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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Fusion Science and Technology
Latest News
College students help develop waste-measuring device at Hanford
A partnership between Washington River Protection Solutions (WRPS) and Washington State University has resulted in the development of a device to measure radioactive and chemical tank waste at the Hanford Site. WRPS is the contractor at Hanford for the Department of Energy’s Office of Environmental Management.
Peter Ozemoyah, John Robinson
Fusion Science and Technology | Volume 71 | Number 3 | April 2017 | Pages 450-456
Technical Note | doi.org/10.1080/15361055.2017.1291037
Articles are hosted by Taylor and Francis Online.
Tritium in everyday water (potable water) is frequently of a level that is too low for measurement with conventional instrumentation that is affordable by small laboratories. Scintillation counters that can measure in fractions of Becquerels per litre are usually out of the reach of most laboratories, especially in developing countries. By concentrating the tritium by a known amount, it can reach measurable levels that can be converted back to the original concentration. Affordability of the concentrating process is vital in the overall process.
A simple concentrating process based on purification and electrolysis was designed and fabricated. The tritium isotope enrichment level, the volumetric reduction and the time frame required for the enrichment were determined using the simple designed and fabricated process, and an easily affordable scintillation counter.
The simple designed and fabricated system effectively concentrated the tritium in the sampled water several times the initial value. The enrichment resulted in the output product being measurable in a non-expensive scintillation counter.