Development of shielding design analysis system

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JNC TJ9520 2001-002, 336 Pages, 2001/03

JNC-TJ9520-2001-002.pdf:7.28MB

The aim of this work is to develop insufficient auxiliary routines which manage input and output data and interface the main codes and to establish a shielding design analysis system on work stations (SUN, DEC). In shieldig design analyses, one- and two- dimensional (1-D and 2-D) transport Sn codes are used mainly with some auxiliary codes which generate input data of Sn calculation and edit Sn calculation outputs. The main transport calculation codes can be obtained from the Code Center of RIST (Research organization for Information Science & Technology). In this work. peripheral codes are developed to generate cross sections, produce Sn quadrature sets, edit calculation outputs or draw contour figures. In shielding calculations around a reactor, the boot-strapping technique is ofen employed to treat a large area extending from the core to the biological shield to improve the calculation accuracy. When a three-dimensional (3-D) calculation for a complex geometry with shielding defects, 2-D and 3-D coupling calculation is employed frequntly. To use this coupling method conversion codes are prepared which read flux file from DORT and prepare an external boundary source file for the 2-D or the 3-D calculation codes. For further conveniences well used data such as the Sn quadrature sets, the dose rate conversion factors, the reaction cross section sets are stored as a data base and code manuals including sample inputs of typical problems are prepared which are comprehensible to beginners.

Evaluation of the shielding design around the reactor core in the prototype FBR Monju

Shiraki, Takako*

Proceedings of 9th International Conference of Radiation Shielding (ICRS-9), 0 Pages, 1999/00

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Dai-9-Kai Hoshasen Shahei Kokusai Kaigi, , 

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