ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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Jul 2024
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Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
Kairos’s Hermes 2 passes NRC safety review
Nuclear Regulatory Commission staff has completed its final safety evaluation for Kairos Power’s application to build its Hermes 2 molten salt–cooled reactor test facility in Oak Ridge, Tenn., the agency announced July 22. Earlier, and independently, the NRC’s Advisory Committee on Reactor Safeguards (ACRS) reviewed safety-related aspects of the Kairos application and provided its review to the Commission on July 17. The evaluation concluded that there are no safety aspects that would preclude issuing a construction permit for the facility, but that can’t happen until the NRC staff issues its final environmental assessment later this summer and the Commission assesses the staff’s work (under newly streamlined procedures for mandatory hearings) this fall before voting on whether to authorize a construction permit.
Ana C. Fernandes, Isabel C. Gonçalves, Nuno P. Barradas, António J. Ramalho
Nuclear Technology | Volume 143 | Number 3 | September 2003 | Pages 358-363
Technical Note | Fission Reactors | doi.org/10.13182/NT03-A3423
Articles are hosted by Taylor and Francis Online.
The Monte Carlo code MCNP-4C was used to calculate the effective multiplication coefficient of a core configuration of the Portuguese Research Reactor (RPI) and the neutron fluxes in the core and in the reflector region.A comparison of the results obtained with MCNP and with the deterministic codes WIMSD-5 and CITATION was made. Consistent deviations of 2% for the effective multiplication constant and 8 to 28% for the neutron flux, depending on the energy range, were observed.Thermal, epithermal, and fast neutron flux measurements were performed using activation detectors. The calculations agree with experimental values within <15%; therefore, the Monte Carlo results can be used to predict the neutron field in other locations and irradiation facilities of the RPI.