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00319 The upgrading of petroleum residuum and coal in catalytic coprocessing
05 96lOO314 Study of the structure and components of tar from Shenfu coal Wang, S. and Guo, S. (In Chinese)
Ranliao Huaxue Xuebao, 1995, 23, (2), 198-204.
The yield, distillation range, elemental composition and other properties of solid heat carrier retorting tar from Shenfu coal were determined. The retorting temperature had a great effect on the yield and properties of the tar.
96lOQ316 product
Study on the tackifying ability of peat degradation
Liu, L. and Guo, S.
M&an Zhuanhua, 1995, 18, (l), 94-97. (In Chinese)
Discusses the tackifying maldehyde resin.
96100316
ability of peat degradation
product
on urea-for-
Study on thermal insulating material made from
coal refuse Liu, X. et al., Huanjing Kexue Xuebao, 1995, 15, (l), 122-128. (In Chinese) Thermal insulating materials that possess specific property of higher compressive strength and lower thermal condition is principally made from coal refuse; and it is a new way for the comprehensive utilization of coal refuse. The paper reveals the effects of the entering quantity of refuse and the impurities Fe3’, T14*, et al., in refuse on the quality of the thermal insulating material and on the process, through analyzing the physicochemical change of coal refuse in the sintering process.
96100317 Synthesis of A-type zeoiite from fly ash pretreated with solid sodrum hydroxide moue, K. et al., Muki Materiaru, 1995, 2, (255), 108-114. (In Japanese) The paper describes how A-type zeolite was synthesized by hydrothermal reaction of the pretreated fly ash and an admixture of NaOH, Na aluminate, water, and seed of A-type zeolite at 90” for 2 hours. The yield of A-type zeolite increased lineally with the reaction ratio between the fly ash and solid NaOH and was approximately 65% at the optimum condition.
96166316
Trace element characterization of coal fly ash
particles Bogdanovic, I. et al., Nucl. Insirum. Methods Phys. Rex, Sect. B, 1995, 99, (1) 402-405. X-ray fluorescence analysis, proton-induced X-ray emission, Rutherford backscattering, and scanning transmission ion microscopy were used for a study of trace elements distributions in Greek lignites and their ashes, Presents the results of analyses of 50 individual fly ash particles.
96100319 The upgrading of petroleum residuum and coal in catalytic coprocessing Hwang, J. et al., Korean _I. Chem. Eng., 1995, 12, (2), 193-197. Describes the combined catalytic reactions using different type of petroleum residue and coal performed at 425” and 60 min in the presence of Hz to upgrade both materials to hi h-quality synthetic fuels, To improve thts coprocessing technology, the ef Pect of the chemical and physical properties of both materials on the coprocessing product yields was investigated through a parametric study.
05 NUCLEAR FUELS Scientific,
96100320
Technical
Adding erbium to increase RBMK safety
Panushkin, A. K. er al., Nuclear E;tgng. Inf., Nov. 1995.40, (496). 40-41. The goal of improving the reliability and safety of RBMK reactors by reducing the void coefficient of reactivity has been strived for over many years. Mashinostroitelny Zavod believes it has reached that goal by adding erbium to fuel as a burnable absorber. Its effectiveness will be put to the test in pilot batches loaded into cores at Ignalina and Leningrad.
96lQO321
Ageing Europeans trust to networks
Von Estorff, U. et al., Nuclear Engng. Int., Dec. 1995, 40, (497) 24-27. Discusses how the three pan-European networks enable European organisations to work together to assess the materials used for structural components and the effects of ageing on those materials.
Nuclear fuels (scientific, technical)
96100322 Aibedo calculations for candidate fusion reactor materials used in the inboard side of a corn act Tokamak reactor and the effects of using such materPais on the tritium breeding Dhab’an, A. H. and Beynon, T. D. Progress In Nuclear Energy, 1994,28, (4), 391-403. In this paper the total neutron albedo and associated energy distribution for 10 candidate fusion reactor materials have been calculated. The angular distribution of reflected neutrons for monodirectional 14.1 MeV neutrons incident on slabs of Pb, Be, and W are presented and the dependence of albedo on neutron energy and incident angle has been investigated. Finally, the impact of the tritium breeding of the outboard blanket of the choice of material used in the inboard side of the reactor has been assessed. It has been found that the largest total neutron albedos are those of neutron multiplying materials, whilst among non-multiplying materials tungsten yields the largest albedo and B,,H,, yields the lowest.
