[en] Nuclear Data Bank generation, is a process in which a great amount of resources is required, both computing and humans. If it is taken into account that at some times it is necessary to create a great amount of those, it is convenient to have a reliable tool that generates Data Banks with the lesser resources, in the least possible time and with a very good approximation. In this work are shown the results obtained during the development of INTPOLBI code, use to generate Nuclear Data Banks employing bicubic polynominal interpolation, taking as independent variables the uranium and gadolinia percents. Two proposal were worked, applying in both cases the finite element method, using one element with 16 nodes to carry out the interpolation. In the first proposals the canonic base was employed, to obtain the interpolating polynomial and later, the corresponding linear equation systems. In the solution of this systems the Gaussian elimination methods with partial pivot was applied. In the second case, the Newton base was used to obtain the mentioned system, resulting in a triangular inferior matrix, which structure, applying elemental operations, to obtain a blocks diagonal matrix, with special characteristics and easier to work with. For the validation tests, a comparison was made between the values obtained with INTPOLBI and INTERTEG (create at the Instituto de Investigaciones Electricas (MX) with the same purpose) codes, and Data Banks created through the conventional process, that is, with nuclear codes normally used. Finally, it is possible to conclude that the Nuclear Data Banks generated with INTPOLBI code constitute a very good approximation that, even though do not wholly replace conventional process, however are helpful in cases when it is necessary to create a great amount of Data Banks

[en] In this work it plans to be carried out the Probabilistic Safety Analysis level 1 for the Modified Design of the IRIS Reactor. To generate computational tools of calculation of the analysis of the reactors of IV Generation and to optimize the use of nuclear fuel. To elaborate the economic analysis of the IRIS Reactor. (Author)

[en] In this work the results obtained when analyzing new strategies in the reload designs of nuclear fuel and models of control bars, for boiling water reactors are presented. The idea is to analyze the behaviour of the reactor during an operation cycle, when the heuristic rules are not used (commonly used by expert engineers in both designs). Specifically was analyzed the rule of low leak and the load strategy Control Cell Core for the design of a fuel reload. In a same way was analyzed the rule of prohibiting the use of the intermediate positions in the control bars, as well as the construction of bar models based on load strategies type Control Cell Core. In the first analysis a balance and transition cycle were used. For the second analysis only a transition cycle was used, firstly with the reloads designed in the first analysis and later on with reloads built by other methods. For the simulation of the different configurations proposed in both cases, was used the code Simulate-3. To obtain the designs in both studies, the heuristic techniques or neural networks and taboo search were used. The obtained results show that it can be omitted of some rules used in the ambit for the mentioned designs and even so to obtain good results. To carry out this investigation was used Dell work station under Li nux platform. (Author)

[en] In this work are presented the obtained preliminary results to design nuclear fuel cells for boiling water reactors (BWR) using new strategies. To carry out the cells design some of the used rules in the fuel administration were discarded and other were implemented. The above-mentioned with the idea of making a comparative analysis between the used rules and those implemented here, under the hypothesis that it can be possible to design nuclear fuel cells without using all the used rules and executing the security restrictions that are imposed in these cases. To evaluate the quality of the obtained cells it was taken into account the power pick factor and the infinite multiplication factor, in the same sense, to evaluate the proposed configurations and to obtain the mentioned parameters was used the CASMO-4 code. To optimize the design it is uses the combinatorial optimization technique named Path Re linking and the Dispersed Search as local search method. The preliminary results show that it is possible to implement new strategies for the cells design of nuclear fuel following new rules. (Author)

[en] Preliminary results are presented for the design of nuclear fuel cells, used in the design of new fuel assemblies. To obtain these results, heuristic techniques known as neural networks and a hybrid between scattered search and trajectory re-chaining were implemented. Because the computational requirements are large, it was necessary to implement parallel computing tools to reduce response times. The objective function implemented includes the local peak power factor of the cell throughout its life, as well as the infinite neutron multiplication factor. The enrichment of ²³⁵U pills increased, beyond the usual, allowing pills with up to 5.9% enrichment. The designed cells were used to propose new fuel assemblies for BWR reactors. To test our designs, the fuel assemblies were used in an optimization process to generate the refills and the respective control bar patterns. Our results show that it is possible to increase the bank of pills available for the design of cells and design refills that comply with the security restrictions and the requested energy requirements. (Author)

