RadChem 2018

Session

NFC 6

NFC.6

18 May 2018, 13:30

Casino Conference Centre

Conveners

NFC 6

• Katja Schmeide (Helmholtz-Zentrum Dresden-Rossendorf, Institute of Resource Ecology)
• Vaclava Havlova (UJV Rez, a.s.)

479. Radiochemical characterisation for a decommissioning purpose at NRG: The case of ion exchange resins

Mr Patrick Haaß (Nuclear Research and consultancy Group)

18/05/2018, 13:30

Chemistry of Nuclear Fuel Cycle, Radiochemical Problems in Nuclear Waste Management

Verbal

The High Flux Reactor in Petten, Netherlands, is used for the production of medical isotopes as well as a material research reactor; during its exploitation several types of radioactive wastes are produced and accumulated.

That is the case in particular for the Ion Exchange Resins (IER) in use to treat the water of the primary water circuit of the reactor and the demineralizing basin....

652. Carbon-14 release from irradiated stainless steel

Mrs Eva De Visser-Týnová (Nuclear Research and consultancy Group (NRG))

18/05/2018, 13:45

Chemistry of Nuclear Fuel Cycle, Radiochemical Problems in Nuclear Waste Management

Verbal

Carbon-14 (half-life 5,730 years) is a key radionuclide in the assessment of the safety of a geological disposal facility (GDF) for radioactive waste. In particular, the radiological impact of gaseous carbon-14 bearing species has been recognised as a potential issue. Carbon 14 is expected to be released from a GDF over a timescale of several thousand years. A number of radioactive gases will...

611. Assessment of the release behavior of 14C from irradiated nuclear graphite from a German Research Reactor

Dr Natalia Shcherbina (Forschungszentrum Jülich GmbH, Institute for Energy and Climate Research, Nuclear Waste Management and Reactor Safety (IEK-6))

18/05/2018, 14:00

Chemistry of Nuclear Fuel Cycle, Radiochemical Problems in Nuclear Waste Management

Verbal

Irradiated graphite (i-graphite) is a typical nuclear waste arising from the decommissioning of some nuclear power plants and research reactors. According to the current nuclear waste management strategy in Germany, i-graphite discharged from commercial and research reactors is to be disposed of in a deep geological repository for low and intermediate level radioactive wastes, which requires...

601. Radiochemical analysis of biological shielding of VVER-440 reactor for deep geological repository

Mr Radek Pošvař

18/05/2018, 14:15

Chemistry of Nuclear Fuel Cycle, Radiochemical Problems in Nuclear Waste Management

Verbal

The decommissioning of nuclear facilities is connected with a huge amount of radioactive waste. The biological shielding of reactor vessel is an example of very heavy and voluminous part of NPP decommissioning waste. It is mainly composed of concrete which is long term exposed to gamma and neutron radiation.
ÚJV Řež a. s. owns one concrete block of biological shielding from NPP Greifswald's...

511. "Dry” decontamination by films and pastes

Dr Nadzeya Varonik (Joint Institute for Power and Nuclear Research – Sosny of the National Academy of Sciences of Belarus)

18/05/2018, 14:30

Chemistry of Nuclear Fuel Cycle, Radiochemical Problems in Nuclear Waste Management

Verbal

This study was aimed to development and application of polymer composite formulations for “dry” decontamination of the spent nuclear fuel storage of mobile NPP “PAMIR” with gas-cooled nuclear reactor using heat carrier N${}_2$O${}_4$.
Polymer composite formulations for “dry” decontamination and their operation characteristics (decontamination efficiency, consumption rate), and at evaluating...