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The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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2024: The Year in Nuclear—April through June
Another calendar year has passed. Before heading too far into 2025, let’s look back at what happened in 2024 in the nuclear community. In today's post, compiled from Nuclear News and Nuclear Newswire are what we feel are the top nuclear news stories from April through May 2024.
Stay tuned for the top stories from the rest of the past year.
K. V. Subbaiah, C. Sunil Sunny
Nuclear Technology | Volume 135 | Number 3 | September 2001 | Pages 265-272
Technical Paper | Radiation Protection | doi.org/10.13182/NT01-A3221
Articles are hosted by Taylor and Francis Online.
KAMINI is the Kalpakkam Mini Reactor, and its main purpose is to cater to experimental needs and for neutron radiography. It is a water-cooled reactor with 233U as the fissile material. Using the Monte Carlo n-particle transport code MCNP, shielding optimization calculations are carried out for the south beam port tube, which is meant for neutron radiography of spent-fuel subassemblies of the fast breeder test reactor. The neutron beam port is a graded cylindrical aluminium channel starting from the center of the reactor core; it pierces through the biological shield and is 2 m long. The diameter of the channel at the core center is 54 mm, at the other end it is 25 cm, and it is 0.5 m below the floor level. The latter end serves as the neutron surface source for these calculations. The calculations have been carried out in cylindrical geometry (r,z) of shield structures. From results of the analysis, a movable shield 50 cm thick (25 cm paraffin and 25 cm lead), 75 cm wide, and 172 cm long extending ~95 cm into the demineralizer room (cooling water purification room) is proposed to replace the existing temporary shield structure. In addition, fixed shields of the same thickness and width of 50 cm on either side of the beam is recommended to reduce the dose levels to a few tens of microsieverts per hour in the accessible areas. Further, the lead-shielded cylindrical tube meant for insertion of irradiated fuel subassemblies for neutron radiography needs to be covered with 20 cm of paraffin up to a height of 1 m from ground level to avoid streaming of neutrons through the air column.