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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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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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Waste Management 2024: The symposia at 50
This year marked the 50th anniversary of Waste Management Symposia’s Waste Management Conference, held March 10–14 in Phoenix, Ariz. The event has grown significantly since the first Waste Management Conference in 1974, which attracted about 200 attendees. This year’s conference saw a record attendance of around 3,300 people from more than 20 different countries and boasted 235 technical sessions and 89 exhibitors.
H. Gerwin, W. Scherer, E. Teuchert
Nuclear Science and Engineering | Volume 103 | Number 3 | November 1989 | Pages 302-312
Technical Paper | doi.org/10.13182/NSE89-A23682
Articles are hosted by Taylor and Francis Online.
The TINTE code deals with the nuclear and thermal transient behavior of a high-temperature reactor, taking into consideration the mutual feedback effects in two-dimensional r-z geometry, including the following: 1. time-dependent neutron flux calculation 2. time-dependent heat source distribution (local and nonlocal fractions) 3. time-dependent heat transport from the fuel to the fuel element surface 4. time-dependent global temperature distribution 5. gas flow distribution for a given mass flow or given pressure difference or even under natural circulation conditions 6. convection and its feedback to the circulation. The TINTE code has been tested against transient experiments performed at the Arbeitsgemein-schaft Versuchsreaktor. It has also been used successfully for other reactor investigations and thermofluid problems including design studies for a small heating reactor of the peu à peu loading type.