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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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Bowman & Smith on NRC security programs
Greg Bowman and George Smith work for the Nuclear Regulatory Commission in implementing programs that deal with risk, whether to nuclear power plants or from nuclear materials, such as radiological sabotage and theft or diversion of materials. Bowman is the director of the NRC’s Division of Physical and Cybersecurity Policy in the Office of Nuclear Security and Incident Response. Smith is the senior project manager for security in the Source Management & Protection Branch of the Division of Materials Safety, Security, State, and Tribal Programs in the Office of Nuclear Material Safety and Safeguards.
The three initiatives Bowman and Smith discussed with Nuclear News editor-in-chief Rick Michal are the Insider Threat Program, the Cybersecurity Program, and the Domestic Safeguards Program.
Thomas K. S. Liang, Chin-Jang Chang, Huan-Jen Hung
Nuclear Technology | Volume 139 | Number 3 | September 2002 | Pages 233-252
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT02-A3316
Articles are hosted by Taylor and Francis Online.
In light water reactors, particularly the pressurized water reactor (PWR), the severity of a loss-of-coolant accident (LOCA) would limit how high the reactor power can operate. Although the best-estimate LOCA licensing methodology can provide the greatest margin on the peak cladding temperature (PCT) evaluation during a LOCA, it generally takes much more resources to develop. Instead, implementation of evaluation models required by Appendix K of 10CFR50 on an advanced thermal-hydraulic platform such as RELAP5, TRAC, etc., also can gain significant margin for the PCT calculation. Through compliance evaluation against Appendix K of 10CFR50, all of the required evaluation models have been implemented in RELAP5-3D. To verify and assess the development of the Appendix K version of RELAP5-3D, nine kinds of separate-effects experiments and eight sets of LOCA integral experiments were adopted. Through the assessments against separate-effects experiments, the success of the code modification in accordance with Appendix K of 10CFR50 was demonstrated. Besides, one set of a typical integral large-break LOCA from Loss-of-Fluid Test Facility experiments (L2-5) has also been applied to preliminarily evaluate the integral performance of the Appendix K version of RELAP5-3D. The PCT predicted by the evaluation models is greater than the one from best-estimate calculation in the whole LOCA history with the conservatism of 150 K, and the measured PCTs of L2-5 are also well bounded by the evaluation model calculation. Another seven sets of integral-effect experiments will be further applied in the next step to ensure the reasonable integral conservatism of the newly developed LOCA licensing analysis code (RELAP5-3DK/INER), which can cover all the phases of both large- and small LOCA in one code.