3/2/2009 Colloquium - Per Peterson

Per Peterson University of California, Berkeley

Event Info

Title:  Status and Progress for the Pebble-Bed Advanced High Temperature Reactor

Date: Mar 2, 2009
Location: 3105 Etcheverry Hall
Time: 4-5pm

Abstract

The Pebble-Bed Advanced High Temperature Reactor (PB-AHTR) is a liquid-salt cooled, solid fueled HTR that achieves high power conversion efficiency using a closed helium Brayton cycle. This talk reviews the current status and recent progress for the PB-AHTR, including development of the licensing framework, separate effects and integral effect tests to predict transient response, seismic and structural design, zero-power critical tests to validate neutronic models, and initial studies of potential once-through and closed thorium cycles.

Speaker Biography

Per Peterson performs research related to high-temperature fission and fusion energy systems, as well as studying topics related to the safety and security of nuclear materials and waste management. He recently participated as a member of a National Research Council committee reviewing DOE Office of Nuclear Energy R&D programs, which provided recommendations on DOE's Generation IV, AFCI, and GNEP programs. He has served as a member and chair of numerous advisory committees for the national laboratories, including LLNL, LANL, INL, ORNL, and PNNL. He participated in the development of the Generation IV Roadmap in 2002 as a member of the Evaluation Methodology Group, and currently co-chairs its Proliferation Resistance and Physical Protection Working Group. His research in the 1990's contributed to the development of the passive safety systems used in the GE ESBWR and Westinghouse AP-1000 reactor designs. Currently his research group focuses primarily on heat transfer, fluid mechanics, regulation and licensing for high temperature reactors, principally designs that use liquid fluoride salts as coolants.