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JAEA Reports

Development of advanced nuclear core analysis system applicable to various reactor types (II)

Kaneko, Kunio*

JNC TJ9400 2003-003, 150 Pages, 2003/03

JNC-TJ9400-2003-003.pdf:5.69MB

A 900 group cross section library based on the specification determined last year was produced for 27 nuclei of the fast reactor benchmark problem evaluated in nuclear data file JENDL-3.2. In addition, the new SLAROM code, which has been developed as an advanced detail analysis system, was revised so as to make cell calculations effectively with the above 900 group library. Furthermore, new functions were added to the SLAROM so that the SLAROM evaluates assembly parameters using effective cross sections derived by the SLAROM and produces any condensed effective cross section set for core perfomance analysis. With the 900 group cross section library and the revised SLAROM, three cell calculations for fast and medium neutron speed reactors having different neutron spectrum were performed, and the results were compared with those calculated by the continuous energy Monte Carlo code MVP. By the comparisons, it is concluded that the newly revised SLAROM and a 900 group cross section library give accuracy comparable to MVP for predicting core perfomances.

JAEA Reports

Preparation of next generation set of group cross sections (III)

*

JNC TJ9400 2002-002, 80 Pages, 2002/03

JNC-TJ9400-2002-002.pdf:1.97MB

This fiscal year, based on the examination result about the evaluation energy range of heavy element unresolved resonance cross sections, the upper energy limit of the energy range, where ultra-fine group cross sections are produced, was raised to 50keV, and an improvement of the group cross section processing system was promoted. At the same time, reflecting the result of studies carried out till now, a function producing delayed neutron data was added to the general-purpose group cross section processing system, thus the preparation of general purpose group cross section processing system has been completed. On the other hand, the energy structure, data constitution and data contents of next generation group cross section set were determined, and the specification of a 151 groups next generation group cross section set was defined. Based on the above specification, a concrete library format of the next generation cross section set has been determined. After having carried out the above-described work, using the general-purpose group cross section processing system, which was complete in this study, with use of the JENDL-3.2 evaluated nuclear data, the 151 groups next generation group cross section of 92 nuclides and the ultra fine group resonance cross section library for 29 nuclides have been prepared. Utilizing the 151 groups next generation group cross section set and the ultra-fine group resonance cross-section library, a bench mark test calculation of fast reactors has been performed by using an advanced lattice calculation code. It was confirmed, by comparing the calculation result with a calculation result of continuous energy Monte Carlo code, that the 151 groups next generation cross section set has sufficient accuracy.

JAEA Reports

Development of advanced nuclear core analysis system applicable to various reactor types

*

JNC TJ9400 2002-001, 96 Pages, 2002/03

JNC-TJ9400-2002-001.pdf:2.8MB

This fiscal year, aiming at development of an advanced detailed analysis system applicable to nuclear core performance analysis of various fast reactors currently considered, the concept of cross section library set was examined and the specification of library set was determined. That is to say, referring the world most advanced reactor physics analysis system ERANOS (European Reactor Analysis optimized System) and the result of preceding research "preparation of next generation cross section library", 900 energy groups structure, concrete cross section data to be included and the format of cross section library were defined. And we performed elaborate work revising the group cross section production system which was prepared in the preceding research. After that the revision work was completed, to confirm the capability of revised cross section production system, we produced a prototype 450 groups cross section library. And we carried out a series of bench mark tests including analysis of small fast reactors utilizing this prototype cross section library and confirmed that the prototype cross section library has sufficient accuracy for predicting core perfomance. Furthermore, we estimated the computer resource infomation such as memory size, hard disk capacity and calculation time, etc. necessary for producing 900 groups detailed cross section library. In addition, we identified problems to be solved for developing a cell calculation code installed in our detailed analysis system.

