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Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
Standards Program
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
WIPP improves utility shaft safety, begins infrastructure project
Harrison Western Shaft Sinkers (HWSS), the company drilling a new utility shaft at the Department of Energy’s Waste Isolation Pilot Plant in New Mexico, has retained a safety culture expert following a near-miss accident in the shaft late last year. The safety expert will conduct monthly facilitated discussions with crews working on the shaft to reinforce expectations for identifying concerns regarding unsafe circumstances, according to a recent report by the Defense Nuclear Facilities Safety Board (DNFSB).
T. Iguchi, A. Sekiguchi, M. Nakazawa
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 817-822
Neutronics and Shielding | doi.org/10.13182/FST83-A22961
Articles are hosted by Taylor and Francis Online.
An integral benchmark experiment on the Lithium Fluoride (LiF) material has been carried out in order to check the accuracy of neutronic design calculations. Experimental data of the tritium production rate and the radiation heating rate have been measured directly by each technique using Lithium Carbonate (Li2CO3) pellets and LiF thermo-luminescent dosimeters (LiF-TLDs), and indirectly by the multi-activation foil technique. The present accuracies of the neutronic calculations on the tritium breeding and the nuclear heating are discussed through comparing these benchmark data, where the two-dimensional transport code DOT 3.5 and the ENDF/B-IV cross-section library are applied as a typical example.