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Fusion Science and Technology
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DTRA’s advancements in nuclear and radiological detection
A new, more complex nuclear age has begun. Echoing the tensions of the Cold War amid rapidly evolving nuclear and radiological threats, preparedness in the modern age is a contest of scientific innovation. The Research and Development Directorate (RD) at the Defense Threat Reduction Agency (DTRA) is charged with winning this contest.
Bhoomi S. Gajjar, Anil Tyagi, Sanjeev Varshney, Siddharth Kumar, Saroj Jha, Hitesh Kumar B. Pandya, P. V. Subhash
Fusion Science and Technology | Volume 82 | Number 4 | May 2026 | Pages 761-774
Review Article | doi.org/10.1080/15361055.2025.2475423
Articles are hosted by Taylor and Francis Online.
The Neutronics Group at ITER-India is carrying out neutronics activities for ITER diagnostics systems [Equatorial Port Plug 11 (EPP-11) and Upper Port Plug (UPP) 09 (UPP-09)] as part of India’s in-kind contribution. The activities include development works on comprehensive nuclear and shielding analyses supporting significant aspects of design, optimization, engineering, and safety of systems and facilities. Neutronics analysis for the X-Ray Crystal Spectrometer (XRCS) Survey diagnostics system at EPP-11 of ITER is being conducted at ITER-India. The preliminary scoping study of the shielding design for the spectrometer with a shielded cabinet (SC) is completed. Because of space and weight constraints, robust optimization for the shielding design is carried out. Different sets of calculations have been done using MCNP. Reduced neutron flux at the SC is achieved by optimizing the geometry of the neutron beam dump. Nuclear activation analysis, radioactive waste classification, and important radiological responses for all the components are performed for the XRCS diagnostics in EPP-11. The results are validated by the Port Integrator and ITER Organization. The neutronic analysis for UPP-09 was carried out for the Preliminary Design Review activities. The total neutron flux was calculated with an error of less than 10% for all mesh voxels. Estimations of the neutron and photon flux and nuclear heating were made. The nuclear activation analysis was done by using 175 energy groups and the FISPACT code for estimation of the activity levels in different diagnostics shielding modules (DSMs). The design is being further optimized for the effectiveness of the shielding by modifying the DSM, adding shielding to reduce streaming from gap areas and shielding in the UPP enclosure.