet surface in terms of rate of heat generation from the surface oxidation reaction and rate of heat loss to the ambient air. Ignition delay times are evaluated numerically using the two pre-ignition models with different ranges of values to the main parameters that can affect the ignition behaviour of the sodium droplets. Based on these results, the relative capability of the models has been brought out in predicting the droplet ignition behaviour, so that the better model could be chosen for the sodium spray fire analysis code being developed. Analysis results show that the reaction kinetics limited pre-ignition model predicts the limit of ignitability for sodium droplets under different initial and convective conditions, whereas the mass transfer limited pre-ignition model predicts this only under very low oxygen concentrations.

]]> 10.1504/IJNEST.2011.045098 International Journal of Nuclear Energy Science and Technology, Vol. 6, No. 4 (2011) pp. 284 - 297 S. Muthu Saravanan; P. Mangarjuna Rao; B.K. Nashine; P. Chellapandi Nuclear and Safety Engineering Group, Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam 603102, India. ' Nuclear and Safety Engineering Group, Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam 603102, India. ' Nuclear and Safety Engineering Group, Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam 603102, India. ' Nuclear and Safety Engineering Group, Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam 603102, India sodium droplet combustion pre-ignition stage combustion ignition delay time shrinking core model sodium spray fire nuclear energy FBR fast breeder reactors nuclear power sodium droplets reaction kinetics. 2012-01-24T23:20:50-05:00 6 4 284 297 2012-01-24T23:20:50-05:00 http://www.inderscience.com/link.php?id=45099 A semi-Markov process model is developed for the reliability analysis of Main Feedwater Valve (MFV) controller system that is used for regulating the water level in a steam generator. The proposed model is generalisation of a Markov process model reported in the literature and allows the use of non-exponential distribution for various state transition times. Reliability analysis of digital feedwater regulating valve controller system using a semi-Markov process model
Arun Veeramany; Mahesh D. Pandey
International Journal of Nuclear Energy Science and Technology, Vol. 6, No. 4 (2011) pp. 298 - 309
A semi-Markov process model is developed for the reliability analysis of Main Feedwater Valve (MFV) controller system that is used for regulating the water level in a steam generator. The proposed model is generalisation of a Markov process model reported in the literature and allows the use of non-exponential distribution for various state transition times.

]]> 10.1504/IJNEST.2011.045099 International Journal of Nuclear Energy Science and Technology, Vol. 6, No. 4 (2011) pp. 298 - 309 Arun Veeramany; Mahesh D. Pandey Department of Civil and Environmental Engineering, University of Waterloo, Waterloo, Ontario N2L 3G1, Canada. ' Department of Civil and Environmental Engineering, University of Waterloo, Waterloo, Ontario N2L 3G1, Canada digital instrumentation digital control reliability analysis semi-Markov nuclear power plants NPP reliability semi-Markov process model feedwater regulation valve controllers process modelling steam generators nuclear energy nuclear power. 2012-01-24T23:20:50-05:00 6 4 298 309 2012-01-24T23:20:50-05:00 http://www.inderscience.com/link.php?id=45100 In this paper, He's variational iteration method and modified decomposition method are applied to obtain the analytical approximate solution of the neutron diffusion equation with fixed source. The main properties of these methods lie in their flexibility and ability to solve linear as well as non-linear equations accurately and conveniently. The explicit solution of the neutron diffusion equation has been presented in the closed form by an infinite series and then the numerical solution has been represented graphically. Application of modified decomposition method and variational iteration method for the solution of the one group neutron diffusion equation with fixed source
S. Saha Ray; A. Patra
International Journal of Nuclear Energy Science and Technology, Vol. 6, No. 4 (2011) pp. 310 - 320
In this paper, He's variational iteration method and modified decomposition method are applied to obtain the analytical approximate solution of the neutron diffusion equation with fixed source. The main properties of these methods lie in their flexibility and ability to solve linear as well as non-linear equations accurately and conveniently. The explicit solution of the neutron diffusion equation has been presented in the closed form by an infinite series and then the numerical solution has been represented graphically.

]]> 10.1504/IJNEST.2011.045100 International Journal of Nuclear Energy Science and Technology, Vol. 6, No. 4 (2011) pp. 310 - 320 S. Saha Ray; A. Patra Department of Mathematics, National Institute of Technology, Rourkela 769008, India. ' Department of Mathematics, National Institute of Technology, Rourkela 769008, India variational iteration method Adomian decomposition method neutron diffusion equation nuclear reactors fixed source. 2012-01-24T23:20:50-05:00 6 4 310 320 2012-01-24T23:20:50-05:00 http://www.inderscience.com/link.php?id=45101 An equation representing a law of physics is said to be Lorentz covariant if it can be written in terms of Lorentz covariant quantities. The key property of Lorentz covariant equations is that if they hold in one inertial frame, then they hold in any inertial frame. This condition is a requirement according to the principle of relativity, that is, all non-gravitational laws must make the same predictions for identical experiments taking place at the same space-time event in two different inertial frames of reference. We divided the presentation into three main sections: introduction for a simple case, the analysis of complex motion under electromagnetic Lorentz force in particle accelerators and we end with a covariant formulation for the Hooke law. Lorentz covariant formulation for the laws of physics – particle and elastic body dynamics
A. Sfarti
International Journal of Nuclear Energy Science and Technology, Vol. 6, No. 4 (2011) pp. 321 - 334
An equation representing a law of physics is said to be Lorentz covariant if it can be written in terms of Lorentz covariant quantities. The key property of Lorentz covariant equations is that if they hold in one inertial frame, then they hold in any inertial frame. This condition is a requirement according to the principle of relativity, that is, all non-gravitational laws must make the same predictions for identical experiments taking place at the same space-time event in two different inertial frames of reference. We divided the presentation into three main sections: introduction for a simple case, the analysis of complex motion under electromagnetic Lorentz force in particle accelerators and we end with a covariant formulation for the Hooke law.

]]> 10.1504/IJNEST.2011.045101 International Journal of Nuclear Energy Science and Technology, Vol. 6, No. 4 (2011) pp. 321 - 334 A. Sfarti UC Berkeley, 387 Soda Hall, CA, USA Lorentz covariance Lorentz force accelerated motion of particles particle accelerators relativistic covariant Hooke law particle dynamics elastic body dynamics Lorentz covariant equations. 2012-01-24T23:20:50-05:00 6 4 321 334 2012-01-24T23:20:50-05:00