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Category :
Languages : en
Pages : 5
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Book Description
Consistent with the intent of this International Atomic Energy Agency technical meeting, decommissioning operating experience and contributions to the preparation for the Coordinated Research Project from Experimental Breeder Reactor-II activities will be discussed. This paper will review aspects of the decommissioning activities of the Experimental Breeder Reactor-II, make recommendations for future decommissioning activities and reactor system designs and discuss relevant areas of potential research and development. The Experimental Breeder Reactor-II (EBR-II) was designed as a 62.5 MWt, metal fueled, pool reactor with a conventional 19 MWe power plant. The productive life of the EBR-II began with first operations in 1964. Demonstration of the fast reactor fuel cycle, serving as an irradiation facility, demonstration of fast reactor passive safety and lastly, was well on its way to close the fast breeder fuel cycle for the second time when the Integral Fast Reactor program was prematurely ended in October 1994 with the shutdown of the EBR-II. The shutdown of the EBR-II was dictated without an associated planning phase that would have provided a smooth transition to shutdown. Argonne National Laboratory and the U.S. Department of Energy arrived at a logical plan and sequence for closure activities. The decommissioning activities as described herein fall into in three distinct phases.
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 5
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Book Description
Consistent with the intent of this International Atomic Energy Agency technical meeting, decommissioning operating experience and contributions to the preparation for the Coordinated Research Project from Experimental Breeder Reactor-II activities will be discussed. This paper will review aspects of the decommissioning activities of the Experimental Breeder Reactor-II, make recommendations for future decommissioning activities and reactor system designs and discuss relevant areas of potential research and development. The Experimental Breeder Reactor-II (EBR-II) was designed as a 62.5 MWt, metal fueled, pool reactor with a conventional 19 MWe power plant. The productive life of the EBR-II began with first operations in 1964. Demonstration of the fast reactor fuel cycle, serving as an irradiation facility, demonstration of fast reactor passive safety and lastly, was well on its way to close the fast breeder fuel cycle for the second time when the Integral Fast Reactor program was prematurely ended in October 1994 with the shutdown of the EBR-II. The shutdown of the EBR-II was dictated without an associated planning phase that would have provided a smooth transition to shutdown. Argonne National Laboratory and the U.S. Department of Energy arrived at a logical plan and sequence for closure activities. The decommissioning activities as described herein fall into in three distinct phases.
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Category : Business & Economics
Languages : en
Pages : 284
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Book Description
Operational experience constitutes an important aspect of any fast reactor knowledge base. It is within this context that the IAEA convened a Topical Technical Meeting on Feedback from Operational and Decommissioning Experience with Fast Reactors. This publication presents the proceedings of this meeting.
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Category : Performing arts
Languages : en
Pages :
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Book Description
Material in the Australian performing arts programs and ephemera (PROMPT) collection consists of programs and related items for Australian performing arts organisations, Australian artists performing overseas, professional productions performed in Australia (including those featuring overseas performers) and overseas performances of Australian plays, music, etc.
Author:
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Category :
Languages : en
Pages : 16
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Book Description
The Experimental Breeder Reactor-II (EBR-II) at Argonne National Laboratory-West (ANL-W) was shutdown in September, 1994. This sodium cooled reactor had been in service since 1964, and by the US Department of Energy (DOE) mandate, was to be placed in an industrially and radiologically safe condition for ultimate decommissioning. The deactivation of a liquid metal reactor presents unique concerns. The first major task associated with the project was the removal of all fueled assemblies. In addition, sodium must be drained from systems and processed for ultimate disposal. Residual quantities of sodium remaining in systems must be deactivated or inerted to preclude future hazards associated with pyrophoricity and generation of potentially explosive hydrogen gas. A Sodium Process Facility (SPF) was designed and constructed to react the elemental sodium from the EBR-II primary and secondary systems to sodium hydroxide for disposal. This facility has a design capacity to allow the reaction of the complete inventory of sodium at ANL-W in less than two years. Additional quantities of sodium from the Fermi-1 reactor are also being treated at the SPF.
Author: U.S. Atomic Energy Commission
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Category :
Languages : en
Pages :
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Author: Michele Laraia
Publisher: Springer
ISBN: 3319759167
Category : Technology & Engineering
Languages : en
Pages : 141
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Book Description
This book discusses the history of nuclear decommissioning as a science and industry. It explores the early, little-known period when the term “decommissioning” was not used in the nuclear context and the end-of-life operations of a nuclear facility were a low priority. It then describes the subsequent period when decommissioning was recognized as a separate phase of the nuclear lifecycle, before bringing readers up to date with today’s state of the art. The author addresses decommissioning as a mature industry in an era in which large, commercial nuclear reactors and other fuel-cycle installations have been fully dismantled, and their sites returned to other uses. The book also looks at the birth, growth and maturity of decommissioning, focusing on how new issues emerged, how these were gradually addressed, and the lessons learned from them. Further, it examines the technologies and management advances in science and industry that followed these solutions. Nuclear Decommissioning is a point of reference for industry researchers and decommissioning practitioners looking to enrich their knowledge of decommissioning in recent decades as well as the modern industry. The book is also of interest to historians and students who wish to learn more about the history of nuclear decommissioning.
Author: Peter B. Erickson
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 24
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Book Description
Review of the decommissioning of nuclear reactors which were licensed under CFR Part 50 of the Nuclear Regulatory Commission.
Author: Stanley H. Fistedis
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 91
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Book Description
Author:
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ISBN:
Category :
Languages : en
Pages :
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Book Description
This final report covers the Decontamination and Decommissioning (D and D) of the Experimental Breeder Reactor No. 1 (EBR-I) Complex funded under Contract No. AT(10-1)-1375. The major effort consisted of removal and processing of 5500 gallons of sodium/potassium (NaK) coolant from the EBR-I reactor system. Tests were performed to assess the explosive hazards of NaK and KO$sub 2$ in various environments and in contact with various contaminants likely to be encountered in the removal and processing operations. A NaK process plant was designed and constructed and the operation was successfully completed. Lesser effort was required for D and D of the Zero Power Reactor (ZPR-III) Facility, the Argonne Fast Source Reactor (AFSR) Shielding, and removal of contaminated NaK from the storage pit. The D and D effort was completed by 13 June 1975, ahead of schedule. (auth).
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Category :
Languages : en
Pages :
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Book Description
The Experimental Breeder Reactor No. 2 (EBR-II) has been modeled using a recently developed special purpose block oriented simulation language, the Dynamic Simulator for Nuclear Power Plants (DSNP). The purpose of the work was to develop and verify the code and use it to support the Operational Reliability Test Program at EBR-II. Designed to be set up directly from block diagrams of the reactor system, DSNP allows easy interchange of modules which simulate individual components of the plant with differing levels of complexity.
