Estimation of coping time in pressurized water reactors for accident tolerant fuel claddings

Estimation of coping time in pressurized water reactors for accident tolerant fuel claddings

Thesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 2018.

Bibliographic Details
Main Author:	Gurgen, Anil
Other Authors:	Koroush Shirvan.
Format:	Thesis
Language:	eng
Published:	Massachusetts Institute of Technology 2018
Subjects:	Nuclear Science and Engineering.
Online Access:	http://hdl.handle.net/1721.1/119048

Similar Items

Impact of reactor environment on quenching heat transfer of accident tolerant fuel cladding
by: Seshadri, Arunkumar.
Published: (2019)

Wettability of candidate Accident Tolerant Fuel (ATF) cladding materials in LWR conditions
by: Jena, Anupam,S.M.Massachusetts Institute of Technology.
Published: (2020)

Fuel performance of multi-layered zirconium and silicon carbide based Accident Tolerant Fuel claddings
by: Wagih, Malik Mamoon AbdelHalim
Published: (2018)

Quantifying the fouling resistance of Accident-Tolerant Fuel (ATF) cladding coatings with force spectroscopy
by: Auguste, Rasheed
Published: (2017)

Safety of light water reactor fuel with silicon carbide cladding
by: Lee, Youho
Published: (2014)

Silicon carbide performance as cladding for advanced uranium and thorium fuels for light water reactors
by: Sukjai, Yanin
Published: (2014)

Stainless steel clad for light water reactor fuels
by: Rivera, John E., et al.
Published: (2011)

Development of Cr cold spray–coated fuel cladding with enhanced accident tolerance
by: Champagne, Victor, et al.
Published: (2018)

Reactor physics assessment of thick silicon carbide clad PWR fuels
by: Bloore, David A. (David Allan)
Published: (2013)

An inverted hydride-fueled pressurized water reactor concept
by: Ferroni, Paolo, Ph. D. Massachusetts Institute of Technology
Published: (2010)

Wettability and CHF limits of Accident-Tolerant nuclear fuel cladding materials in light water reactor conditions
by: Su, GY, et al.
Published: (2023)

System code evaluation of near-term accident tolerant claddings during pressurized water reactor station blackout accidents
by: Jin, Yue, et al.
Published: (2023)

An assessment of silicon carbide as a cladding material for light water reactors
by: Carpenter, David Michael
Published: (2013)

Analysis and optimization of a new accident tolerant fuel called fuel-in-fibers
by: Hiscox, Briana (Briana Diane)
Published: (2018)

Innovative fuel designs for high power density pressurized water reactor
by: Feng, Dandong, Ph. D. Massachusetts Institute of Technology
Published: (2008)

Application of advanced fuel concepts for use in innovative pressurized water reactors
by: Andrews, Nathan Christopher
Published: (2016)

Prediction of peak cladding temperature in a three-loop pressurised water reactor with accident- tolerant fuel during loss-of-coolant accident
by: Agung, Alexander
Published: (2018)

Achievable power uprates in pressurized water reactors using uranium nitride fuel
by: Giudicelli, Guillaume
Published: (2017)

Assessing thermo-mechanical performance of ThO₂ and SiC clad light water reactor fuel rods with a modular simulation tool
by: Mieloszyk, Alexander James
Published: (2016)

Materials testing and development of functionally graded composite fuel cladding and piping for the Lead-Bismuth cooled nuclear reactor
by: Fray, Elliott Shepard
Published: (2013)

CRUD resistant fuel cladding materials
by: Paramonova, Ekaterina (Ekaterina D.)
Published: (2013)

Reactor dosimetry : dosimetry methods for fuels, cladding and structural materials /
by: ASTM-Euratom Symposium on Reactor Dosimetry (5th : 1984 : GKSS Research Centre, Geesthacht), et al.
Published: (1985)

Quality assurance and control in the manufacture of metal-clad UO2 reactor fuels /
by: 7924 International Atomic Energy Agency

Development of an experimental technique to investigate droplet cooling phenomena on accident tolerant fuel materials
by: McGhee, Warner(Warner A.)
Published: (2020)

Improved and Innovative Accident-Tolerant Nuclear Fuel Materials Considered for Retrofitting Light Water Reactors—A Review
by: Raul B. Rebak
Published: (2023-08-01)

Applicability of Swaging as an Alternative for the Fabrication of Accident-Tolerant Fuel Cladding
by: Dae Yun Kim, et al.
Published: (2020-06-01)

Design optimization of advanced PWR SiC/SiC fuel cladding for enhanced tolerance of loss of coolant conditions
by: Guenoun, Pierre, S.M. Massachusetts Institute of Technology
Published: (2016)

Optimization of hydride fueled pressurized water reactor cores
by: Shuffler, Carter Alexander
Published: (2006)

Evaluation of multilayer silicon carbide composite cladding under loss of coolant accident conditions
by: Daines, Gregory Welch
Published: (2016)

Reactor physics considerations for implementing silicon carbide cladding into a PWR environment
by: Dobisesky, Jacob P. (Jacob Paul), 1987-
Published: (2013)

Study of chemistry and irradiation effects on nanofluids to be used in light water reactor accident cooling
by: Lucas, Timothy R
Published: (2009)

Impact assessment for the MIT Research Reactor low enrichment uranium fuel fabrication tolerances
by: Allen, Dakota J.
Published: (2020)

Actinide minimization using pressurized water reactors
by: Visosky, Mark Michael
Published: (2008)

Hydrogen entry in Zircaloy-4 fuel cladding : an electrochemical study
by: Jarvis, Jennifer Anne
Published: (2016)

Preventing fuel failure for a beyond design basis accident in a fluoride salt cooled high temperature reactor
by: Minck, Matthew J. (Matthew Joseph)
Published: (2014)

Transient analysis of hydride fueled pressurized water reactor cores
by: Trant, Jarrod Michael
Published: (2006)

Chemical interaction layer between uranium oxide fuel pellet and zirconium alloy cladding in pressurized water reactor
by: WANG Huacai, et al.
Published: (2023-09-01)

Conceptual design of an annular-fueled superheat boiling water reactor
by: Ko, Yu-Chih, Ph. D. Massachusetts Institute of Technology
Published: (2013)

Development Status of Accident-tolerant Fuel for Light Water Reactors in Korea
by: Hyun-Gil Kim, et al.
Published: (2016-02-01)

Characterization and mitigation of crud at pressurized water reactor conditions
by: Dumnernchanvanit, Ittinop
Published: (2018)