A generic method for automatic translation between input models for different versions of simulation codes

• Published in: Nuclear engineering and design Vol. 271; pp. 388 - 391
• Main Authors: Serfontein, Dawid E., Mulder, Eben J., Reitsma, Frederik
• Format: Journal Article
• Language: English
• Published: Elsevier B.V 01.05.2014
• Subjects: Algorithms; Automation; Computer simulation; Mathematical models; Nuclear engineering; Nuclear reactor components; Nuclear reactors; Translations
• ISSN: 0029-5493; 1872-759X
• DOI: 10.1016/j.nucengdes.2013.12.006

A computer code was developed for the semi-automatic translation of input models for the VSOP-A diffusion neutronics simulation code to the format of the newer VSOP 99/05 code. In this paper, this algorithm is presented as a generic method for producing codes for the automatic translation of input models from the format of one code version to another, or even to that of a completely different code. Normally, such translations are done manually. However, input model files, such as for the VSOP codes, often are very large and may consist of many thousands of numeric entries that make no particular sense to the human eye. Therefore the task, of for instance nuclear regulators, to verify the accuracy of such translated files can be very difficult and cumbersome. This may cause translation errors not to be picked up, which may have disastrous consequences later on when a reactor with such a faulty design is built. Therefore a generic algorithm for producing such automatic translation codes may ease the translation and verification process to a great extent. It will also remove human error from the process, which may significantly enhance the accuracy and reliability of the process. The developed algorithm also automatically creates a verification log file which permanently record the names and values of each variable used, as well as the list of meanings of all the possible values. This should greatly facilitate reactor licensing applications.