Author: Tony BakerPublisher:
ISBN:
Category : Nuclear fuel rods
Languages : en
Pages :
Book Description
Rod Control System Evaluation Program
Author: Tony BakerPublisher:
ISBN:
Category : Nuclear fuel rods
Languages : en
Pages :
Book Description
Systematic Evaluation Program
Author: Control Rod Theories Evaluation Based Upon Measurements of Control Rod Worths in SM-I-2 Reactor Assemblies
Author: J. W. ZwickPublisher:
ISBN:
Category : Nuclear fuel rods
Languages : en
Pages : 46
Book Description
Weekly Information Report
Author: Aging Assessment of the Westinghouse PWR Control Rod Drive System
Author: William GuntherPublisher:
ISBN:
Category : Nuclear fuel rods
Languages : en
Pages :
Book Description
Status Report on Control Rod Materials Research and Development Program
Author: W. C. BallowePublisher:
ISBN:
Category : Nuclear fuel rods
Languages : en
Pages : 144
Book Description
Off-center Control Rod Program (digital Computer Program K)
Author: C. L. MoorePublisher:
ISBN:
Category : Nuclear fuel rods
Languages : en
Pages : 138
Book Description
Evaluation of On-line Fuel and Control Rod Detection System at KKL During Cycles 25-26
Author: Irina LarssonAdvanced Test Reactor Servo Regulator Rod Test Program
Author: R. T. PickettPublisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 68
Book Description
Aging Mechanisms in the Westinghouse PWR (Pressurized Water Reactor) Control Rod Drive System
Author: Publisher:
ISBN:
Category :
Languages : en
Pages : 5
Book Description
An aging assessment of the Westinghouse Pressurized Water Reactor (PWR) Control Rod System (CRD) has been completed as part of the US NRC's Nuclear Plant Aging Research, (NPAR) Program. This study examined the design, construction, maintenance, and operation of the system to determine its potential for degradation as the plant ages. Selected results from this study are presented in this paper. The operating experience data were evaluated to identify the predominant failure modes, causes, and effects. From our evaluation of the data, coupled with an assessment of the materials of construction and the operating environment, we conclude that the Westinghouse CRD system is subject to degradation which, if unchecked, could affect its safety function as a plant ages. Ways to detect and mitigate the effects of aging are included in this paper. The current maintenance for the control rod drive system at fifteen Westinghouse PWRs was obtained through a survey conducted in cooperation with EPRI and NUMARC. The results of the survey indicate that some plants have modified the system, replaced components, or expanded preventive maintenance. Several of these activities have effectively addressed the aging issue. 2 refs., 2 figs., 2 tabs.