Development of finite-difference equations for variance of neutron fluxes in reactor

Laletin N.I.; Kovalishin A.A.

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Development of finite-difference equations for variance of neutron fluxes in reactor

机译：反应堆中子通量方差有限差分方程的建立

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摘要

Different sources-methodical, constant, and technological-are discussed for uncertainties in calculation functionals. The basic principles of three methods used in calculations of uncertainties are briefly described.

机译：对于计算功能的不确定性，讨论了不同的方法（方法，常量和技术）。简要介绍了用于不确定度计算的三种方法的基本原理。

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《Physics of atomic nuclei》 |2010年第13期|共10页
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Laletin N.I.; Kovalishin A.A.;
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正文语种 eng
中图分类原子物理学;
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1. Development of finite-difference equations for variance of neutron fluxes in reactor [J] . Laletin N.I., Kovalishin A.A. Physics of atomic nuclei . 2010,第13期

机译：反应堆中子通量方差有限差分方程的建立
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3. Determination of Neutron Fluxes and Spectrum Shaping Factors in Irradiation Sites of Ghana’S Miniature Neutron Source Reactor (mnsr) by Activation Method After Compensation of Loss of Excess Reactivty [J] . R.B.M. Sogbadji, B.J.B. Nyarko, E.H.K. Akaho, World Journal of Nuclear Science and Technology . 2011,第2期

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4. Monte Carlo Calculation of Core Reactivity and Fluxes for the Development of the BNCT Neutron Source at the Kyiv Research Reactor [C] . Olena Gritzay, Oleksandr Kalchenko, Nataliya Klimova, International Conference on Nuclear Data for Science and Technology . 2005

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机译：方差均值法在确定关键和次临界反应堆（反应堆噪声，费因曼-阿尔法）中子倍增参数中的应用。

Development of finite-difference equations for variance of neutron fluxes in reactor

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