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Featured researches published by Philip L. Winston.


ASME 2005 Pressure Vessels and Piping Conference | 2005

The Long-Term Performance of Concrete in Nuclear Applications

Denzel L. Fillmore; Philip L. Winston; Sheryl L. Morton; Cecelia R. Hoffman; Leo A. Van Ausdeln; Toshiari Saegusa; Koji Shirai; Takatoshi Hattori; Akihiro Sasahara

The Idaho National Laboratory investigated long-term concrete performance for nuclear applications. Scientists searched the open literature for information on the effects of heat and radiation. They also examined the concrete shield of the Pacific Sierra Nuclear Ventilated Storage Cask (VSC-17) for concrete deterioration and loss of shielding. The literature search revealed that low doses, <109 n/cm2 or <1011 Rad gamma, of radiation over periods less than 50 years do not appear to significantly affect concrete. Exposure over 100 years was not studied. The effects of higher doses of radiation are not as clear. Generally, the threshold of degradation is 95°C, and degradation increases with increasing temperature and time. In 15 years of VSC-17 use, there is no apparent effect from environment, radiation, or temperature that has adversely affected the shielding or structural functions, although there has been some minor cracking of the concrete.© 2005 ASME


Nuclear Engineering and Design | 2016

Irradiation performance of AGR-1 high temperature reactor fuel

Paul A. Demkowicz; John D. Hunn; Scott A. Ploger; Robert Noel Morris; Charles A. Baldwin; Jason M. Harp; Philip L. Winston; Tyler J. Gerczak; Isabella J. van Rooyen; Fred C. Montgomery; Chinthaka M. Silva


Archive | 2012

Preliminary Results of Post-Irradiation Examination of the AGR-1 TRISO Fuel Compacts

Paul A. Demkowicz; John D. Hunn; Robert Noel Morris; Jason M. Harp; Philip L. Winston; Charles A. Baldwin; Fred C. Montgomery; Scott A. Ploger; Isabella J. van Rooyen


Nuclear Engineering and Design | 2014

An analysis of nuclear fuel burnup in the AGR-1 TRISO fuel experiment using gamma spectrometry, mass spectrometry, and computational simulation techniques

Jason M. Harp; Paul A. Demkowicz; Philip L. Winston; James W. Sterbentz


Archive | 2013

Analysis of Fission Products on the AGR-1 Capsule Components

Paul A. Demkowicz; Jason M. Harp; Philip L. Winston; Scott A. Ploger


Archive | 2011

AGR-1 Irradiated Test Train Preliminary Inspection and Disassembly First Look

Paul A. Demkowicz; Lance Cole; Scott A. Ploger; Philip L. Winston; Binh T. Pham; Michael L. Abbott


2006 International High Level Radioactive Waste Management Conference,Las Vegas, NV,04/30/2006,05/04/2006 | 2006

Concrete Shield Performance of the VSC-17 Spent Nuclear Fuel Cask

Sheryl L. Morton; Philip L. Winston; Toshiari Saegusa; Koji Shirai; Akihiro Sasahara; Takatoshi Hattori


Archive | 2016

AGR-1 Compact 4-1-1 Post-Irradiation Examination Results

Paul A. Demkowicz; Jason M. Harp; Philip L. Winston; Scott A. Ploger; Isabella J. van Rooyen


Archive | 2012

Preliminary Evaluation of Fission Product Release from AGR-1 Coated Particles

Paul A. Demkowicz; John D. Hunn; Robert Noel Morris; Jason M. Harp; Charles A. Baldwin; Philip L. Winston; Scott A. Ploger; Fred C. Montgomery


Archive | 2016

AGR-3/4 Irradiation Test Train Disassembly and Component Metrology First Look Report

John D. Stempien; Francine J. Rice; Jason M. Harp; Philip L. Winston

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Jason M. Harp

Idaho National Laboratory

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Scott A. Ploger

Idaho National Laboratory

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Charles A. Baldwin

Oak Ridge National Laboratory

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Fred C. Montgomery

Oak Ridge National Laboratory

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John D. Hunn

Oak Ridge National Laboratory

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Robert Noel Morris

Oak Ridge National Laboratory

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Koji Shirai

Central Research Institute of Electric Power Industry

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Toshiari Saegusa

Central Research Institute of Electric Power Industry

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