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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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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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.
F. Cismondi, G. Aiello, S. Kecskes, G. Rampal
Fusion Science and Technology | Volume 60 | Number 1 | July 2011 | Pages 123-127
ITER Systems | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 1) | doi.org/10.13182/FST11-A12338
Articles are hosted by Taylor and Francis Online.
Six different breeding blanket concepts will be tested in ITER under the form of six different Test Blanket Modules (TBMs). In the frame of the activities of the European TBM Consortium of Associates the Helium Cooled Pebble Bed (HCPB-TBM) and the Helium Cooled Lithium Lead (HCLL) Test Blanket Modules are developed in Karlsruhe Institute of Technology (KIT) and in CEA Saclay respectively. For each EU TBM concept, four different TBMs will be installed into one dedicated ITER equatorial port and tested during different test campaigns. The main goal of the ITER TBM program is providing DEMO relevant experimental data for the three main functions of a blanket module of a future fusion reactor, namely removing heat, breeding tritium and shielding sensitive components from radiation.The two EU TBMs share a common external structure (the so called TBM box) while featuring a different internal design of the Breeder Units (BUs), reflecting the different breeding concept. The preliminary design assessment of the two TBMs boxes is based on nuclear analyses and on the evaluation of the power produced in the BU and deposed on the TBM box structures. The preliminary thermomechanical designs have been presented and are based on steady state analyses.The TBMs will work under ITER loads, i.e. cyclic loads defined by the typical ITER pulses. Transient thermal and mechanical analyses of the two EU TBMs under a typical ITER pulse are presented in this paper, identifying the main design issues related to: structural behavior of the TBM box, codes and standard rules for assessing the TBM box integrity, TBM operational domain and related DEMO relevancy of the experimental campaign. Solutions to improve the weak structural points of the present designs are proposed, identifying the missing rules and the modelling development needs.
