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Dive into the research topics where Fred J Peretz is active.

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Archive | 2011

Pre-Conceptual Design of a Fluoride-Salt-Cooled Small Modular Advanced High Temperature Reactor (SmAHTR)

S.R. Greene; Jess C Gehin; David Eugene Holcomb; Juan J. Carbajo; Dan Ilas; Anselmo T Cisneros; Venugopal Koikal Varma; W.R. Corwin; Dane F Wilson; Graydon L. Yoder; A L Qualls; Fred J Peretz; George F. Flanagan; Dwight A Clayton; Eric Craig Bradley; Gary L Bell; John D. Hunn; Peter J Pappano; Mustafa Sacit Cetiner

This document presents the results of a study conducted at Oak Ridge National Laboratory during 2010 to explore the feasibility of small modular fluoride salt-cooled high temperature reactors (FHRs). A preliminary reactor system concept, SmATHR (for Small modular Advanced High Temperature Reactor) is described, along with an integrated high-temperature thermal energy storage or salt vault system. The SmAHTR is a 125 MWt, integral primary, liquid salt cooled, coated particle-graphite fueled, low-pressure system operating at 700 C. The system employs passive decay heat removal and two-out-of-three , 50% capacity, subsystem redundancy for critical functions. The reactor vessel is sufficiently small to be transportable on standard commercial tractor-trailer transport vehicles. Initial transient analyses indicated the transition from normal reactor operations to passive decay heat removal is accomplished in a manner that preserves robust safety margins at all times during the transient. Numerous trade studies and trade-space considerations are discussed, along with the resultant initial system concept. The current concept is not optimized. Work remains to more completely define the overall system with particular emphasis on refining the final fuel/core configuration, salt vault configuration, and integrated system dynamics and safety behavior.


Archive | 2009

An Analysis of Testing Requirements for Fluoride Salt Cooled High Temperature Reactor Components

David Eugene Holcomb; Sacit M. Cetiner; George F. Flanagan; Fred J Peretz; Graydon L. Yoder

This report provides guidance on the component testing necessary during the next phase of fluoride salt-cooled high temperature reactor (FHR) development. In particular, the report identifies and describes the reactor component performance and reliability requirements, provides an overview of what information is necessary to provide assurance that components will adequately achieve the requirements, and then provides guidance on how the required performance information can efficiently be obtained. The report includes a system description of a representative test scale FHR reactor. The reactor parameters presented in this report should only be considered as placeholder values until an FHR test scale reactor design is completed. The report focus is bounded at the interface between and the reactor primary coolant salt and the fuel and the gas supply and return to the Brayton cycle power conversion system. The analysis is limited to component level testing and does not address system level testing issues. Further, the report is oriented as a bottom-up testing requirements analysis as opposed to a having a top-down facility description focus.


Archive | 2011

Advanced High Temperature Reactor Systems and Economic Analysis

David Eugene Holcomb; Fred J Peretz; A L Qualls

The Advanced High Temperature Reactor (AHTR) is a design concept for a large-output [3400 MW(t)] fluoride-salt-cooled high-temperature reactor (FHR). FHRs, by definition, feature low-pressure liquid fluoride salt cooling, coated-particle fuel, a high-temperature power cycle, and fully passive decay heat rejection. The AHTRs large thermal output enables direct comparison of its performance and requirements with other high output reactor concepts. As high-temperature plants, FHRs can support either high-efficiency electricity generation or industrial process heat production. The AHTR analysis presented in this report is limited to the electricity generation mission. FHRs, in principle, have the potential to be low-cost electricity producers while maintaining full passive safety. However, no FHR has been built, and no FHR design has reached the stage of maturity where realistic economic analysis can be performed. The system design effort described in this report represents early steps along the design path toward being able to predict the cost and performance characteristics of the AHTR as well as toward being able to identify the technology developments necessary to build an FHR power plant. While FHRs represent a distinct reactor class, they inherit desirable attributes from other thermal power plants whose characteristics can be studied to provide general guidance on plant configuration, anticipated performance, and costs. Molten salt reactors provide experience on the materials, procedures, and components necessary to use liquid fluoride salts. Liquid metal reactors provide design experience on using low-pressure liquid coolants, passive decay heat removal, and hot refueling. High temperature gas-cooled reactors provide experience with coated particle fuel and graphite components. Light water reactors (LWRs) show the potentials of transparent, high-heat capacity coolants with low chemical reactivity. Modern coal-fired power plants provide design experience with advanced supercritical-water power cycles. The current design activities build upon a series of small-scale efforts over the past decade to evaluate and describe the features and technology variants of FHRs. Key prior concept evaluation reports include the SmAHTR preconceptual design report,1 the PB-AHTR preconceptual design, and the series of early phase AHTR evaluations performed from 2004 to 2006. This report provides a power plant-focused description of the current state of the AHTR. The report includes descriptions and sizes of the major heat transport and power generation components. Component configuration and sizing are based upon early phase AHTR plant thermal hydraulic models. The report also provides a top-down AHTR comparative economic analysis. A commercially available advanced supercritical water-based power cycle was selected as the baseline AHTR power generation cycle both due to its superior performance and to enable more realistic economic analysis. The AHTR system design, however, has several remaining gaps, and the plant cost estimates consequently have substantial remaining uncertainty. For example, the enriched lithium required for the primary coolant cannot currently be produced on the required scale at reasonable cost, and the necessary core structural ceramics do not currently exist in a nuclear power qualified form. The report begins with an overview of the current, early phase, design of the AHTR plant. Only a limited amount of information is included about the core and vessel as the core design and refueling options are the subject of a companion report. The general layout of an AHTR system and site showing the relationship of the major facilities is then provided. Next is a comparative evaluation of the AHTR anticipated performance and costs. Finally, the major system design efforts necessary to bring the AHTR design to a pre-conceptual level are then presented.


