NUCLEAR DATA FOR REACTOR NEUTRONICS CALCULATIONS - ROSFOND DATA LIBRARY AND ABBN-RF GROUP DATA SYSTEM

G. Manturov, M. Nikolaev, V. Koshcheev
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引用次数: 1

Abstract

The work is devoted to one of the most important scientific and technical problems in reactor physics related to the development and verification of codes and nuclear data that provide reliable and highly accurate calculations of neutron-physical characteristics of fast reactors and radiation shielding, including nuclear fuel cycle, criticality and radiation safety parameters. The designed neutronics characteristics of fast reactors should be based on certified, qualified sets of codes and nuclear constants: the calculation tools should be related to the modern state of scientific knowledge and computational techniques, and used nuclear physics constants should be adequate to the most reliable evaluations of nuclear data. In connection with rapid development of the computing engineering and all greater introduction in practice of calculation Monte Carlo codes, the methodical constituent of calculation error falls down substantially. In these terms the nuclear constant’s constituent of error of calculations becomes fully qualificatory. A situation is intensifyed by the fall-off of financing of experimental works, why in this connection the amount of fast critical stands in the world diminishes sharply. The paper consider the state of art of the constant’s providing system CONSYST/ABBN, created on the basis of the national library of neutron data files ROSFOND and libraries of multigroup constants ABBN-93 and ABBN-RF. One of the most important problems under consideration here also is the methodical and software for estimating of errors of the calculated physical characteristics. System of codes and nuclear data for reactor neutronics calculations is based on the unified methodological basis that ensures the transparency of the procedure for obtaining the data used in the calculations, the reliability of their verification and the obtaining of guaranteed accuracy of the calculated physical reactor characteristics.
反应堆中子计算用核数据。rosfond数据库和abbn-rf群数据系统
这项工作致力于研究反应堆物理学中最重要的科学和技术问题之一,涉及开发和核查提供可靠和高度精确计算快堆中子物理特性和辐射屏蔽的代码和核数据,包括核燃料循环、临界和辐射安全参数。设计快堆的中子特性应以经过认证的合格代码和核常数为基础;计算工具应与现代科学知识和计算技术有关,所使用的核物理常数应足以对核数据进行最可靠的评价。随着计算工程的迅速发展和蒙特卡罗编码在计算实践中的广泛应用,计算误差的方法成分大大降低。在这些条件下,核常数的计算误差的组成部分是完全限定的。由于实验工程资金的减少,这种情况更加严重,因此,世界上快速临界站的数量急剧减少。本文考虑了在国家中子数据库ROSFOND和多群常数库ABBN-93和ABBN- rf的基础上建立的常数提供系统CONSYST/ABBN的现状。这里考虑的最重要的问题之一是计算物理特性误差的方法和软件估计。反应堆中子计算的代码和核数据系统是建立在统一的方法基础上的,以确保获得计算中使用的数据的程序的透明性、验证的可靠性和获得计算的反应堆物理特性的有保证的准确性。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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