[en] The features of the DLTS detection of defects with retrappability of thermally excited carriers due to a large value of effective capture cross section are considered. Indications allowing identification of the implementation of the given model are found.

[en] Results and analyses are reported for TREAT in-pile transient overpower tests of margin to cladding failure and pre-failure axial expansion of metallic fuel. In all cases the power rise was exponential on an 8 s period until either incipient or actual cladding failure was achieved. Test fuel included EBR-II driver fuel and ternary alloy, the reference fuel of the Intergral Fast Reactor concept. Test pin burnup spanned the widest range available. The nature of the observed cladding failure and resultant fuel dispersals is described. Simple models are presented which describe observed cladding failures and pre-failure axial expansions yet are general enough to apply to all metal fuel types

[en] After outlining main characteristics of PIPER-ONE facility (a BWR thermalhydraulic simulator) the paper describes the results already achieved, as well as research perspectives

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[en] TASS 1.0 is consisted of two parts. First part analyze the reactor transients and calculates system parameters during the transients. This part comprises the program of the primary and secondary thermal hydraulic model, the core model, the transfer model, the protection and the control system. The second part is the TASS executive routine. This part provides an operating system for TASS. The user can execute TASS with above models interactively through the TASS executive routine. But TASS executive routine is very large and the function is restricted. The development of GRIS( Graphical Routines for Interactive Simulation) was initiated to overcome the limitation of the TASS executive routine. TASS-NPA was developed based on GRIS. TASS-NPA simulation can be performed on Windows 95 and Window Nt of IBM Pc. The verification of the TASS-NPA function was performed with the Feed Water Line Break of Kori 3/4. (Author). 6 refs., 3 tabs., 26 figs

[en] An examination has been made of how the currently available computing capabilities could be used to reduce Liquid Metal Fast Reactor design, manufacturing, and construction cost. While the examination focused on computer analyses some other promising means to reduce costs were also examined. (author)

[en] Suppression of the floating body effects in partially depleted SOI-MOSFETs (silicon-on-insulator metal oxide semiconductor field effect transistors) with and without body contact electrodes has been investigated using nuclear microprobes with currents of 5-250 pA. Transient SOI-MOSFET behavior with and without body contact electrodes during ion irradiation by three-dimensional computer simulation has also been compared with that using nuclear microprobes. The floating body effects were observed in SOI-MOSFETs without body contact electrodes by nuclear microprobe irradiation, while those were suppressed in the SOI-MOSFETs with body contacts

No abstract available

[en] Transient testing is critical for understanding how new fuels perform in accident conditions such as transient overpower and/or under cooling events. In February of 2014, The U.S. Department of Energy (DOE) determined that a Finding of No Significant Impact (FONSI) was appropriate for the resumption of transient testing of nuclear fuels and materials. At that point, work began on the restart of the Transient Reactor Test Facility (TREAT), which was the DOE preferred alternative for reestablishing transient testing capability for nuclear fuels and materials in the U.S. Significant progress has been made in the restart of TREAT for transient testing since the FONSI in 2014. The progress made since 2014 towards restarting TREAT and the current status is documented in this summary. (author)