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The 13th International Conference on Environmental ... - Events

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Abstracts<br />

shearing tools have been developed to cut the reactor internals. All of those equipments are hydraulically driven which is<br />

very suitable for submerged applicati<strong>on</strong>s. Mechanical cutting has a number of advantages compared to other cutting<br />

techniques. ? <str<strong>on</strong>g>The</str<strong>on</strong>g> technique produces almost no sec<strong>on</strong>dary waste. ? <str<strong>on</strong>g>The</str<strong>on</strong>g> visibility during cutting is very good because the<br />

cutting produces <strong>on</strong>ly a negligible amount of micro particles. ? Chips from the cutting process falls down to the bottom of<br />

the cutting pool and are easy to collect. ? No gases are produced that can cause airborne c<strong>on</strong>taminati<strong>on</strong>. ? <str<strong>on</strong>g>The</str<strong>on</strong>g> technique<br />

is safe and reliable. ? All reactor internal sizes, materials and thicknesses can be cut.<br />

Westinghouse experience in mechanical cutting has dem<strong>on</strong>strated that it is an excellent technique for segmentati<strong>on</strong><br />

of internals. Westinghouse c<strong>on</strong>tinues to develop new methods and products in order to further reduce the waste volume.<br />

In summary, the purpose of this paper will be to provide an overview of the Westinghouse mechanical segmentati<strong>on</strong><br />

process, based <strong>on</strong> actual experience from the work that has been completed to date.<br />

2) 40130 – EPRI Nuclear Power Plant Decommissi<strong>on</strong>ing Technology Program<br />

Karen Kim, Sean Bushart, Mike Naught<strong>on</strong>, Richard McGrath, Electrict Power Research Institute (USA)<br />

<str<strong>on</strong>g>The</str<strong>on</strong>g> Electric Power Research Institute (EPRI) is a n<strong>on</strong>-profit research organizati<strong>on</strong> that supports the energy industry.<br />

<str<strong>on</strong>g>The</str<strong>on</strong>g> Nuclear Power Plant Decommissi<strong>on</strong>ing Technology Program c<strong>on</strong>ducts research and develops technology for the safe<br />

and efficient decommissi<strong>on</strong>ing of nuclear power plants.<br />

Several USA nuclear power plants shut down and entered active decommissi<strong>on</strong>ing in the 1990s. At that time the<br />

decommissi<strong>on</strong>ing of a commercial nuclear power plant was a first of a kind evoluti<strong>on</strong>; nuclear power plant<br />

decommissi<strong>on</strong>ing is a combinati<strong>on</strong> of industrial decommissi<strong>on</strong>ing with the complexities of radioactive materials and<br />

waste management. <str<strong>on</strong>g>The</str<strong>on</strong>g> first plants to undergo this process encountered various challenges related to decommissi<strong>on</strong>ing<br />

planning and project management, removal of large radioactive comp<strong>on</strong>ents, radiati<strong>on</strong> protecti<strong>on</strong>, site remediati<strong>on</strong>, final<br />

status survey, and license terminati<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> USA regulatory framework for nuclear power plant decommissi<strong>on</strong>ing<br />

developed and evolved al<strong>on</strong>g with these first decommissi<strong>on</strong>ing projects. As of 2009 these nuclear power plants have<br />

successfully completed decommissi<strong>on</strong>ing activities and have achieved license terminati<strong>on</strong>. Two major c<strong>on</strong>tributors to the<br />

successful completi<strong>on</strong> of these projects were a) the development of technology specifically tailored to tasks unique to<br />

nuclear plant decommissi<strong>on</strong>ing and b) learning from each other’s experiences.<br />

<str<strong>on</strong>g>The</str<strong>on</strong>g> EPRI Nuclear Power Plant Decommissi<strong>on</strong>ing Technology Program c<strong>on</strong>ducts research and develops technology<br />

that addresses the range of decommissi<strong>on</strong>ing tasks from pre-planning, site characterizati<strong>on</strong>, removal of large comp<strong>on</strong>ents,<br />

site remediati<strong>on</strong>, to license terminati<strong>on</strong>. A key feature of the EPRI Program is the collecti<strong>on</strong> and transfer of less<strong>on</strong>s<br />

learned and experiences from the major decommissi<strong>on</strong>ing projects c<strong>on</strong>ducted to date. <str<strong>on</strong>g>The</str<strong>on</strong>g> EPRI Program c<strong>on</strong>ducts<br />

