Work Structure in Nuclear Power Plants

1983 ◽  
Vol 27 (7) ◽  
pp. 571-575 ◽  
Author(s):  
Marjorie B. Bauman ◽  
Richard F. Pain ◽  
Harold P. Van Cott ◽  
Margery K. Davidson
Keyword(s):  
Critical Incident ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Primary Source ◽  
Structure Factors ◽  
Research Themes ◽  
Plant Personnel ◽  
And Performance ◽  
Work Structure

This paper describes the assessment of the work structure of ten nuclear power plants. Work structure factors are those factors that relate to the way in which work at all levels in a plant is organized, staffed, managed, rewarded, and perceived by plant personnel. Questionnaires given to a cross-section of personnel at the plants were the primary source of data collection. Structured “critical incident” interviews were conducted to verify the questionnaire results. The study revealed that a variety of work structure factor problem areas do exist in nuclear power plants. The paper highlights a prioritized set of candidate research themes to be considered in EPRI's Work Structure and Performance Research Program.

Work structure in nuclear power plants

1983 ◽  
Author(s):  
Marjorie B. Bauman ◽  
Richard F. Pain ◽  
Harold P. Van Cott ◽  
Margery K. Davidson
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Work Structure

scholarly journals A REVIEW ON USAGE OF NANO-PARTICLES IN NUCLEAR POWER PLANTS

2017 ◽  
Vol 5 (2) ◽  
pp. 233-236
Author(s):  
Din Bandhu ◽  
Ritesh Kumar
Keyword(s):  
Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Review Paper ◽  
Nano Particles ◽  
Construction Experience ◽  
And Performance ◽  
Materials Used ◽  
Effects Of Radiation

Nuclear power plants are big in construction and possess complex facilities. These plants usually operate at very large temperatures and the materials used in their construction experience considerably higher levels of radiation. It is therefore very important to understand the effects of radiation on these materials. Radiation is responsible for defects which affects the strength and performance of the materials. In this review paper, we have suggested one idea for constructing an efficient nuclear power plant by using nano-particles. This paper also details about nano-particles in an elaborated way and a few of them can be used for constructing nuclear power plants (NPP).

scholarly journals Fire Safety in Nuclear Power Plants: A Risk-Informed and Performance-Based Approach

1999 ◽  
Author(s):  
Mohamed A. Azarm ◽  
Richard J. Travis
Keyword(s):  
Case Studies ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Fire Risk ◽  
Policy And Practice ◽  
Fire Risk Analysis ◽  
Regulatory Decision ◽  
Near Term ◽  
And Performance

Abstract The consideration of risk in regulatory decision-making has long been a part of NRC’s policy and practice. Initially, these considerations were qualitative and were based on risk insights. The early regulations relied on good practices, past insights, and accepted standards. As a result, most NRC regulations were prescriptive and were applied uniformly to all areas within the regulatory scope. Risk technology is changing regulations by prioritizing the areas within regulatory scope based on risk, thereby focusing on the risk-important areas. Performance technology, on the other hand, is changing the regulations by allowing requirements to be adjusted based on the specific performance expected and manifested, rather than a prior prescriptive requirement. Consistent with the objectives of risk-informed and performance-based regulatory requirements, BNL evaluated the feasibility of applying risk- and performance-technologies to modifying NRC’s current regulations on fire protection for nuclear power plants.(1) This feasibility study entailed several case studies (trial applications). This paper describes the results of two of them. Besides the case studies, the paper discusses an overall evaluation of methodologies for fire-risk analysis to support the risk-informed regulation. It identifies some current shortcomings and proposes some near-term solutions.

