Characterization of Thermal-hydraulic and Ignition Phenomena in Prototypic, Full-length Boiling Water Reactor Spent Fuel Pool Assemblies After a Postulated Complete Loss-of-coolant Accident PDF Download
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Author: Eric R. Lindgren
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 0
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Book Description
Author: Eric R. Lindgren
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 0
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Book Description
Author: U.s. Nuclear Regulatory Comion
Publisher: CreateSpace
ISBN: 9781499629842
Category : Science
Languages : en
Pages : 248
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Book Description
The NRC regulates the operation of the civilian nuclear power plant fleet by establishing and enforcing regulatory requirements for their design, construction, and operation. To protect the health and safety of the public and environment, the NRC requires all nuclear power plants to have a spent fuel pool where the used reactor fuel assemblies are allowed to cool for a number of years before being moved to interim or permanent storage. Spent fuel pools (SFP) are robust structures with an extremely low likelihood of a complete loss of coolant under traditional accident scenarios. However, in the wake of the terrorist attacks of September 11, 2001, the SFP accident progression was reconsidered and reevaluated using best-estimate accident codes.
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 244
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Book Description
The objective of this project was to provide basic thermal-hydraulic data associated with a SFP complete loss-of-coolant accident. The accident conditions of interest for the SFP were simulated in a full-scale prototypic fashion (electrically-heated, prototypic assemblies in a prototypic SFP rack) so that the experimental results closely represent actual fuel assembly responses. A major impetus for this work was to facilitate code validation (primarily MELCOR) and reduce questions associated with interpretation of the experimental results. It was necessary to simulate a cluster of assemblies to represent a higher decay (younger) assembly surrounded by older, lower power assemblies. Specifically, this program provided data and analysis confirming: (1) MELCOR modeling of inter-assembly radiant heat transfer, (2) flow resistance modeling and the natural convective flow induced in a fuel assembly as it heats up in air, (3) the potential for and nature of thermal transient (i.e., Zircaloy fire) propagation, and (4) mitigation strategies concerning fuel assembly management.
Author: National Academies of Sciences, Engineering, and Medicine
Publisher: National Academies Press
ISBN: 0309388880
Category : Political Science
Languages : en
Pages : 239
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Book Description
The U.S. Congress asked the National Academy of Sciences to conduct a technical study on lessons learned from the Fukushima Daiichi nuclear accident for improving safety and security of commercial nuclear power plants in the United States. This study was carried out in two phases: Phase 1, issued in 2014, focused on the causes of the Fukushima Daiichi accident and safety-related lessons learned for improving nuclear plant systems, operations, and regulations exclusive of spent fuel storage. This Phase 2 report focuses on three issues: (1) lessons learned from the accident for nuclear plant security, (2) lessons learned for spent fuel storage, and (3) reevaluation of conclusions from previous Academies studies on spent fuel storage.
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ISBN:
Category :
Languages : en
Pages :
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Book Description
Quick-look test results are reported for the initial test series of the Loss-of-Coolant Accident (LOCA) Simulation in the National Research Universal {NRU) test program, conducted by Pacific Northwest Laboratory (PNL) for the U.S. Nuclear Regulatory Commission (NRC). This test was devoted to evaluating the thermal-hydraulic characteristics of a full-length light water reactor (LWR) fuel bundle during the heatup, reflood, and quench phases of a LOCA. Experimental results from 28 tests cover reflood rates of 0.74 inches/sec to 11 inches/sec and delay times to initiate reflood of 3 sec to 66 sec. The results indicate that current analysis methods can predict peak temperatures within 10% and measured quench times for the bundle were significantly less than predicted. For reflood rates of 1 inches/sec where long quench times were predicted (>2000 sec}, measured quench times of 200 sec were found.
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 35
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Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
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Book Description
Author: C. L. Mohr
Publisher:
ISBN:
Category : Light water reactors
Languages : en
Pages : 332
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Book Description
Author: U.S. Nuclear Regulatory Commission
Publisher:
ISBN:
Category :
Languages : en
Pages :
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Author: International Atomic Energy Agency
Publisher: International Atomic Energy Agency
ISBN: 9789201019196
Category : Technology & Engineering
Languages : en
Pages : 74
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Book Description
There is considerable interest in both developing and developed countries in the design of innovative water cooled reactors (WCRs) and, owing to the higher thermal efficiency and significant system simplifications, supercritical water cooled reactors (SWCRs). Compared to conventional WCRs the SCWR concept requires extensive, comprehensive research and development (R&D). Fundamental research in understanding important phenomena has been completed successfully in providing information required for the next step of development. Currently, a few concepts have been assessed as being technical feasible, and several other concepts are under development. These concepts are described in this publication, together with detailed analysis of remaining gaps requiring future R&D.