JAEA Reports

Preparation of next generation set of group cross sections (II)

*

JNC TJ9400 2001-007, 138 Pages, 2001/03

JNC-TJ9400-2001-007.pdf:4.08MB

In FY2000, the general reactor group constant production system has been completed as below: TIMS-1; the code for preparing heavy element's resonance crosssection that is utilized in the JFS3 library production, was introduced and connected with the basic general reactor group constant production system which has been prepared last year, while consisting of a serial code PRENJOY, NJOY97, POSDTNJOY, and PDSMAKE and resulting whole system was adjusted so as to be utilized as the constant production system. With this introduction of TIMS-1 and the usage of the relevant general reactor group constant system, it becomes possible to produce a point-wise cross section of unresolved resonance energy region, which is necessary to the ultra fine group cross sections library for the PEACO module of new SLAROM code. On the other hand, while conversion of TIMS-1 to a UNIX machine program, TIMS-1 has been improved so as to make possible heavy nuclide resonance cross section processing with considerably simple input operation, with simplification of data input, and improvement of the method of evaluated nuclear data processing. In addition, we discussed the basic concept of next generation group constant set which should exhibit fully the high capability of the group constant and increase core performance analysis and be utilized in fields other than core analysis. Along with the knowledge obtained by ZPPR-13A core reaction rate analysis perfomed in the last year, the investigation of number of groups and group structure and proposition of a concrete group structure was done. Further supposing wider applications of the next generation group constant such as core safety analysis, core design and so on, other than core parameter analysis, the data structure and the concrete content of next generation group constant set were discussed

JAEA Reports

Preparation of next generation set of group cross sections; A Task report to the Japan Nuclear Cycle Development Institute)

*

JNC TJ9400 2000-005, 182 Pages, 2000/03

JNC-TJ9400-2000-005.pdf:4.74MB

The SLAROM code, performing fast reactor cell calculation based on a deterministic methodology, has been revised by adding the universal module PEACO of generating Ultra-fine group neutron spectra. The revised SLAROM, then, was utilized for evaluating reaction rate distributions in ZPPR-13A simulated by a 2-dim RZ homogeneous model, although actually ZPPR-13A composed of radial heterogereous cells. The reaction rate distributions of ZPPR-13A were also calculated by the code MVP, that is a continuous energy Monte Carlo calculation code based on a probabilistic methodology. By coparing both results, it was concluded that the module PEACO has excellent capability for evaluating highly accurate effective cross sections. Also it was proved that the use of a new fine group cross section library set (next generation set), reflecting behavior of cross sections of structural materials, such as Fe and O, in the fast neutron energy region, is indispensable for attaining a better agreement within 1% between both calculation methods. Also, for production of a next generation set of group cross sections, the code NJOY97.V107 was added to the group cross section production system and both front and end processing parts were prepared. This system was utilized to produce the new 70 group JFS-3 library using the evaluated nuclear data library JENDL-3.2. Furthermore, to confirm the capability of this new group cross section production system, the above new JFS-3 library was applied to core performance analysis of ZPPR-9 core with a 2-dim RZ homogeneous model and analysis of heterogeneous cells of ZPPR-9 core by using the deterministic method. Also the analysis using the code MVP was performed. Bycoaparison of both results the following conclusion has been derived; the deterministic method, with the PEACO module for resonance cross sections, contributes to improve accuracy of predicting reaction rate distributions and Na void reactivity in fast reactor cores. And it ...

JAEA Reports

Analysis of a basic core performance for FBR core nuclear design (III)

*

JNC TJ9400 99-005, 200 Pages, 1999/03

JNC-TJ9400-99-005.pdf:4.45MB

The spatial distribution of reaction rates in the ZPPR-13A, having an axially heterogeneous core, has been analysed. The ZPPR-13A core is treated as a 2-dimensional RZ configuration consisting of a homogenous core. The analysis is performed utilising both probabilistic and deterministic treatments. The probabilistic treatmnt is performed with the Monte Carlo Code MVP using of continuous energy variable. Comparing the results obtained both treatments and reviewing the calculation method of effective resonance cross sections, for deterministic treatment, utilised for the reaction rate distributions, it is revealed that the present treatment of effective resonance cross sections is not accurate, since that there are observed effects due to dependence on energy group number or energy group width, and on anisotropic scattering. To utilise miltiband method for calculating effective resonance cross sections, widely used by the european researchers, the computer code GROUPIE is installed and the performace of code is confirmed. Although, in order to improve effective resonance cross sections accuracy, the thermal neutron reactor standard code system SRAC-95 was improved last year by revising the ultra-fine group spectrum calculation module PEAC0, the module PEACO works specially under the restriction that number of nuclei having resonance cross section, in any zone, must be less than three, because collision probabilities are obtained by an interpolation method. This year, the module is improved so that these collision probabilities are directly calculated, and by this improvement highly accurate effective resonance cross sections under the energy of 40.868 keV can be calculated for whole geometrical configurations considered. To extend the application range of the module PEAC0, the cross sections of sodium and structure material nuclei are prepared so that they are also represented as ultra-fine group cross sections. By such modifications of cross section library, ...