96100323 Analysis of the sampling distribution in Monte Carlo radiation transport calculations
Vieira, W. J. and Stevens, P. N. Ann. Nucl. Energy, Jan. 1995, 22, (l), 51-55. Undersampling conditions can often lead to an estimated solution which can be significantly smaller than the true solution-but the estimate of the standard deviation may seem acceptably small. Various techniques devised to flag undersampling in Monte Carlo calculations were investigated. The calculations of F values, of the variance of the variance, and of the figure of merit, can be helpful but were not conclusive. A particle contribution distribution histogram which is omput at the end of each batch provided a very effective way of detecting undersampling.
96100324 Analysis of the spatial distribution of aerosol dispersions Gimenez, M. ef al., Ann. Nucl. Energy Jan. 1995, 22, (l), 17-28. The dispersion of contaminant particles m a fluid media is studied considering the main mechanisms for coagulation and removal, with special emphasis on its application to the field of nuclear reactor safety. Starting from the general balance equation for the aerosol size spectrum as a function of position and time, a diffusion-convection equation is derived using the method of moments. The equation is analyzed for a variety of cases, and the solutions are discussed and cornpar:d with existing codes calculations as well as exact analytical solutions. The method presented is very useful in the sense that it reduces the complexity of the spatial aerosol dispersion to the domain of the classical diffusion-convection transport analysis.
Application of a fuzzy learning algorithm to nuclear steam generator level control yz~;ly;y~ Y. and Seong, P. H. Ann. Nucl. Energy, Mar.-Apr. 1995, 22, (3), 96100325
In order’to reduce the load of tuning works by trial-and-error for obtaining the best control performance of conventional fuzzy control algorithm, a fuzzy control algorithm with learning function is investigated in this work. This fuzzy control algorithm can make its rule base and tune the membership functions automatically by use of learning function which needs the data from the control actions of the plant operator or other controllers such as PI controller. Learning process in fuzzy control algorithm is to find the optimal values of parameters, which consist of the membership functions and the rule base, by gradient descent method. Learning speed of gradient descent is significantly improved in this work with the addition of modified momentum term. This control algorithm is applied to the steam generator level control by computer simulations.
96100326 Application of recent iron evaluations of ENDF/B, JEF and JENDL to neutron transport calculations through light water reactor pressure vessel Kim, J. D. et al., Ann. Nucl. Energy, May 1995, 22, (5), 283-290. It has been generally known that iron cross section sets derived from ENDFB-IV and ENDFB-V evaluations underestimate the transmission of fast neutrons through light water reactor pressure vessel. In recent years, ENDFIB, JEF and JENDL iron data have been newly revised. To verify an applicability of the new iron evaluations to neutron transport calculations through the pressure vessel, fast neutron spectra and various threshold dosimeter activities obtained with the revised iron data has been intercompared. The results calculated with ENDF/B-VI iron data amoung those show good agreements with the measurements.
Avoid iosin your head. STUK experiments on ECCS strainer pressure 8 rop caused by insulation debris
96100327
Hyvarinen, J. Nuclear Engng. Inr., Nov. 1995, 40, (496), 18, 20, 22. In the wake of the Barseback incident in 1992, the Finnish nuclear utilities carried out extensive backfitting of their ECCS strainers (BWRs) and containment sumps (PWRs) to guarantee undisturbed emergency core and containment cooling in the event of a loss of coolant accident (LOCA). An element of this backfitting effort in the BWRs was to install metallic insulation in the containment. In evaluating the backfitting measures, the Finnish regulator STUK did experiments to investigate the transport and clogging properties of both fibrous and metallic insulation.
