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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.
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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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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
A.C. Klein, R.A. Pawlowski, H.H. Lee
Fusion Science and Technology | Volume 20 | Number 4 | December 1991 | Pages 759-766
Space Nuclear Power/Propulsion | doi.org/10.13182/FST91-A11946933
Articles are hosted by Taylor and Francis Online.
Incore thermionic space reactor design concepts which operate at a nominal power output range of between 20 and 50 kWe are described. Details of the neutronic, thermionic, thermal, and shielding performance are presented. These moderated reactor concepts use enriched uranium dioxide fuel, zirconium hydride moderator, reinforced tungsten emitters, niobium collectors, alumina insulators, and sodium-potassium coolant in a long, single cell configuration. Due to the strong absorption of thermal neutrons by natural tungsten, and the large amount of that material within the reactor core, two options for the reactor are considered. The first uses enriched tungsten (greater than 70 weight percent W-184) emitters and only thermionic fuel elements (TFEs) in the core to achieve criticality and sufficient lifetime. The second option uses natural tungsten and driver fuel elements in addition to the TFEs in the core. An overall systems design code has been developed to model advanced incore thermionic energy conversion based nuclear reactor systems for space applications. The code modules include neutronics and core criticality, a thermionic fuel element performance module with integral thermal hydraulic calculation capability, a radiation shielding module, and a module for waste heat rejection. Coupled thermal hydraulic and thermionic performance calculations are presented. The model includes the effects of radiation and conductive heat transfer as well as electron cooling of the emitter, and the resistive lead losses on long emitter TFE concepts. Radiation shielding design and overall system heat rejection analyses are also presented.