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Latest News
Argonne investigates industrial SMR applications for postwar Ukraine
Argonne National Laboratory will play a leading role in planning and rebuilding a nuclear-generated clean energy infrastructure for postwar Ukraine as part of the lab’s focus on developing small modular reactor applications to help countries meet energy security goals. The latest plans, described in a November 19 article, were announced on November 16 at COP29 in Baku, Azerbaijan.
Dan Gabriel Cepraga, Gilio Cambi, Manuela Frisoni, Gian Carlo Panini
Fusion Science and Technology | Volume 34 | Number 3 | November 1998 | Pages 969-973
Neutronics Experiments and Analysis (Poster Session) | doi.org/10.13182/FST98-A11963738
Articles are hosted by Taylor and Francis Online.
The ANITA-4/F is a code package for the activation characterisation of materials exposed to neutrons in fusion machines. The package has been intensively used by ENEA for safety assessment of the International Thermonuclear Experimental Reactor ITER to evaluate the activated corrosion product source terms. This paper presents a summary description of the package and gives the details of its capabilities. The main component of the package is an updated version of the activation code ANITA that computes the radioactive inventory of a material subject to neutron irradiation, continuous or stepwise. It provides activity, atomic density, decay heat, biological hazard and gamma-ray source of each nuclide; total activity, decay heat, contact dose equivalent, gamma-ray spectra and other relevant parameters, for the irradiated material, versus cooling time. As an option, those parameters may be plotted by the GRANITA module, as a function of the cooling time. The code is provided with a complete data base that includes: 1) the FENDL/A-2 neutron activation data libraries (both for the standard 100 GAM-II and 175 VITAMIN-J groups structure), 2) the FENDL/D-2 decay data library, 3) the ICRP dose coefficients for ingestion and inhalation of radionuclides. Arbitrary structure can be used for the neutron irradiation spectrum. It is internally converted to one of the standard structures. Continuous or multi-steps (up to 2000 burn-dwell intervals) can be considered for the operational scenario. A different level of the irradiation flux can be used for each one of the exposure time step. The paper presents also, as an example, an application to the neutron exposure characterisation for the AISI 316 LN of the first wall, with reference to the basic performance phase of ITER.
