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NRC proposes changes to its rules on nuclear materials
In response to Executive Order 14300, “Ordering the Reform of the Nuclear Regulatory Commission,” the NRC is proposing sweeping changes to its rules governing the use of nuclear materials that are widely used in industry, medicine, and research. The changes would amend NRC regulations for the licensing of nuclear byproduct material, some source material, and some special nuclear material.
As published in the May 18 Federal Register, the NRC is seeking public comment on this proposed rule and draft interim guidance until July 2.
Koichi Hata, Masahiro Shiotsu, Nobuaki Noda
Nuclear Science and Engineering | Volume 154 | Number 1 | September 2006 | Pages 94-109
Technical Note | doi.org/10.13182/NSE06-A2620
Articles are hosted by Taylor and Francis Online.
The critical heat flux (CHF) of subcooled water flow boiling for a high length/diameter (L/d) region is systematically measured for the flow velocities (u = 6.93 to 13.32 m/s), the outlet subcoolings (Tsub,out = 12.5 to 113 K), the inlet subcoolings (Tsub,in = 45 to 148.7 K), the outlet pressure (Pout = 773.50 to 861.12 kPa), and the inlet pressure (Pin = 796.16 to 920.07 kPa). Type 304 stainless steel tubes of inner diameter (d = 2 mm) and heated lengths (L = 21.5, 79.45, and 149.7 mm) with L/d = 10.75, 39.73, and 74.85 are used. The CHF correlation against outlet subcooling including the effect of L/d already presented by the authors describes the CHF obtained in this work within a 15% difference. However, the correlation against inlet subcooling also presented by the authors in the same papers needs a small modification to describe the CHF obtained in this work for a high L/d range. The modified correlation describes not only the experimental data for L/d up to 75 on the 2-mm tube but also the CHF for the same range of L/d on larger diameter tubes predicted by the correlation against outlet subcooling within a 15% difference.
