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The 12th International Conference on Environmental ... - Events

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Abstracts Sessi<strong>on</strong> 55<br />

It is found that the basis for the differentiati<strong>on</strong> am<strong>on</strong>g the facility operators and owners should be the cost and the associated<br />

uncertainty. Thus, cost calculati<strong>on</strong> will have to be carried out by all. It should be based <strong>on</strong> available standards and guidance documents.<br />

It is found that this is a requirement that already exists elsewhere in the legislati<strong>on</strong>, and thus no additi<strong>on</strong>al burden is imposed<br />

<strong>on</strong> the companies.<br />

2) MARSAME: MULTI-AGENCY RADIATION SURVEY AND ASSESSMENT<br />

OF MATERIALS AND EQUIPMENT - 16181<br />

Kathryn Snead, Nidal Azzam, U.S. Envir<strong>on</strong>mental Protecti<strong>on</strong> Agency (USA);<br />

Colleen F. Petullo, U.S. Public Health Service (USA); Ramachandra Bhat, Craig Bias, U.S. Air Force (USA);<br />

David P. Alberth, Gerald Falo, U.S. Army, Aberdeen Proving Ground (USA);<br />

Steven Doremus, U.S. Navy, Yorktown (USA);<br />

W. Alexander Williams, Amanda Anders<strong>on</strong>, U.S. Department of Energy (USA);<br />

Robert A. Meck, George E. Powers, U.S. Nuclear Regulatory Commissi<strong>on</strong> (USA)<br />

<str<strong>on</strong>g>The</str<strong>on</strong>g> MARSAME manual is a technical resource that describes processes and methods for the measurement of radi<strong>on</strong>uclides in or<br />

<strong>on</strong> materials and equipment. <str<strong>on</strong>g>The</str<strong>on</strong>g>se methods and processes are used to make the decisi<strong>on</strong> that a radi<strong>on</strong>uclide is present and, if so, how<br />

to quantify the amount and its uncertainty. <str<strong>on</strong>g>The</str<strong>on</strong>g>y are also used to make the decisi<strong>on</strong> that no radi<strong>on</strong>uclide more than background is present.<br />

<str<strong>on</strong>g>The</str<strong>on</strong>g> MARSAME manual is technically defensible, and endorsed by the U.S. Department of Defense, the U.S. Department of Energy,<br />

the U.S. Envir<strong>on</strong>mental Protecti<strong>on</strong> Agency, and the U.S. Nuclear Regulatory Commissi<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> MARSAME manual was published<br />

in January 2009, and is available for download from the following website: http://www.epa.gov/rpdweb00/marssim/marsame.html.<br />

<str<strong>on</strong>g>The</str<strong>on</strong>g> MARSAME manual is a supplement to the MARSSIM manual, and closely follows the c<strong>on</strong>cepts and processes developed<br />

therein. <str<strong>on</strong>g>The</str<strong>on</strong>g> MARSSIM manual describes processes and methods for the measurement of radi<strong>on</strong>uclides <strong>on</strong> the surfaces of buildings<br />

and soils.<br />

3) DETERMINATION OF THE RADIONUCLIDE INVENTORY OF SAMPLES<br />

FROM A SPALLATION NEUTRON SOURCE - 16225<br />

Dorothea Schumann, Paul Scherrer Institute (Switzerland)<br />

<str<strong>on</strong>g>The</str<strong>on</strong>g> Paul Scherrer Institute (PSI) in Villigen (Switzerland) operates the most powerful spallati<strong>on</strong> neutr<strong>on</strong> source (SINQ) in<br />

Europe and also world-wide. A 590-MeV-ringcyclotr<strong>on</strong> accelerates prot<strong>on</strong>s with a beam current of 2 mA which hit a solid lead target.<br />

An upgrate of the accelerator complex to 3.5 mA is foreseen in the near future.<br />

In such huge accelerator facilities, the safe operati<strong>on</strong> as well as the handling of the nuclear waste in the case of dismantling,<br />

decommissi<strong>on</strong>ing and/or disposal of activated comp<strong>on</strong>ents requires reliable data <strong>on</strong> the radi<strong>on</strong>uclide inventory.<br />

<str<strong>on</strong>g>The</str<strong>on</strong>g> spallati<strong>on</strong> neutr<strong>on</strong> source SINQ represents in this c<strong>on</strong>text a special issue, because the lead target serves in principle as a<br />

big “beam dump”, which means that the beam particles are completely stopped and the entire energy deposit has to be expected in<br />

the target body and the surrounding envir<strong>on</strong>ment. Accurate determinati<strong>on</strong> of the activati<strong>on</strong> in this area is therefore of essential<br />

importance.<br />

We report here <strong>on</strong> the radiochemical analysis of three comp<strong>on</strong>ential parts of the SINQ target setup and envir<strong>on</strong>ment. <str<strong>on</strong>g>The</str<strong>on</strong>g> materials<br />

are zircaloy, stainless steel and AlMg3 . 20 radi<strong>on</strong>uclides were determined by gamma-spectrometry, Liquid Scintillati<strong>on</strong> Counting<br />

