RadChem 2014

Session

Chemistry of Nuclear Fuel Cycle 1

NFC-1

12 May 2014, 13:30

Casino Conference Centre

Conveners

Chemistry of Nuclear Fuel Cycle 1

• Christian Ekberg (Nuclear Chemistry, Chalmers)
• Václava Havlová (ÚJV Řež, a.s.)

Description

(1st ASGARD International Workshop)

21. Experiences of reprocessing plutonium rich mixed carbide fuels

Dr Natarajan Rajamani (Indira Gandhi Centre for Atomic Energy)

12/05/2014, 13:30

Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop

Invited

The mixed carbide (70% Pu, 30% U) spent fuel from the Fast Breeder Test Reactor (FBTR) at Kalpakkam, India is being reprocessed at the CORAL facility since 2003. Several campaigns with progressively increasing burnups and reducing cooling periods have been carried out in this facility. Presently spent fuels with a burn up of 155 GWd/Te with cooling periods as around two years are being...

162. Dissolution of carbide fuel materials

Mr Chris Maher (National Nuclear Laboratory)

12/05/2014, 14:00

Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop

Verbal

As part of the strategic research agenda for sustainable nuclear energy in Europe [1], carbide fuel is proposed as a potential candidate fuel for sodium cooled fast reactors and is the fuel of choice for gas cooled fast reactors. Carbide fuels have also been demonstrated to achieve high burn-up (> 155 GWd/t) in the sodium cooled Fast Reactor Fuel Reprocessing technology being pursued at the...

200. Dissolution of Mo-based CERMET fuel: ESI-TOF MS Speciation in nitric acid medium

Ms Elena Laura Ebert (Forschungszentrum Jülich GmbH IEK-6)

12/05/2014, 14:15

Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop

Verbal

The main long term contributors to spent fuel radiotoxicity are plutonium followed by the minor actinides (MA = Np, Am, and Cm). A possibility to reduce the radiotoxic inventory and the footprint of the repository is to separate the most radiotoxic and long-lived elements from spent fuel and to transmute them into nonradioactive elements or elements with a much shorter lifetime. For the...

241. Radionuclide distribution in corrosion layers of historic radioactive waste of NPP A1

Mr Boris Andris (VUJE a.s.)

12/05/2014, 14:30

Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop

Verbal

The radioactive waste management in Slovak Republic complies with the waste acceptance criteria for repository of Slovak Republic. The essential criterion is a declaration of radionuclides disposed in waste packages. The group of 19 limited radionuclides comprises various gamma, beta and alpha radionuclides. The activity of alpha radionuclides is monitored as a total alpha radioactivity, the...

174. Study on sorption and diffusion of Sr in crushed and intact basalt and granite investigated in column method

Prof. Ming-Chee Wu (Department of Earth Sciences, National Cheng Kung University, Tainan, Taiwan)

12/05/2014, 14:45

Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop

Verbal

This study investigates sorption and diffusion of Strontium (Sr) in two potential host rocks (granite from Kinmen Island and basalt from Penghu Island) by using batch and through-diffusion methods in order to establish a reliable safety assessment methodology. These methods were applied to crushed and intact rock samples to investigate the actual geological environment. According to...