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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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Deep Space: The new frontier of radiation controls
In commercial nuclear power, there has always been a deliberate tension between the regulator and the utility owner. The regulator fundamentally exists to protect the worker, and the utility, to make a profit. It is a win-win balance.
From the U.S. nuclear industry has emerged a brilliantly successful occupational nuclear safety record—largely the result of an ALARA (as low as reasonably achievable) process that has driven exposure rates down to what only a decade ago would have been considered unthinkable. In the U.S. nuclear industry, the system has accomplished an excellent, nearly seamless process that succeeds to the benefit of both employee and utility owner.
Yu Weng, Fangfang Cao, Xiaobing Tuo, Hongfang Gu, Haijun Wang
Nuclear Science and Engineering | Volume 190 | Number 1 | April 2018 | Pages 93-104
Technical Paper | doi.org/10.1080/00295639.2017.1417345
Articles are hosted by Taylor and Francis Online.
In a 1250-MW pressurized water reactor (PWR), coolant is injected into the reactor vessel under accident conditions through the method of direct injection, which is the most important function of the emergency core cooling system. Since the problem has been found that safety injection start-up will have a significant thermal effect on the reactor’s internal system, a confirmatory study of an improved structure is required in the initial design stage. In this paper, the heat transfer and flow characteristics of the core barrel, the neutron shielding panels, and the radiation surveillance capsules are investigated by a scaled experiment combined with a numerical method to obtain the distribution of the wall temperature and the convective heat transfer coefficient on the outer wall of the reactor internals under different injection conditions. In addition, potentially dangerous parts have been pointed out, and dimensionless correlations are fitted to describe the heat transfer laws of key parts of reactor internals for use in reactor design. This research fills in the gaps in the study of heat transfer under direct injection of the reactor internals in a PWR, providing support for the safety of the reactor structure.