(LSC) technique as well as Accelerator Mass Spectrometry (AMS). Some of these isotopes can <strong>on</strong>ly be measured after a complex<br />

chemical separati<strong>on</strong> procedure. <str<strong>on</strong>g>The</str<strong>on</strong>g> results are compared with the declarati<strong>on</strong> limits and the activity limits for decommissi<strong>on</strong>ing.<br />

It is shown that all determined radi<strong>on</strong>uclides have to be declared, but no problems have to be expected for decommissi<strong>on</strong>ing<br />

and disposal.<br />

4) MEASUREMENT OF RADIOACTIVE AEROSOL BEHAVIOR DURING DISMANTLING<br />

AND REFLECTION TO THE EXPOSURE DOSE EVALUATION - 16107<br />

Yukihiro Iguchi, Masami Kato, Japan Nuclear Energy Safety Organizati<strong>on</strong> (Japan)<br />

Radioactive aerosol disperses slightly via c<strong>on</strong>taminati<strong>on</strong> preventi<strong>on</strong> systems such as c<strong>on</strong>trol enclosures and filters when the<br />

nuclear installati<strong>on</strong> is dismantled, and it might impact the envir<strong>on</strong>ment. <str<strong>on</strong>g>The</str<strong>on</strong>g>refore, when decommissi<strong>on</strong>ing is planned, it is necessary<br />

to assess the safety such as exposure dose evaluati<strong>on</strong> to the public. For the radioactive aerosol, it is possible that the dispersi<strong>on</strong><br />

ratio is different according to the c<strong>on</strong>taminati<strong>on</strong> c<strong>on</strong>diti<strong>on</strong>, the dismantlement method of the material, nuclides (elements), etc.<br />

<str<strong>on</strong>g>The</str<strong>on</strong>g> radiati<strong>on</strong> exposure evaluati<strong>on</strong> for the decommissi<strong>on</strong>ing plan has been executed by operators in Japan based <strong>on</strong> a number<br />

of experiments (mostly cold tests) and overseas results.<br />

<str<strong>on</strong>g>The</str<strong>on</strong>g> decommissi<strong>on</strong>ing is now being carried out at the Tokai Power Stati<strong>on</strong> (GCR) and Fugen Decommissi<strong>on</strong>ing Engineering<br />

Center in Japan. In this study, the results data is acquired at the decommissi<strong>on</strong>ing sites, and the methodology and data for the exposure<br />

dose evaluati<strong>on</strong> are verified and c<strong>on</strong>firmed. <str<strong>on</strong>g>The</str<strong>on</strong>g>se examinati<strong>on</strong> results will lead to the upgrading and improvement of the exposure<br />

evaluati<strong>on</strong> methodology.<br />

5) IAEA DECOMMISSIONING SAFETY ACTIVITIES - 16397<br />

Vladan Ljubenov, Ernst Warnecke, Mark Hannan, <str<strong>on</strong>g>Internati<strong>on</strong>al</str<strong>on</strong>g> Atomic Energy Agency (Austria)<br />

This paper presents a summary of the recent, <strong>on</strong>going and planned safety related IAEA activities <strong>on</strong> planning, implementati<strong>on</strong><br />

and terminati<strong>on</strong> of decommissi<strong>on</strong>ing. Work related to the Joint C<strong>on</strong>venti<strong>on</strong> <strong>on</strong> the Safety of Spent Fuel Management and <strong>on</strong> the<br />

Safety of Radioactive Waste Managementand to the development of the internati<strong>on</strong>al safety standards for decommissi<strong>on</strong>ing of facilities<br />

using radioactive materials is described. <str<strong>on</strong>g>The</str<strong>on</strong>g> IAEA activities <strong>on</strong> the technical assistance to the Member States in the development<br />

and review of decommissi<strong>on</strong>ing plans through nati<strong>on</strong>al and internati<strong>on</strong>al Technical Cooperati<strong>on</strong> Programme projects and<br />

through other projects (FaSa project, R2D2P Project, decommissi<strong>on</strong>ing of the Iraq former nuclear complex) are presented. Recently<br />

established IAEA peer review services <strong>on</strong> decommissi<strong>on</strong>ing are addressed, as well as the internati<strong>on</strong>al decommissi<strong>on</strong>ing forum.<br />

127

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