Fuel and Energy Abstracts January 1996
19
Ranliao Huaxue Xuebao, 1995, 23, (2), 198-204.
The yield, distillation range, elemental composition and other properties of solid heat carrier retorting tar from Shenfu coal were determined. The retorting temperature had a great effect on the yield and properties of the tar.
96lOQ316 product
Study on the tackifying ability of peat degradation
Liu, L. and Guo, S.
M&an Zhuanhua, 1995, 18, (l), 94-97. (In Chinese)
Discusses the tackifying maldehyde resin.
96100316
ability of peat degradation
product
on urea-for-
Study on thermal insulating material made from
coal refuse Liu, X. et al., Huanjing Kexue Xuebao, 1995, 15, (l), 122-128. (In Chinese) Thermal insulating materials that possess specific property of higher compressive strength and lower thermal condition is principally made from coal refuse; and it is a new way for the comprehensive utilization of coal refuse. The paper reveals the effects of the entering quantity of refuse and the impurities Fe3’, T14*, et al., in refuse on the quality of the thermal insulating material and on the process, through analyzing the physicochemical change of coal refuse in the sintering process.
96100317 Synthesis of A-type zeoiite from fly ash pretreated with solid sodrum hydroxide moue, K. et al., Muki Materiaru, 1995, 2, (255), 108-114. (In Japanese) The paper describes how A-type zeolite was synthesized by hydrothermal reaction of the pretreated fly ash and an admixture of NaOH, Na aluminate, water, and seed of A-type zeolite at 90” for 2 hours. The yield of A-type zeolite increased lineally with the reaction ratio between the fly ash and solid NaOH and was approximately 65% at the optimum condition.
96166316
Trace element characterization of coal fly ash
particles Bogdanovic, I. et al., Nucl. Insirum. Methods Phys. Rex, Sect. B, 1995, 99, (1) 402-405. X-ray fluorescence analysis, proton-induced X-ray emission, Rutherford backscattering, and scanning transmission ion microscopy were used for a study of trace elements distributions in Greek lignites and their ashes, Presents the results of analyses of 50 individual fly ash particles.
96100319 The upgrading of petroleum residuum and coal in catalytic coprocessing Hwang, J. et al., Korean _I. Chem. Eng., 1995, 12, (2), 193-197. Describes the combined catalytic reactions using different type of petroleum residue and coal performed at 425” and 60 min in the presence of Hz to upgrade both materials to hi h-quality synthetic fuels, To improve thts coprocessing technology, the ef Pect of the chemical and physical properties of both materials on the coprocessing product yields was investigated through a parametric study.
05 NUCLEAR FUELS Scientific,
96100320
Technical
Adding erbium to increase RBMK safety
Panushkin, A. K. er al., Nuclear E;tgng. Inf., Nov. 1995.40, (496). 40-41. The goal of improving the reliability and safety of RBMK reactors by reducing the void coefficient of reactivity has been strived for over many years. Mashinostroitelny Zavod believes it has reached that goal by adding erbium to fuel as a burnable absorber. Its effectiveness will be put to the test in pilot batches loaded into cores at Ignalina and Leningrad.
96lQO321
Ageing Europeans trust to networks
Von Estorff, U. et al., Nuclear Engng. Int., Dec. 1995, 40, (497) 24-27. Discusses how the three pan-European networks enable European organisations to work together to assess the materials used for structural components and the effects of ageing on those materials.
Nuclear fuels (scientific, technical)
96100322 Aibedo calculations for candidate fusion reactor materials used in the inboard side of a corn act Tokamak reactor and the effects of using such materPais on the tritium breeding Dhab’an, A. H. and Beynon, T. D. Progress In Nuclear Energy, 1994,28, (4), 391-403. In this paper the total neutron albedo and associated energy distribution for 10 candidate fusion reactor materials have been calculated. The angular distribution of reflected neutrons for monodirectional 14.1 MeV neutrons incident on slabs of Pb, Be, and W are presented and the dependence of albedo on neutron energy and incident angle has been investigated. Finally, the impact of the tritium breeding of the outboard blanket of the choice of material used in the inboard side of the reactor has been assessed. It has been found that the largest total neutron albedos are those of neutron multiplying materials, whilst among non-multiplying materials tungsten yields the largest albedo and B,,H,, yields the lowest.
