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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Nuclear Science and Engineering
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Nuclear Technology
Fusion Science and Technology
Latest News
A more open future for nuclear research
A growing number of institutional, national, and funder mandates are requiring researchers to make their published work immediately publicly accessible, through either open repositories or open access (OA) publications. In addition, both private and public funders are developing policies, such as those from the Office of Science and Technology Policy and the European Commission, that ask researchers to make publicly available at the time of publication as much of their underlying data and other materials as possible. These, combined with movement in the scientific community toward embracing open science principles (seen, for example, in the dramatic rise of preprint servers like arXiv), demonstrate a need for a different kind of publishing outlet.
Yoshiyuki Asaoka, Kunihiko Okano, Tomoaki Yoshida, Ryouji Hiwatari, Seiji Mori
Fusion Science and Technology | Volume 39 | Number 2 | March 2001 | Pages 1018-1022
Safety and Environment | doi.org/10.13182/FST01-A11963376
Articles are hosted by Taylor and Francis Online.
Radioactive waste generated from the CREST reactor has been evaluated. Activation of blankets and shields used during a plant lifetime was evaluated by an activation calculation code taking into accounts of the distribution of neutron wall loading and the scenario of blanket replacement. Limits on surface dose limits define the feasibility of recycling by remote handling (RHR) and by hands-on operation (HOR). After 50 years for decay of activated components, surface dose rate of most of components exceeds 10 mSv/h and cannot be recycled. Some of shields are lower than 10 mSv/h and have a possibility of RHR. After 100 years, surface dose rate of all components is lower than 3 mSv/h, and RHR is feasible. Half of shields are lower than 0.01 mSv/h and have a possibility of HOR. After 125 years, dose rate of all components is lower than 1 mSv/h. RHR with a relatively simple shielding precaution may be feasible. In the cases of 150 years or later, little degradation of dose rate can be expected. Therefore, the used components should be managed within approximately 125 years by suitable methods.
