This work presents experimental results on the distribution of irradiated reactor uranium from fallout after the accident at Chernobyl Nuclear Power Plant (NPP) in comparison to natural uranium distribution in different soil types. Oxidation processes and vertical migration of irradiated uranium in soils typical of the 30 km relocation area around Chernobyl NPP were studied using 236U as the tr...

BNCT is a radiotherapy modality based on the neutron capture and fission reactions that occur when boron-10 is irradiated by thermal neutrons. This reaction generates alpha and lithium that produce high density of ionizations in close to the reaction site. The concept provides high absorbed doses into the cancerous cells preserving the adjacent healthy tissues. Nowadays, the available neutron s...

There is increasing interest in using ionic molten-salt Flibe not only as self-cooled tritium(T)-breeding material in a fusion reactor blanket but also as fuel solvent of molten-salt fission reactors. Application of Flibe to T-breeding fluid for a stellarator-type fusion reactor operated at a high magnetic field brings large simplification of its blanket structure, allowing continuous operation...

One of challenges the Monte Carlo full core simulations is to obtain acceptable statistical variance local parameters throughout whole reactor at a reasonable computation cost. The tends be larger in low-power regions. To tackle this problem, Uniform-Fission-Site method was implemented code MC21 and its effectiveness demonstrated on NEA performance benchmark. very similar also Serpent under nam...

Argonne National Laboratory (ANL), along with other national laboratories, has been developing a solvent extraction process for partitioning of spent fuel constituents to lead to safer and cheaper disposal of high-level waste. The process, known as UREX+, separates key radionuclides from dissolved spent fuel into: (1) uranium for disposal as LLW, (2) technetium for disposal as HLW, (3) iodine f...

ECCN Description Page 0A001 "Nuclear reactors", i.e. reactors capable of operation so as to maintain a controlled, self-sustaining fission chain reaction, and equipment and components specially designed or prepared for use in connection with a "nuclear reactor". . 0A002 Power generating or propulsion equipment specially designed for use with space, marine or mobile "nuclear reactors". 0A984 Sho...

-The finite element response matrix method has been applied to the solution of the neutron transport equation. This method has previously been applied to the neutron diffusion equation for coarse mesh reactor analysis with excellent results. As with the diffusion equation implementation, the transport method employs a local-global projection technique to allow treatment of internal heterogeneit...

Three neutron reactions leading to production of the rare gases Ar41 and Xe135 have been in­ vestigated. Single crystal samples of KF, CaF2 , and BaF2 were irradiated in the Berlin reactor and the target-free absolute activities of the rare gas isotopes measured by a /^-/-coincidence method. The calculated cross sections are K41 (n,p)Ar41: o = ( 2 ,73±0,41) mb; o0= (98,6± 14,8) mb; Ca44(n,a)Ar4...

Abstract Z-Pinch fusion centre, encased by a fission envelope, serves as an individual neutron source. It can expeditiously catalyze reactions in 238U and 232Th nuclear materials, which are hard to use current commercial reactors. This is the essence of Driven Fusion-Fission Hybrid Reactor (Z-FFR). The core acts stand-alone source, efficiently driving energy materials that difficult existing re...

The use of a lead slowing-down spectrometer (LSDS) is considered as a possible option for nondestructive assay of fissile material of used nuclear fuel. The primary objective is to quantify fissile isotopes, particularly 239Pu and 235U, via a direct measurement distinguishing them through their characteristic fission spectra in the LSDS. In this paper, we present several assay measurements perf...