96100323 Analysis of the sampling distribution in Monte Carlo radiation transport calculations
Vieira, W. J. and Stevens, P. N. Ann. Nucl. Energy, Jan. 1995, 22, (l), 51-55. Undersampling conditions can often lead to an estimated solution which can be significantly smaller than the true solution-but the estimate of the standard deviation may seem acceptably small. Various techniques devised to flag undersampling in Monte Carlo calculations were investigated. The calculations of F values, of the variance of the variance, and of the figure of merit, can be helpful but were not conclusive. A particle contribution distribution histogram which is omput at the end of each batch provided a very effective way of detecting undersampling.
96100324 Analysis of the spatial distribution of aerosol dispersions Gimenez, M. ef al., Ann. Nucl. Energy Jan. 1995, 22, (l), 17-28. The dispersion of contaminant particles m a fluid media is studied considering the main mechanisms for coagulation and removal, with special emphasis on its application to the field of nuclear reactor safety. Starting from the general balance equation for the aerosol size spectrum as a function of position and time, a diffusion-convection equation is derived using the method of moments. The equation is analyzed for a variety of cases, and the solutions are discussed and cornpar:d with existing codes calculations as well as exact analytical solutions. The method presented is very useful in the sense that it reduces the complexity of the spatial aerosol dispersion to the domain of the classical diffusion-convection transport analysis.
Application of a fuzzy learning algorithm to nuclear steam generator level control yz~;ly;y~ Y. and Seong, P. H. Ann. Nucl. Energy, Mar.-Apr. 1995, 22, (3), 96100325
In order’to reduce the load of tuning works by trial-and-error for obtaining the best control performance of conventional fuzzy control algorithm, a fuzzy control algorithm with learning function is investigated in this work. This fuzzy control algorithm can make its rule base and tune the membership functions automatically by use of learning function which needs the data from the control actions of the plant operator or other controllers such as PI controller. Learning process in fuzzy control algorithm is to find the optimal values of parameters, which consist of the membership functions and the rule base, by gradient descent method. Learning speed of gradient descent is significantly improved in this work with the addition of modified momentum term. This control algorithm is applied to the steam generator level control by computer simulations.
96100326 Application of recent iron evaluations of ENDF/B, JEF and JENDL to neutron transport calculations through light water reactor pressure vessel Kim, J. D. et al., Ann. Nucl. Energy, May 1995, 22, (5), 283-290. It has been generally known that iron cross section sets derived from ENDFB-IV and ENDFB-V evaluations underestimate the transmission of fast neutrons through light water reactor pressure vessel. In recent years, ENDFIB, JEF and JENDL iron data have been newly revised. To verify an applicability of the new iron evaluations to neutron transport calculations through the pressure vessel, fast neutron spectra and various threshold dosimeter activities obtained with the revised iron data has been intercompared. The results calculated with ENDF/B-VI iron data amoung those show good agreements with the measurements.
Avoid iosin your head. STUK experiments on ECCS strainer pressure 8 rop caused by insulation debris
96100327
Hyvarinen, J. Nuclear Engng. Inr., Nov. 1995, 40, (496), 18, 20, 22. In the wake of the Barseback incident in 1992, the Finnish nuclear utilities carried out extensive backfitting of their ECCS strainers (BWRs) and containment sumps (PWRs) to guarantee undisturbed emergency core and containment cooling in the event of a loss of coolant accident (LOCA). An element of this backfitting effort in the BWRs was to install metallic insulation in the containment. In evaluating the backfitting measures, the Finnish regulator STUK did experiments to investigate the transport and clogging properties of both fibrous and metallic insulation.
Fuel and Energy Abstracts January 1996
19