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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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February 2024
Latest News
Can hydrogen be the transportation fuel in an otherwise nuclear economy?
Let’s face it: The global economy should be powered primarily by nuclear power. And it probably will by the end of this century, with a still-significant assist from renewables and hydro. Once nuclear systems are dominant, the costs come down to where gas is now; and when carbon emissions are reduced to a small portion of their present state, it will become obvious that most other sources are only good in niche settings. I mean, why use small modular reactors to load-follow when they can just produce that power instead of buffering it?
Haibo Liu, Kaiming Feng
Fusion Science and Technology | Volume 54 | Number 4 | November 2008 | Pages 970-977
Technical Paper | doi.org/10.13182/FST08-A1912
Articles are hosted by Taylor and Francis Online.
The Chinese helium-cooled solid breeder (CH-HCSB) test blanket module (TBM) is designed to be tested in ITER, and its aim is to validate the feasibility of a DEMO fusion reactor. The thermal-hydraulic transient analysis has to testify that the TBM and its helium cooling system (HCS) will not impact the safe operation of ITER under both normal and accidental conditions. In order to simulate the transient accidents, the TBM and HCS are modeled using the RELAP5/MOD3 system code. The steady-state results indicate that the designed TBM inlet/outlet temperatures are obtained and the temperature of first-wall (FW) structural material is below the limit. An ex-vessel loss-of-coolant accident (LOCA) will induce the melting of FW beryllium armor after ~80 s of LOCA initiation, and some controlling measures have to be taken before melting. The pressurization of the vacuum vessel induced by an in-vessel LOCA is within the allowable value of the ITER design. Because of pressurization of the purge gas system, the tritium extraction system has to be isolated from the TBM quickly when an in-box LOCA happens. Based on the results, the design of the CH-HCSB TBM could be further modified in order to assure the safety of the TBM and ITER, from an engineering point of view.