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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.
Masayoshi Akutsu, Yoshinobu Okabe, Kazuziro Satoh, Hideki Kamide, Kenji Hayashi, Nobuyuki Naohara, Kengo Iwashige, Yoji Shibata
Nuclear Technology | Volume 98 | Number 1 | April 1992 | Pages 14-26
Technical Paper | Fast Reactor Safety / Fission Reactor | doi.org/10.13182/NT92-A34647
Articles are hosted by Taylor and Francis Online.
The thermal-hydraulic characteristics of a pooltype fast breeder reactor during decay heat removal are studied experimentally with a one-eighth-scaled threedimensional reactor model using water as the working fluid. The model is designed to simulate reactor operations from full power to scram transient and decay heat removal conditions as well as two types of decay heat removal systems, a direct reactor auxiliary cooling system (DRACS) and a primary reactor auxiliary cooling system (PRACS). The transient thermal-hydraulic performance of the DRACS is compared with that of the PRACS for the water test results. The results are used to evaluate the accuracy of the multidimensional analysis codes AQUA and THER VIS. The analytical results are generally in good agreement with the measurements.