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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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NRC begins special inspection at Hope Creek
The Nuclear Regulatory Commission is conducting a special inspection at Hope Creek nuclear plant in New Jersey to investigate the cause of repeated inoperability of one of the plant’s emergency diesel generators, the agency announced in a February 25 news release.
A. D’Angelo,A. Filip
Nuclear Science and Engineering | Volume 114 | Number 4 | August 1993 | Pages 332-341
Technical Paper | doi.org/10.13182/NSE93-A24042
Articles are hosted by Taylor and Francis Online.
The uncertainty of the 235U, 239Pu, and 238U absolute delayed neutron yields vd is one of the principal sources of uncertainty in predicting the fission reactor reactivity scale βeff. The current uncertainties in the dependence of vd on incident neutron energy is investigated for significance in the evaluation of βeff. The uncertainty effects on the GODIVA, JEZEBEL, Zero Power Reactor, SNEAK, and Masurca benchmark facility calculations are analyzed using ENDF/B and JEF basic data. Different assumptions about the energy dependence result in variations of up to 5% in the reactor spectrum averaged values of vd, and these would result in variations of up to ∼2% in the value of βeff for a typical liquid-metal fast breeder reactor.