[en] In this work the results to plan different scenarios for designing a nuclear fuel reload are shown. Given a reload with specific energy requirements, the objective is to verify the feasibility of using either a greater number of fresh fuel with less uranium enrichment, or otherwise reduce the number of fresh fuel assemblies and therefore they have a higher average uranium enrichment. For the study a cycle balance 18-month basis with 112 fresh assemblies divided into two lots, with energy produced of 10,075 Mwd/Tu was used. For the designs under the mentioned scenarios, the heuristic techniques known as taboo search and neural networks were used. To verify the feasibility of obtained reloads an economic study of the reload costs was performed. The results showed that is possible to design reloads under the two scenarios, but was more complicated decrease the amount of fresh fuel assemblies. In both scenarios was possible to reduce manufacturing costs of fuel and according to purely static calculation, it would be possible to increase the energy produced. (Author)

[en] This work presents the preliminary results of a statistical analysis carried out for the design of nuclear fuel cells. The analysis consists in verifying the behavior of a cell, related with the frequency of the pines used for its design. In this preliminary study was analyzed the behavior of infinite multiplication factor and the peak factor of local power. On the other hand, the mentioned analysis was carried out using a pines group of enriched uranium previously established, for which varies the pines frequency used in the design. To carry out the study, the CASMO-IV code was used. The obtained designs are for the different axial areas of a fuel assembly. A balance cycle of the unit 1 of the nuclear power plant of Laguna Verde was used like reference. To obtain the result of the present work, systems that are already had and in which have already been implemented the heuristic techniques of ant colonies, neural networks and a hybrid between the dispersed search and the trajectories re-chaining. The results show that is possible to design nuclear fuel cells with a good performance, if is considered a statistical behavior in the frequency of the used pines, in a same way. (Author)

[en] The fuel management in a nuclear power reactor for the electricity production has a main objective the efficient use of the nuclear fuel during the reactor operation, without to neglect the related with the security and to achieve the economic profitability in turn. The efficient use of the fuel implies to extract the maximum electric power of the uranium that the reactor security is guaranteed and provide economic benefits for the owner company of the nuclear reactor. In Mexico, the Federal Commission of Electricity have two boiling water reactors in the nuclear power plant of Laguna Verde (Veracruz, Mexico). In this nuclear power plant the operation of a nuclear reactor is carried out by means of operation cycles that have 18 months of duration at the moment. At the end of each cycle, the reactor stops to carry out the fuel recharge phase. The fuel assemblies can be removed or relocated in each cycle. Approximately a fourth part of the fuel assemblies are replaced by fresh fuels. This means that each fuel assemble remains, on the average, 4 cycles in the reactor or the order of six years. Therefore, the fuel management has for object to design the configuration of fuel load and form of reactor operation, so that the safety aspects are satisfied and that the expectations of electric generation are reached for each operation cycle of the useful life of the reactor. (Author)

[en] The criticality state of the core of a boiling water reactor (BWR) was evaluated, during the reload process for the intermediate states between the load pattern of cycle end and the beginning of the next, using the information of the load pattern of the operation cycles 13 and 14 of Unit 1 of the nuclear power plant of Laguna Verde. For this evaluation the codes CASMO-4 and Simulate-3 for conditions of the core in cold were used. The strategy consisted on moving assemblies with 4 burned cycles of the reactor core. Later on were re situated the remaining assemblies, placing them in the positions to occupy in the next operation cycle. Finally, was carried out the assemblies load of fresh fuel. In each realized change, it was observing the behavior of the k-effective value that is the parameter used to evaluate the criticality state of each state of the core change. In a second stage, was designed a program that builds in automatic way each one of the intermediate cores and also analyzes the criticality state of the reactor core after each withdrawal, re situated and load of fuel assemblies. (Author)

[en] In this paper preliminary results are presented, obtained with the development of a computer system that resolves three stages of the nuclear fuel management, which are: the axial and radial designs of fuel, as well as the design of nuclear fuel reloads. The novelty of the system is that the solution is obtained solving the 3 mentioned stages, in coupled form. For this, heuristic techniques are used for each stage, in each one of these has a function objective that is applied to particular problems, but in all cases the obtained partial results are used as input data for the next stage. The heuristic techniques that were used to solve the coupled problem are: tabu search, neural networks and a hybrid between the scatter search and path re linking. The system applies an iterative process from the design of a fuel cell to the reload design, since are preliminary results the reload is designed using the operation strategy Haling type. In each one of the stages nuclear parameters inherent to the design are monitored. The results so far show the advantage of solving the problem in a coupled manner, even when a large amount of computer resources is used. (Author)