Download full-text PDF |
Source |
---|---|
http://dx.doi.org/10.1103/physrevb.53.15617 | DOI Listing |
Phys Chem Chem Phys
January 2025
Department of Physics, Indian Institute of Technology (IIT) Delhi, New Delhi 110016, India.
The concept of inert matrix fuel (IMF) has been proposed to utilize the energetic value of Pu and transmute minor actinides in nuclear reactors. In order to offset the initial reactivity of nuclear fuel, gadolinium (Gd) is employed as a burnable poison, owing to its high neutron absorption cross-section. To gain insights into the radiation stability and influence of grain boundaries on irradiation behaviour, 5 mol% Gd-doped ceria samples, sintered at varying temperatures, were subjected to irradiation using 400 Kr ions.
View Article and Find Full Text PDFSci Rep
October 2024
ELI-ALPS, ELI-HU Non-Profit Ltd., Wolfgang Sandner Utca 3, Szeged, 6728, Hungary.
Laser-driven deuterons generate neutrons with a mean energy of 2.5 MeV, through the H(d,n) fusion reaction in a deuterated polyethylene (dPE) tablet. The deuterium ions are accelerated by 12 fs, 21 mJ laser pulses interacting with a 0.
View Article and Find Full Text PDFSci Rep
September 2024
Bio-Organic Division, Bhabha Atomic Research Centre, Trombay, Mumbai, 400085, India.
Electrolysis of DO may be used as a portable neutron source with numerous applications without the complexity of huge reactor operations. Herein, we report reproducible fast neutron generation by electrolysis of DO using palladium cathode and platinum anode, which was detected with diamond detector, gas filled He detectors after thermalisation with high density polythene, as well as novel epoxy resin and CR-39 detectors. Notably, a highly reproducible neutron generation at electrochemical surfaces of palladium electrode was observed and signature transmutation via Pd (d, n) Ag was corroborated.
View Article and Find Full Text PDFMaterials (Basel)
August 2024
School of Materials Science and Engineering, University of Science and Technology Beijing, Beijing 100083, China.
Beryllium (Be) has been selected as the solid neutron multiplier material for a tritium breeding blanket module in ITER, which is also the primary option of the Chinese TBM program. But the irradiation swelling of beryllium is severe under high temperature, high irradiation damage and high doses of transmutation-induced helium. Advanced neutron multipliers with high stability at high temperature are desired for the demonstration power plant (DEMO) reactors and the China Fusion Engineering Test Reactor (CFETR).
View Article and Find Full Text PDFMed Phys
May 2024
Department of Radiation Oncology, University of Michigan, Ann Arbor, Michigan, USA.
Background: Intensity modulated brachytherapy based on partially shielded intracavitary and interstitial applicators is possible with a cost-effective Yb production method. Yb is a traditionally expensive isotope suitable for this purpose, with an average γ-ray energy of 93 keV. Re-activating a single Yb source multiple times in a nuclear reactor between clinical uses was shown to theoretically reduce cost by approximately 75% relative to conventional single-activation sources.
View Article and Find Full Text PDFEnter search terms and have AI summaries delivered each week - change queries or unsubscribe any time!