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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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Latest News
NRC Hanson's renomination clears Senate committee
Hanson
The U.S. Senate Environment and Public Works Committee voted 18–1 yesterday to advance the renomination of Christopher T. Hanson as a member of the Nuclear Regulatory Commission. Hanson has been a commissioner since 2020, and was named chair by President Biden in January 2021. The full U.S. Senate will consider Hanson’s nomination later this month.
Voices of support: “Chair Hanson is a dedicated public [servant] who has thoughtfully and . . . skillfully led the [NRC] during his tenure as its chair. Throughout his time on the[NRC], he has demonstrated his commitment to ensuring the safety and the security of our nation’s use of nuclear energy,” said EPW committee chair Tom Carper (D., Del.) before the vote.
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.