Computer code system

Development of computer code system for analyzing the heat/mass balance, dynamic process simulation, supporting the component design works, etc. 

Tachimori, S. 1994. EXTRA-M A computing code system for analysis of the Purex process with mixer settlers for reprocessing. JAERI Report. JAERI1331. 

Noh, J-M., et al. (2008), Development of a Computer Code System for the Analysis of Prism and Pebble Type VHTR Cores , Ann. of Nucl. Energy, 35,1919-1928. 

Imai, K. et al., SPEEDI A computer code system for the real-time prediction of radiation dose to the public due to an accidental release. JAERI 1297, 1985. 

In this section we have tried to indicate the usefulness of sensitivity functions for the large number of applications. Considerable development is still required, however, before full benefit can be derived from perturbation theory methods for all these applications. Cross-section sensitivity studies, for example, will be more useful and reliable when cross-section error files supplement the cross-section files in present use. New computer code systems that can process these error files and perform sensitivity studies, allowing... 

Despite the significant progress made in perturbation theory since 1968, additional development is necessary before perturbation-based methods become reliable standard tools for the nuclear engineer. These developments can be grouped into four categories (1) resolution of fundamental questions, (2) development of formulations for new applications, (3) acquisition of practical experience on the range of applicability and relative merits of alternative perturbation theory formulations, and (4) development of computer code systems. 

Much work is still required before many of the perturbation theory formulations reviewed and presented here can be implemented in practice. If full benefit is to be drawn from perturbation theory techniques for a wide variety of problems concerned with the design, analysis, and optimization of nuclear systems, computer code systems of the future must include basic and specific modules for calculations based on perturbation theory formulations. The basic modules are intended for the calculation of different sensitivity functions. Specific modules should enable performanee of dilTerent studies sueh as cross-section sensitivity studies, analysis of alterations in the design or operating conditions of nuclear systems, and optimization studies. 

Basic computer codes such as one- and two-dimensional diffusion, S)f and Pi codes are being, revised to use toe JAERI-FAST >et. Codes for calculating a fine spec- trum and an ultra-fine spectrum in homogeneous media have been developed. Preparation of spectrum calculation codes for heterogeneous media is to progress. Development of a versatile computer code system is betog carried out to meet various requirements for reactor analysis. 

Y. NATTO et aL. MGCL-PROCE R A Computer Code System for Processing MultiOroup Constants Library MGCL, JAERl-M 9396, Japan Atomic Energy, Research Institute (1977). 

Development of the Computer Code System JACS for Criticality Safety, /. Katakura, Y. Naito, Y. KomurofJAERJ-Japan)... 

To satisfy the above requirements, a computer code system named JACS has been developed in Japan, in. which neutron transport calculations are performed with the Monte Carlo code KENO-IV (Ref. 1) and a modified KENO-IV code MULTI-KENO, S, codes ANISN-JR (Ref. 2) and DOT3.5 (Ref. 3), or the diffusion code FEDM (Ref. 4X with the finite element method. The Monte Carlo code is a powerful tool for criticality safety evaluation. For the Monte Carlo calculation, the KENO code was selected, for which the Hansen-Roach library is often used, and a simple PI approximation was applied to scattering. The number of energy groups in the Hansen-Roach library, e.g., 16, is too small to satisfy requirement 1 above, and is especially inadequate for calculation of thermal neutron behavior. A simple P.l approximation used in KENO-IV is also inadequate to satisfy requirement 3 above. Taking this into consideration, the cross-section library and treatment of scattering of KENO-IV were improved. 

Y. NAITO et al.. "MGCL-PROCESSOR A Computer Code System for Processing Multigroup Constants library MGCL, JAERI-M 9396, Japan Atomic Energy Research Institute (1981). 

A systein whose criticality should be diedced is often too complex to End directly applicable experimental measurements. In such a case, computer codes are used to evaluate the criticality safety. The codes rmd data used must be validated by many benchmark calculations. A computer code system named JACS (Ref. 1) has been developed at the Japan Atomic Energy Research Institute (JAE for evaluating nuclear oiticality safety, and more than 700 benclunark calculatiotis, as riiown in Table 1, wm carried out to validate it. Tte computed keff s of the calculations were widely S ead (0.90 to 1.03), and in some cases absolute values of keff woe far from 1.0. Hence, problems are submitted, one on how to improve tim calculation method and another on how to waluate tire criticality safety of a system from the result computed by the cpde. A study has been carried on to answer the latter problem. ... 

Mosf Commonly Used Computer Code Systems.714... 

KAERI has been developing computer code systems for graphite-moderated, helium-cooled VHTR. Fig. 13.10 shows the overall code system for VHTR licensing developed at KAERI. 

S. M. Ah, "An Updated Version of Computer Code CORA II for Estimation of Corrosion Product Mass and Activity Migration ia PWR Primary Circuits and Related Experimental Loops," Eourth International Conference on Water Chemistry of Nuclear Systems, Bournemouth, U.K., Oct. 1986, pp. 107-109. 

S. B. Watson md R. H. Rmney, Modfcations of the SEPHIS Computer Code for Calculating the Purex Solvent Extraction System, ORNL/TM-5123, Oak Ridge National Laboratory, Oak Ridge, Term., 1975. 

A spinoff from the UPC bar code is the European Article Numbering (EAN) bar code system. EAN numbers are based on the UPC bar code guidelines. For distribution outside North America, these bar codes are unique and different in the number of characters per code and the computer data base related to each code. 

The first stage toward producing an accurate estimate is to use a standard cost code for all construction projects. Table 9-45 shows a suitable numerical cost code, and Table 9-46 shows a typical alphabetical-numerical code. The cost-code system can be used throughout the estimating and construction stages for the collection of cost data by manual or computer methods. There are numerous types of fixed-capital-cost estimates, but in 1958 the American Association of Cost Engineers defined five types as follows ... 

Some of the features of GO (EPRI NP-3123) are given in Table 3.4.6-2. A GO model is networks GO operators to represent a system. It can be constructed from engineering drawings by replacing system elements (valves, switches, etc.) with one or more GO symbols. The GO computer code quantifies the GO model for system reliability, availability, identification of system fault sequences, and relative importance in rank of the constituent elements. 

The Seismic Safety Margins Research Program developed a computer code called SMACS (Seismic Methodology Analysis Chain with Statistics) for calculating the seismic responses of structures, systems, and components. This code links the seismic input as ensembles of acceleration time histories with the calculations of the soil-structure interactions, the responses of major structures, and the responses of subsystems. Since uses a multi-support approach to perform the time-history response calculations for piping subsystems, the correlations between component responses can be handled explicitly. SMACS is an example of the codes that are available for calculating seismic response for PSA purposes. 

This chapter overviews the techniques for incorporating external events into a PSA. The discussion was primarily aimed at nuclear power plants but is equally applicable to chemical process plants. The types of external events discussed were earthquakes, fires and floods. Notably absent were severe winds and tornados. Tornados are analyzed as missiles impacting the structures and causing common-cause failures of systems (EPRINP-768). Missile propagation and the resulting damage is a specialized subject usually solved with computer codes. 

FIRAC is a computer code designed to estimate radioactive and chemical source-terms as.sociaied with a fire and predict fire-induced flows and thermal and material transport within facilities, especially transport through a ventilation system. It includes a fire compartment module based on the FIRIN computer code, which calculates fuel mass loss rates and energy generation rates within the fire compartment. A second fire module, FIRAC2, based on the CFAST computer code, is in the code to model fire growth and smoke transport in multicompartment stmetures. 

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