Channel-type uranium-graphite reactor RBMK-1000.

نویسندگان

چکیده

برای دانلود باید عضویت طلایی داشته باشید

برای دانلود متن کامل این مقاله و بیش از 32 میلیون مقاله دیگر ابتدا ثبت نام کنید

اگر عضو سایت هستید لطفا وارد حساب کاربری خود شوید

منابع مشابه

Parameters Estimation in Modelling of Gas-Gap in RBMK Type Reactor Using Bayesian Approach

This study presents developed algorithm for assessment and updating estimates of parameters in the mathematical models of non-stationary processes (for instance, system ageing model, dynamic system models and so on) with respect of prior information and new obtained observations. Proposed algorithm for updating estimates of random parameters is based on modified application of Bayesian approach...

متن کامل

Determination of irradiated reactor uranium in soil samples in Belarus using 236U as irradiated uranium tracer.

This work presents experimental results on the distribution of irradiated reactor uranium from fallout after the accident at Chernobyl Nuclear Power Plant (NPP) in comparison to natural uranium distribution in different soil types. Oxidation processes and vertical migration of irradiated uranium in soils typical of the 30 km relocation area around Chernobyl NPP were studied using 236U as the tr...

متن کامل

Examination of reactor grade graphite using neutron powder diffraction

Graphite is of principal interest in Generation IV nuclear reactor concepts. In particular, graphite will be the moderator for the Very High Temperature Reactor. In support of experimental and computational investigations that aim at understanding the behavior of reactor grade graphite under operating conditions, neutron powder diffraction experiments have been performed at the North Carolina S...

متن کامل

Relap5-3d Code Validation for Rbmk Phenomena

.......................................................................................................................................................iii Summary ....................................................................................................................................................... v

متن کامل

Dynamic reliability and risk assessment of the accident localization system of the Ignalina NPP RBMK-1500 reactor

The paper presents reliability and risk analysis of the RBMK-1500 reactor accident localization system (ALS) (confinement), which prevents radioactive releases to the environment. Reliability of the system was estimated and compared by two methods: the conventional fault tree method and an innovative dynamic reliability model, based on stochastic differential equations. Frequency of radioactive...

متن کامل

ذخیره در منابع من


  با ذخیره ی این منبع در منابع من، دسترسی به آن را برای استفاده های بعدی آسان تر کنید

ژورنال

عنوان ژورنال: Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan

سال: 1986

ISSN: 0004-7120

DOI: 10.3327/jaesj.28.695