Author: Clinton Eugene GrossPublisher:
ISBN:
Category :
Languages : en
Pages : 49
Book Description
Determination of Moderator Temperature Coefficient in a Pressurized Water Reactor Using Neutron and Temperature Noise Analysis
Author: Clinton Eugene GrossValidation of Noise Analysis Techniques for Evaluating the Moderator Temperature Coefficient in Pressurized Water Reactors
Author: Nikhil VenkateshPublisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 186
Book Description
Development of a Noise-based Method for the Determination of the Moderator Temperature Coefficient of Reactivity (MTC) in Pressurized Water Reactors (PWRs)
Author: Chalmers tekniska högskolaPublisher:
ISBN: 9789172912243
Category :
Languages : en
Pages : 72
Book Description
Energy Research Abstracts
Author: American National Standard Calculation and Measurement of the Modular Temperature Coefficient of Reactivity for Water Moderated Power Reactors
Author: American National Standards InstitutePublisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 32
Book Description
American National Standard
Author: American Nuclear Society. Standards Committee Working Group ANS-19.11Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages :
Book Description
This standard provides guidance and specifies criteria for determining the MTC in PWRs. Measurement of the isothermal temperature coefficient of reactivity (ITC) at hot-zero-power (HZP) conditions is covered in ANSI/ANS-19.6.1-2011 (R2016). This standard therefore addresses the calculation of the ITC at HZP and the calculation and measurement of the MTC at power. This standard addresses the calculation and measurement of the MTC only in PWRs because that is the only type of power reactor currently sited in the United States for which measurement of the MTC is required.
Analysis of In-core Dynamics in Pressurized Water Reactors with Application to Parameter Monitoring
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The behavior of the phase relationship between neutron flux and core-exit temperature fluctuations in a pressurized water reactor (PWR) is studied as a function of the moderator temperature coefficient of reactivity (.cap alpha./sub c/). PWR operational data indicate that the neutron noise and core-exit temperature noise cross power spectrum phase is linear in a certain frequency range, and approaches -180 deg at low frequencies. Extensive modeling studies applied to the LOFT reactor show that this low frequency phase behavior changes when .cap alpha./sub c/ is positive, approaching zero deg at low frequencies. The analysis further showed that in the LOFT reactor, coolant flow rate fluctuation is the primary driving source causing neutron noise and core-exit temperature fluctuations. This conclusion was also confirmed by independent studies. The neutron noise-coolant temperature phase behavior may be used as a single method of monitoring the moderator temperature coefficient of reactivity during different stages of a PWR fuel cycle.
Nuclear Science Abstracts
Author: ERDA Energy Research Abstracts
Author: Thermal Analysis of Pressurized Water Reactors
Author: Long-sun TongPublisher:
ISBN:
Category : Science
Languages : en
Pages : 328
Book Description