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.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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!
Latest Magazine Issues
Dec 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
December 2025
Nuclear Technology
Fusion Science and Technology
November 2025
Latest News
INL makes first fuel for Molten Chloride Reactor Experiment
Idaho National Laboratory has announced the creation of the first batch of enriched uranium chloride fuel salt for the Molten Chloride Reactor Experiment (MCRE). INL said that its fuel production team delivered the first fuel salt batch at the end of September, and it intends to produce four additional batches by March 2026. MCRE will require a total of 72–75 batches of fuel salt for the reactor to go critical.
J. R. Easoz, R. Bajaj, R. E. Gold, J. W. H. Chi
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 780-784
Blanket and First Wall Engineering | doi.org/10.13182/FST83-A22955
Articles are hosted by Taylor and Francis Online.
This paper reports work performed under Program Element I (PE-I) of the First Wall, Blanket, and Shield Program, the principal objectives of which are the testing of first wall design concepts to support the design of fusion reactor first walls and the verification of analytical techniques and design tools. The test facility, ESURF, consists of a 36 kW continuous duty electron beam, evacuated target chamber, and a 6.9 MPa water loop for active cooling of test pieces. Long pulse “steady state” surface heat loads are simulated by rastering the beam in two dimensions, while disruption heat loads are simulated by imposing a focused, stationary beam for a fixed length of time on the target area. Initial test pieces consisted of stainless steel (Type 316) tubes. Tests to date have included thermal-hydraulic characterization of the specimens, thermal cycling up to 500 cycles, disruption heat load simulations, and combined disruption heat loads with thermal cycling. The test results reported here address the verification of predicted thermomechanical response of the specimens, the effects of disruption heat loads on surface melting and crack formation, and the affect of thermal cycling on crack formation/propagation.