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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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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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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Beyond borders
Lisa Marshallpresident@ans.org
Global partnerships advance the nuclear enterprise, demonstrating commitment to energy security, supply chain buildout, and economic and human development. Collaborations remain imperative, keeping these things in mind:
Approximately half of the 400-GW reactor fleet will be retiring by 2040.1
The forecasted need for new nuclear is 300–600 GW by 2050.
There is a need to counter the build-own-operate model.2
Appropriate funding and financing mechanisms are needed.
Host country regulatory oversight is paramount.
By 2050, there will be 4 million nuclear professionals supporting the industry.3
Michitsugu Mori
Nuclear Technology | Volume 148 | Number 1 | October 2004 | Pages 12-24
Technical Paper | RETRAN | doi.org/10.13182/NT04-A3544
Articles are hosted by Taylor and Francis Online.
Two advanced boiling water reactors (ABWRs) whose electric output power is 1356 MW have been commercially operated since 1996 and 1997 by the Tokyo Electric Power Company (TEPCO) in Japan. Features of an ABWR are reactor internal pumps (RIPs) placed in the lower plenum and downcomer, peripherally bottom-mounted on the reactor pressure vessel - which should require different modeling from the jet pumps and two recirculation pumps in the primary outer-loop recirculations of BWR-5.Efforts focused on modeling and simulating the ABWR with transient analyses by the point-kinetics model with the local reactivity modified by local importance weighting of the squared nodal power during start-up tests using the RETRAN-3D code, version MOD003 without three-dimensional kinetics. The core and reactor pressure vessel including ten ABWR RIPs and the steam lines were modeled, and simulations were carried out for the cases of the one-pump trip test, the changing-setpoint tests, the main-steam-isolation-valve-closure test, and the generator load rejection test with bypass.The analytical simulation with RETRAN-3D/MOD003 well reproduced the measured data of the ABWR in operation for the RIP trip and the transient tests and could demonstrate its validation for applying to the ABWR with modeling of RIPs.