JAEA Reports

Analysis of a basic core performance for FBR core nuclear design (II)

*

PNC TJ9660 98-001, 210 Pages, 1998/03

PNC-TJ9660-98-001.pdf:5.94MB

The core performance of ZPPR-10A was analyzed using the Monte Carlo treatment processing with continuous energy variable, which is based on a statistical principle completely different from various traditional deterministic neutron transport treatments. By inclusion of the continuous energy Monte Carlo code into our analysis system, a highly advanced analysis capability has been established for the JUPITER project. The above Monte Carlo method result was examined by comparison with the results of past deterministic analyses, and the difference between the Monte Carlo result and traditional deterministic results was confirmed as reasonable. In these years, the fast reactor concept is changing from the past concept, which make use of fuels composed of only Uranium -Plutonium. Aiming incineration of highly radioactive wastes or plutonium, various fast reactor cores are projected burning fuels blending actinide or minor actinide (MA). Fuels blending hydride are also considered, for efficient incineration of MA.. In these circumstances, the energy spectra of fast reactors are widely changing from a core to a core. For analyzing core performance of these concept, we need fast reactor group cross section set applicable to any spectrum, substituted for the usual set that was based on some standard spectrum. Two advanced group cross section production codes were installed and combined to our general comprehensive processing system for group cross section set. The installed codes are Red Cullen Codes, a group of codes for producing PENDF, and the newest version of NJOY which is recognized as having the most excellent group cross section processing capability. Utilizing these group cross section processing codes, the JFS3-70 group cross section set for Pu-238 and MN-55 were produced using the ENDF/B6. Through the production of set, we confirmed the excellent capability of these codes. Furthermore, the thermal neutron reactor standard code system SRAC-95, installed ...

JAEA Reports

Analysis of a basic core performance for FBR core nuclear design

*

PNC TJ9660 97-001, 166 Pages, 1997/03

PNC-TJ9660-97-001.pdf:4.19MB

An analysis of ZPPR-13A core was carried out usjng continuous energy Monte Carlo Code MVP based on a stochastic treatment that completely differs with a so-called deterministic treatment, aiming at an improvement of JUPITER analysis. By this improvement, differences between deterministic method results and continuous energy Monte Carlo method results were clearly understood. Problems, to be considered for performing JUPITER analysis by continuous energy Monte Carlo method, were made clear by this comparison. In addition, thermal reactor standard code system SRAC, that was recently released for users, was installed in a SUN work station to analyze new reactors of which neutron energy spectrum differs from that of fast reactors. The installation of SRAC is done to provide a new advanced analysis method for research demands related with various utilization of Fast reactors. Using SRAC code, we did an analysis of ZPPR-9 Doppler sample experiment and an analysis of the Minor actinide transmutation in a light water reactor. In the analysis of ZPPR-9 Doppler sample experiment, we could treat the effect of fine resonance structure on Doppler reactivity that was not considered in the previous analysis method. So was completed the preparation of the new analytical technique taking the mutual interference effect of resonance into consideration. From this doppler experiment analysis with the use of improved PEACO routine in the SRAC code, it was realized that if we use an increased upper energy bound of the ultra fine group treatment of PEACO, we will obtain better results for the Doppler reactivity evaluation with the SRAC code. We recommend that the upper energy bound in PEACO routine should be 150 keV because recent U-238 nuclear data evaluation has 150 keV unresolved resonance region upper energy. In the analysis of a Minor actinide transmutation in a light water reactor, we compared the performance of Minor actinide transmutation in a light water reactor with ...

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