Beyond Design Basis Seismic Analysis for Atucha II Nuclear Plant

2012 ◽  
Author(s):  
Tao Zhang ◽  
Frederick W. Brust ◽  
Gery Wilkowski ◽  
Heqin Xu ◽  
Alfredo A. Betervide ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Seismic Event ◽  
Seismic Analysis ◽  
Cooling System ◽  
Safety Margin ◽  
Design Basis ◽  
Heavy Water Reactor ◽  
And Performance

The Atucha II nuclear power plant is a pressurized heavy water reactor being constructed in Argentina. Nuclear power plants must be designed to maintain their integrity and performance of safety functions for a bounding set of normal operational events as well as abnormal events that might occur during the lifetime of the plant. Seismic fracture mechanics evaluations for the Atucha II plant showed that even with a seismic event with the amplitudes corresponding to an event with a probability of 10−6 per year, that a double-ended guillotine break (DEGB) was pragmatically impossible due to the incredibly high leakage rates and total loss of make-up water inventory. The critical circumferential through-wall flaw size for this case is 94-percent of the circumference. These analyses are performed by placing cracked-pipe-elements into a complete model of the primary cooling system including the reactor pressure vessel, pumps, and steam generators as summarized in the paper. This paper summarizes these results and further shows how much higher the applied accelerations would have to be to cause a DEGB for an initial circumferential through-wall crack that was 33 percent (about 120°) around the circumference. This flaw length would also be easily detected by leakage and loss of make-up water inventory. These analyses showed that the applied seismic peak-ground accelerations had to exceed 25 g’s for the case of this through-wall-crack to become a DEGB during a single seismic loading event. This is a factor of 80 times higher than the 10−6 seismic event accelerations, or 240 times higher than the SSE accelerations. This suggests there is a huge safety margin for beyond design basis seismic events and Atucha II plant rupture is pragmatically impossible. These surprising results are discussed and could be potentially applicable to other nuclear power plants as well.

The Problems of Nuclear Power are Much Too Serious to Leave to Nuclear Experts

1998 ◽  
Vol 42 (10) ◽  
pp. 737-739 ◽  
Author(s):  
Vladimir Munipov
Keyword(s):  
Operating Procedure ◽  
Chernobyl Accident ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Protection System ◽  
Root Cause ◽  
Nuclear Age ◽  
Plant Personnel ◽  
Machine Interaction

The full story of the Chernobyl disaster is yet to be disclosed. The initial cause of the accident was a very unlikely violation of the operating procedure and conditions by the plant personnel which showed the design faults of the reactor and the control and protection system rods. The main or root cause of the accident was the inadequate design of the user-machine interaction. Many people involved with the reliability and safety of Nuclear Power Plants now believe that even if the operators had acted correctly their actions would have resulted in the explosion. The main lesson from the Chernobyl accident is that the Nuclear Age calls for a new culture and and can certainly not tolerate ignorance. Chernobyl is a severe warning of what can happen if people disregard the necessity of including ergonomics in the process of designing and operating complex technical facilities.

scholarly journals Survey and analysis of work structure in nuclear power plants. Final report

1983 ◽  
Author(s):  
M. Bauman ◽  
R. Pain ◽  
H. Van Cott ◽  
M. Davidson
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Final Report ◽  
Work Structure

A Comparison of Displays and Associated Workload on Nuclear Power Plants Tasks

2016 ◽  
Vol 60 (1) ◽  
pp. 1686-1690 ◽  
Author(s):  
Lauren Reinerman-Jones ◽  
Niav Hughes ◽  
Amy D’Agostino
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Performance Measures ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Control Room ◽  
Experimental Environment ◽  
And Performance ◽  
Task Types

Nuclear Power Plant (NPP) operators complete a variety of tasks to ensure the NPP is running safely and efficiently. However, the levels and types of workload associated with the different task types are not yet fully understood. The present investigation examined workload levels and types for three common NPP Main Control Room (MCR) tasks in a controlled experimental environment using a variety of subjective and performance measures of workload. The results suggest that the three task types differ in the levels and types of workload. These findings can be used to better understand the types of NPP tasks that induce workload and the type of workload they induce. The full results of these experiments will be captured in future articles and technical reports.

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