[HTML][HTML] Effect of hydrogen gas and leaching solution on the fast release of fission products from two PWR fuels

T Mennecart, L Iglesias, M Herm, T König… - Journal of Nuclear …, 2024 - Elsevier
To study the dissolution of UOX spent nuclear fuel in a deep geological environment and the
fast release of a selection of relevant radionuclides for long-term safety of this high level …

[HTML][HTML] Fast release from clad and declad spent UOX PWR fuel segments in a bicarbonate solution under anoxic conditions

T Mennecart, C Cachoir, K Lemmens - Journal of Nuclear Materials, 2021 - Elsevier
For the safety assessment of Spent Nuclear Fuel (SNF) in disposal conditions, it is crucial to
determine the fast release of the potentially critical radionuclides (eg 129 I, 137 Cs, 99 Tc, 93 …

[图书][B] A non-destructive method to determine the neutron production rate of a sample of spent nuclear fuel under standard controlled area conditions

P Schillebeeckx, M Verwerft, G Žerovnik, Y Parthoens… - 2020 - ejp-eurad.eu
A method to determine the neutron production rate of a sample of spent nuclear fuel by
means of nondestructive analysis conducted under controlled-area conditions is described …

An absolute measurement of the neutron production rate of a spent nuclear fuel sample used for depletion code validation

P Schillebeeckx, M Verwerft, P Romojaro… - Frontiers in Energy …, 2023 - frontiersin.org
A method to determine the neutron production rate of a spent nuclear fuel segment sample
by means of non-destructive assay conducted under standard controlled-area conditions is …

Методы обращения с ОЯТ энергетических реакторов

СА Квятковский, ОА Мансуров, ПБ Птицын - 2021 - elibrary.ru
На основе анализа ретроспективы развития национальных ядерных энергетических
систем показаны основные мировые тенденции и изменение подхода к обращению с …

Projektová a bezpečnostní kritéria jaderného paliva

T Lucie - 2023 - dspace.cvut.cz
Splnění kritérií a požadavků kladených na jaderné palivo během provozu je nedílnou
součástí jaderné bezpečnosti. Provozní a bezpečnostní kritéria jaderného paliva jsou …

Effect of ionizing radiation on solvent extraction systems for the separation of minor actinides

B Verlinden - 2022 - lirias.kuleuven.be
Minor actinides and long living fission products, are largely responsible for the radiotoxicity
and heat production of spent nuclear fuel on the long term. During the last decades …

Development of a MOX equivalence Python code package for ANICCA

B Vermeeren, H Druenne - EPJ Nuclear Sciences & Technologies, 2021 - epjn.epj.org
The basis of the MOX (Mixed OXide) energy equivalence principle is keeping the in-core
fuel management characteristics (cycle length, feed size, etc.) of a nuclear reactor …

[PDF][PDF] Radiation resistant ionic liquids for the separation of minor actinides

P Zsabka - 2020 - lirias.kuleuven.be
The project foresees the synthesis of novel radiation-resistant hydrophobic ionic liquids to
be used for the extraction of minor actinides from acidic aqueous solutions. The importance …