A Scoping Study of Fission Product Transport from Failed Fuel During N Reactor Postulated Accidents

A Scoping Study of Fission Product Transport from Failed Fuel During N Reactor Postulated Accidents PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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Book Description
This report presents a scoping study of cesium, iodine, and tellurium behavior during a cold leg manifold break in the N Reactor. More detail about fission product behavior than has previously been available is provided and key parameters that control this behavior are identified. The LACE LA1 test and evidence from the Power Burst Facility Severe Fuel Damage tests are used to test the key model applied to determine aerosol behavior. Recommendations for future analysis are also provided. The primary result is that most of the cesium, iodine, and tellurium remains in the molten uranium fuel. Only 0.0035 of the total inventory is calculated to be released. Condensation of the most of the species of cesium and iodine that are released is calculated, with 0.998 of the released cesium and iodine condensing in the spacers and upstream end of the connector tubes. Most of the tellurium that is released condenses, but the chemical reaction of tellurium vapor with surfaces is also a major factor in the behavior of this element.

Scoping Analysis of Fission Product Behavior and Transport in the Primary Coolant System for Postulated N Reactor Severe Accidents

Scoping Analysis of Fission Product Behavior and Transport in the Primary Coolant System for Postulated N Reactor Severe Accidents PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 151

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Fission Product Processes In Reactor Accidents

Fission Product Processes In Reactor Accidents PDF Author: J. T. Rogers
Publisher: CRC Press
ISBN: 1000107310
Category : Science
Languages : en
Pages : 883

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Book Description
The Three Mile Island and Chernobyl nuclear incidents emphasized the need for the world-wide nuclear community to cooperate further and exchange the results of research in this field in the most open and effective manner. Recognizing the roles of heat and mass transfer in all aspects of fission-product behavior in sever reactor accidents, the Executive Committee of the International Centre for Heat and Mass Transfer organized a Seminar on Fission Product Transport Processes in Reactor Accidents. This book contains the eleven of the lectures and all the papers presented at the seminar along with four invited papers that were not presented and a summary of the closing session.

Energy Research Abstracts

Energy Research Abstracts PDF Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 852

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A Scoping Study of Spent Fuel Cask Transportation Accidents

A Scoping Study of Spent Fuel Cask Transportation Accidents PDF Author: W. R. Rhyne
Publisher:
ISBN:
Category : Radioactive substances
Languages : en
Pages : 172

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Book Description
A scoping study of spent fuel cask transportation accidents was performed to provide the NRC with an assessment of existing information and to recommend, on a priority basis, the additional information that should be obtained to allow specification of increasingly realistic source terms. The scope was limited to the escape of radionuclides from the cask to the environment resulting from severe accidents. The accident environment definition associated with a severe accident is the starting point and was selected not for its realism but to allow sensitivity studies on the remaining variables in the accident scenario. However, given this accident definition, the remainder of the evaluation of the accident scenarios is to be as realistic as possible. Information was found to be inadequate to make correlations between accident severity and radionuclide release. Generally, cask and fuel rod thermal-hydraulic data and analytical capability were found to be reasonably adequate; however, data and analytical capability for evaluating structural response to impact are not. Radionuclide behavior information is adequate for noble gases but generally inadequate for most volatile radionuclides and for fuel particulates. A series of gauging calculations were performed to permit prioritization of the information needs, and research recommendations were made in eight areas.

International Symposium on Fission Product Release and Transport Under Accident Conditions

International Symposium on Fission Product Release and Transport Under Accident Conditions PDF Author:
Publisher:
ISBN:
Category : Fission products
Languages : en
Pages : 592

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A Study of Fission Product Transport Mechanisms in High Temperature Gas-cooled Reactor Fuel Elements

A Study of Fission Product Transport Mechanisms in High Temperature Gas-cooled Reactor Fuel Elements PDF Author: A. R. Saunders
Publisher:
ISBN:
Category : Fission products
Languages : en
Pages : 42

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Book Description


Fission Product Processes In Reactor Accidents

Fission Product Processes In Reactor Accidents PDF Author: J. T. Rogers
Publisher: CRC Press
ISBN: 9780891168768
Category : Science
Languages : en
Pages : 890

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Book Description
The Three Mile Island and Chernobyl nuclear incidents emphasized the need for the world-wide nuclear community to cooperate further and exchange the results of research in this field in the most open and effective manner. Recognizing the roles of heat and mass transfer in all aspects of fission-product behavior in sever reactor accidents, the Executive Committee of the International Centre for Heat and Mass Transfer organized a Seminar on Fission Product Transport Processes in Reactor Accidents. This book contains the eleven of the lectures and all the papers presented at the seminar along with four invited papers that were not presented and a summary of the closing session.

Fission Product Transport Analysis in a Loss of Decay Heat Removal Accident at Browns Ferry

Fission Product Transport Analysis in a Loss of Decay Heat Removal Accident at Browns Ferry PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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Book Description
This paper summarizes an analysis of the movement of noble gases, iodine, and cesium fission products within the Mark-I containment BWR reactor system represented by Browns Ferry Unit 1 during a postulated accident sequence initiated by a loss of decay heat removal (DHR) capability following a scram. The event analysis showed that this accident could be brought under control by various means, but the sequence with no operator action ultimately leads to containment (drywell) failure followed by loss of water from the reactor vessel, core degradation due to overheating, and reactor vessel failure with attendant movement of core debris onto the drywell floor.

Nuclear Safety in Light Water Reactors

Nuclear Safety in Light Water Reactors PDF Author: Bal Raj Sehgal
Publisher: Academic Press
ISBN: 0123884462
Category : Technology & Engineering
Languages : en
Pages : 732

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Book Description
La 4e de couverture indique : Organizes and presents all the latest thought on LWR nuclear safety in one consolidated volume, provided by the top experts in the field, ensuring high-quality, credible and easily accessible information.