area was the result of a study supported by USNRC on Accident Management. These efforts resulted in several publications, one of which was an invited paper in Nuclear engineering and Design and an invitation by the International Atomic Energy Committee to evaluate the Krsko nuclear power plant accident management program. The second area of study was steam generator tube vibration and loose parts wear This work extended the state of the art in vibration prediction for single phase flow over tube bundles by predicting the onset of vibration without resorting to use of experimental data, a first for rod bundles. An invited paper appeared in Nuclear Engineering and Design that summarizes this work where results for two-phase flow were also included. Another in the same journal addresses the issue of dry out and heat up of a reactor core following a severe accident. This work placed UCLA at the forefront of nuclear power plant severe accident research culminating with his being general chairman of the 6th International Post Accident Heat Removal Information Meeting held at UCLA in 1986 and co-chair of a similar meeting held in Dubrovnik in 1989. During 1988, Dr. Catton participated in an effort to establish the uncertainty in calculated reactor system behavior following a major loss of coolant accident. The results of this work led to five publications in Nuclear Engineering and Design. We, the group, had to bring together the results of a $1.5B research program that spanned a 15 year period. The work underwent peer review by eminent researchers from all the major western nations and was judged to be a first of its kind. A second such study addressing severe accidents (which led to elimination of the DCH issue) was initiated by NRC but his appointment to the ACRS limited his involvement to oversight. Dr. Catton was the ACRS representative to the Steam Generator, Safety Stop Valve and Check Valve Owner Groups. Issues like core axial power distribution and erosion of shutdown margin (SDM) attributing to crud buildup on the nuclear fuel and subsequent boron deposition in the crud layer, and steam generator tube vibration at SONGS were addressed as an independent consultant following his ACRS membership. Professor Catton was appointed to membership on the ACRS in February of 1989 and served until February of 1997. Any safety issue arising in the nuclear industry is within the charter of the ACRS. Every licensed plant must have an
area was the result of a study supported by USNRC on Accident Management. These efforts resulted in several publications, one of which was an invited paper in Nuclear engineering and Design and an invitation by the International Atomic Energy Committee to evaluate the Krsko nuclear power plant accident management program. The second area of study was steam generator tube vibration and loose parts wear This work extended the state of the art in vibration prediction for single phase flow over tube bundles by predicting the onset of vibration without resorting to use of experimental data, a first for rod bundles. An invited paper appeared in Nuclear Engineering and Design that summarizes this work where results for two-phase flow were also included. Another in the same journal addresses the issue of dry out and heat up of a reactor core following a severe accident. This work placed UCLA at the forefront of nuclear power plant severe accident research culminating with his being general chairman of the 6th International Post Accident Heat Removal Information Meeting held at UCLA in 1986 and co-chair of a similar meeting held in Dubrovnik in 1989. During 1988, Dr. Catton participated in an effort to establish the uncertainty in calculated reactor system behavior following a major loss of coolant accident. The results of this work led to five publications in Nuclear Engineering and Design. We, the group, had to bring together the results of a $1.5B research program that spanned a 15 year period. The work underwent peer review by eminent researchers from all the major western nations and was judged to be a first of its kind. A second such study addressing severe accidents (which led to elimination of the DCH issue) was initiated by NRC but his appointment to the ACRS limited his involvement to oversight. Dr. Catton was the ACRS representative to the Steam Generator, Safety Stop Valve and Check Valve Owner Groups. Issues like core axial power distribution and erosion of shutdown margin (SDM) attributing to crud buildup on the nuclear fuel and subsequent boron deposition in the crud layer, and steam generator tube vibration at SONGS were addressed as an independent consultant following his ACRS membership. Professor Catton was appointed to membership on the ACRS in February of 1989 and served until February of 1997. Any safety issue arising in the nuclear industry is within the charter of the ACRS. Every licensed plant must have an