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ANS hosts webinar on criticality safety standards
A diagram depicting the NRC’s regulatory structure for nuclear criticality safety. (Image: Oak Ridge National Laboratory)
The American Nuclear Society’s Risk-informed, Performance-based Principles and Policy Committee (RP3C) held another presentation in its monthly Community of Practice (CoP) series last month. RP3C chair Steven Krahn opened the meeting with brief introductory remarks about the importance of risk-informed, performance based (RIPB) decision-making and the need for new approaches to nuclear design that go beyond conventional and deterministic methods.
P. E. MacDonald, J. Weisman
Nuclear Technology | Volume 31 | Number 3 | December 1976 | Pages 357-366
Technical Paper | Fuel | doi.org/10.13182/NT76-A31672
Articles are hosted by Taylor and Francis Online.
It is postulated that typical light water reactor (LWR) fuel pellets will crack after a few power cycles and that the majority of the pellet segments will lie against the cladding. When there is a nominal cladding-to-pellet gap at operating conditions, pellet cracking will improve the fuel-to-cladding gap conductance but will reduce the fuel thermal conductivity. A model that accounts for the effects of fuel pellet cracking on both fuel conductivity and gap conductance has been formulated. Fuel centerline temperature measurements were made during the steady-state irradiation in the Halden Heavy Boiling Water Reactor of four typical LWR-type test rods with varying fuel density and pellet-to-cladding gap sizes. Calculations using the cracked pellet model were compared to the in-pile temperature measurements, and good agreement was obtained.