research and development based <strong>on</strong> the needs of its utility members; the EPRI Program membership c<strong>on</strong>sists of utilities<br />

from the USA, France, Spain, Sweden, Italy, Taiwan, and Japan. EPRI is the mechanism through which these<br />

internati<strong>on</strong>al utilities can c<strong>on</strong>duct collaborative research and development and learn from each other’s experiences and<br />

less<strong>on</strong>s learned. In additi<strong>on</strong> to collaborative research and development, the EPRI Program Team of decommissi<strong>on</strong>ing<br />

experts provides direct and site-specific support to its member utilities to facilitate knowledge transfer and<br />

decommissi<strong>on</strong>ing project optimizati<strong>on</strong>.<br />

This presentati<strong>on</strong> will provide informati<strong>on</strong> about the EPRI Nuclear Power Plant Decommissi<strong>on</strong>ing Technology<br />

Program and discuss USA and <str<strong>on</strong>g>Internati<strong>on</strong>al</str<strong>on</strong>g> Decommissi<strong>on</strong>ing experiences to date.<br />

3) 40253 – Tokai-1 Decommissi<strong>on</strong>ing Project<br />

Keizaburou Yoshino , JAPC (Japan)<br />

Tokai-1 is the oldest and historical commercial Magnox reactor in Japan, which had started commercial operati<strong>on</strong> in<br />

1966. <str<strong>on</strong>g>The</str<strong>on</strong>g> unit had helped introducti<strong>on</strong> and establishment of the c<strong>on</strong>structi<strong>on</strong> and operati<strong>on</strong> technologies regarding<br />

nuclear power plant at early stage in Japan by its c<strong>on</strong>structi<strong>on</strong> and operating experiences. However, <str<strong>on</strong>g>The</str<strong>on</strong>g> Japan Atomic<br />

Power Company (JAPC), the operator and owner of Tokai-1, decided to cease its operati<strong>on</strong> permanently because of a<br />

fulfillment of its missi<strong>on</strong> and ec<strong>on</strong>omical reas<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> unit was finally ceased in March 1998 after about 32 year operati<strong>on</strong>.<br />

It took about three years for removal of all spent fuels from the site, and then decommissi<strong>on</strong>ing started in 2001. JAPC,<br />

always <strong>on</strong> the forefr<strong>on</strong>t of the nati<strong>on</strong>’s nuclear power generati<strong>on</strong>, is now grappling Japan’s first decommissi<strong>on</strong>ing of a<br />

commercial nuclear power plant, striving to establish effective, advanced decommissi<strong>on</strong>ing. <str<strong>on</strong>g>The</str<strong>on</strong>g> decommissi<strong>on</strong>ing for<br />

Tokai-1 was scheduled as 20 years project. At the beginning, the reactor was started to be in a static c<strong>on</strong>diti<strong>on</strong> for ten<br />

years (“safe storage period”). While the reactor had been safely stored, the phased decommissi<strong>on</strong>ing works started from<br />

n<strong>on</strong>-radioactive or low radioactive equipments toward high radioactive equipments. First five years of the project, JAPC<br />

c<strong>on</strong>centrated to drain and clean spent fuel cartridge cooling p<strong>on</strong>d and to remove c<strong>on</strong>venti<strong>on</strong>al equipments such as turbine,<br />

feed water pump and fuel charge machine as planed and budgeted.<br />

From 2006, the project came into new phase. JAPC has been trying to remove four Steam Raising Units (SRUs).<br />

<str<strong>on</strong>g>The</str<strong>on</strong>g> SRUs are huge comp<strong>on</strong>ent (7t<strong>on</strong>, �6.3m, H24.7m) of the Gas Cooling Reactor (GCR) and inside of the SRUs are<br />

radioactively c<strong>on</strong>taminated. It is c<strong>on</strong>cerned that workers are required safety and minimizing c<strong>on</strong>taminati<strong>on</strong> areas during<br />

SRU removal. <str<strong>on</strong>g>The</str<strong>on</strong>g>refore, JAPC is developing and introducing Jack-down method and remote c<strong>on</strong>trol multi functi<strong>on</strong>al<br />

removal system. This method is the method by which to remove the SRUs in turn from the bottom by lifting the SRU by<br />

a large jack and cutting for removing SRU is d<strong>on</strong>e remotely with this system. <str<strong>on</strong>g>The</str<strong>on</strong>g> system enables cutting and holding not<br />

<strong>on</strong>ly SRU body but also internals. This technology and experiences would be useful for the reactor removal in the near<br />

future.<br />

46

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