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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Tsutomu Yokoyama, Toshiyuki Tamura
Nuclear Technology | Volume 57 | Number 3 | June 1982 | Pages 372-388
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A26304
Articles are hosted by Taylor and Francis Online.
Calculations have been made to investigate the dependence of the primary neutron emission rate (the neutron source strength) of spent boiling water reactor (BWR) fuel assemblies on the irradiation parameters: initial 235U enrichment, void fraction, power density, and operation history. A BWR lattice cell calculation code, which was verified by experiments, has been used to calculate the buildup of transuranium isotopes. The neutron emission rate was split into three components: 242Cm, 244Cm, and other nuclides. The effects of the irradiation parameters have been studied for each of the three components. The energy spectra of the primary neutrons emitted by the irradiated fuel have been calculated parametrically. The calculations have elucidated the neutron emission characteristics of the spent BWR fuel assemblies and provided the basic information to be used for:1. the neutron-shielding design for spent-fuel storage facilities and transportation casks2. the feasibility study of the startup of a BWR without radioisotope neutron source3. the application of passive neutron method to the nondestructive determination of burnup and plutonium contents in spent BWR fuels.
