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Garrish up for repeat term as DOE’s nuclear energy secretary
Garrish
Theodore “Ted” Garrish—who has spent more than four decades working in nuclear—is President Donald Trump’s nominee to serve as the Department of Energy’s assistant secretary for nuclear energy, or, NE-1.
The nomination was referred to the U.S. Senate’s Committee on Energy and Natural Resources on February 3. Garrish previously held the office from 1987 to 1989 under President Ronald Reagan. Most recently, Kathryn Huff held the NE-1 post, and Michael Goff has served as interim assistant secretary since Huff stepped down in May 2024.
Garrish’s most recent term in public office was as assistant secretary for the Office of International Affairs at the Energy Department, from 2018 to 2021, during Trump’s first term. Supporters say Garrish’s 40-plus years working in the nuclear industry and in nuclear energy oversight positions makes him more than qualified to serve in the DOE office again.
Minoru Yamada, Ikuo Kinoshita, Toshihide Torige, Michio Murase, Yoshitaka Yoshida, Hideo Nakamura
Nuclear Technology | Volume 200 | Number 2 | November 2017 | Pages 125-143
Technical Paper | doi.org/10.1080/00295450.2017.1362940
Articles are hosted by Taylor and Francis Online.
Application of the statistical safety evaluation method to the analysis for reflux cooling in the loss of residual heat removal system (RHR) event during mid-loop operation was conducted with RELAP5/MOD3.2 as the best-estimate code. The evaluation parameters for this event are the reactor coolant system (RCS) pressure and reactor vessel (RV) water level. A phenomena identification and ranking table was developed previously to identify important phenomena that have a large influence on the evaluation parameters. The uncertainties of the analytical models which are related to the important phenomena were quantified to use as input for the statistical analysis. Actual plant sensitivity analyses were carried out to confirm the influence of the uncertainty which was quantified. Validation analysis of the RELAP5/MOD3.2 code was carried out for the reflux cooling test conducted with the ROSA-IV Large-Scale Test Facility to confirm that the experimental RCS pressure results were within the range of the uncertainty of the analytical models. A statistical analysis for 93 cases was carried out for a four-loop plant to evaluate the RV water level in the steady state and the maximum RCS pressure with 95% cumulative probability and 95% confidence. As a result, it was confirmed that reflux cooling using two cooling steam generators was successful.