نتایج جستجو برای: reactor safety

تعداد نتایج: 290794  

2011
William Kerr

Reactor control and safety systems are discussed with emphasis on safety considerations. Consideration is given to the importance of reactor characteristics, control and safety system characteristics, the operational program of the reactor, and credible accidents, in a determination of safety of operation. Ecperience with research reactor control and safety systems has led to the development of...

2001
Charles S. Hinson James D. Noggle

The objective of the revised Reactor Oversight Process is to monitor licensee performance in the areas of reactor safety, radiation safety, and security. This paper describes the NRC’s revised Reactor Oversight Process and how it is used to assess licensee performance against stated objectives in seven areas (or cornerstones) of plant operations. One of the seven cornerstones of the Reactor Ove...

ژورنال: سنجش و ایمنی پرتو 2016

Tehran Research Reactor (TRR) is in a residential area. Some other characteristics such as aged, relatively full time operation and also being the only available reactor for producing some radioisotopes, are the reasons for special attention to this reactor safety. Recently, a Second Shutdown System (SSS) has been designed for this reactor, which is completely independent and diverse from First...

Journal: :Aerosol Science and Technology 1982

Journal: :Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan 1964

2013
N. Ha Hoang Denis Dochain Thuong Kiet

The paper deals with nonlinear control under input constraints of a non isothermal Continuous Stirred Tank Reactor (CSTR) using thermodynamic concepts. More precisely, the paper presents an extension of the previous work (Hoang et al. (2012)) where the jacket temperature is used as the only control input. Constrained input control strategy is based on the observation that the chemical reactor o...

Journal: :iranian journal of science and technology transactions of mechanical engineering 2015
a. hussain f. abolaban s. m. khubaib s. mubin i. ahmed

nuclear cross sections that determine core multiplication strongly depend on core temperature (e.g., the doppler, moderator density effects etc). on the other hand, since this heat is generated by the neutron flux in the reactor core, the temperature distribution in the core will depend heavily on its neutronic behavior. fuel centerline temperature could be the limiting constraint on reactor po...

An accurate description of the fluid flow and heat transfer within a Pressurized Water Reactor (PWR), for the safety analysis and reactor performance is always desirable. In this paper a mathematical model of the fundamental physical phenomena which are associated to a typical PWR is presented. The mathematical model governs the fluid dynamics in the reactor. Using commercial software CFX, a co...

2013
W. D. Pointer K. Bradley P. Fischer M. Smith T. Tautges R. Ferencz R. Martineau R. Jain A. Obabko J. Billings

This paper provides an introduction to the reactor analysis capabilities of the nuclear power reactor simulation tools that are being developed as part of the U.S. Department of Energy’s Nuclear Energy Advanced Modeling and Simulation (NEAMS) Toolkit. The NEAMS Toolkit is an integrated suite of multi-physics simulation tools which leverage high-performance computing to reduce uncertainty in the...

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