Archive | 2012

Embedded Sensors and Controls to Improve Component Performance and Reliability Conceptual Design Report

Roger A. Kisner; Alexander M. Melin; Timothy A Burress; David Fugate; David Eugene Holcomb; J. B. Wilgen; John M Miller; Dane F Wilson; Pamela C Silva; Lynsie J Whitlow; Fred J Peretz

The overall project objective is to demonstrate improved reliability and increased performance made possible by deeply embedding instrumentation and controls (IC adequate performance was obtained through over-design. This report describes the progress and status of the project and provides a conceptual design overview for the embedded I&C pump.


Annals of Nuclear Energy | 2014

An experimental test facility to support development of the fluoride-salt-cooled high-temperature reactor

Graydon L. Yoder; Adam M Aaron; Burns Cunningham; David Fugate; David Eugene Holcomb; Roger A. Kisner; Fred J Peretz; Kevin R Robb; J. B. Wilgen; Dane F Wilson


Archive | 2012

AHTR Mechanical, Structural, And Neutronic Preconceptual Design

Venugopal Koikal Varma; David Eugene Holcomb; Fred J Peretz; Eric Craig Bradley; Dan Ilas; A L Qualls; Nathaniel M Zaharia


Archive | 2010

Development of a Forced-Convection Liquid-Fluoride-Salt Test Loop

Graydon L. Yoder; Dane F Wilson; Fred J Peretz; J. B. Wilgen; Glenn Romanoski; Roger A. Kisner; David Eugene Holcomb; Dennis Wayne Heatherly; Adam M Aaron


Archive | 2012

Current status of the advanced high temperature reactor

David Eugene Holcomb; D. Iias; A. L. Quails; Fred J Peretz; Venugopal Koikal Varma; Eric Craig Bradley; A. T. Cisneros


Archive | 2015

High Temperature Fluoride Salt Test Loop

Adam M Aaron; Richard Burns Cunningham; David Fugate; David Eugene Holcomb; Roger A. Kisner; Fred J Peretz; Kevin R Robb; Dane F Wilson; Graydon L. Yoder


Archive | 2011

AN EXPERIMENT TO STUDY PEBBLE BED LIQUID-FLUORIDE-SALT HEAT TRANSFER

Graydon L. Yoder; Adam M Aaron; Dennis Wayne Heatherly; David Eugene Holcomb; Roger A. Kisner; Mike McCarthy; Fred J Peretz; J. B. Wilgen; Dane F Wilson

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David Eugene Holcomb

Oak Ridge National Laboratory

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Graydon L. Yoder

Oak Ridge National Laboratory

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Dane F Wilson

Oak Ridge National Laboratory

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Roger A. Kisner

Oak Ridge National Laboratory

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Adam M Aaron

Oak Ridge National Laboratory

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J. B. Wilgen

Oak Ridge National Laboratory

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A L Qualls

Oak Ridge National Laboratory

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David Fugate

Oak Ridge National Laboratory

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Eric Craig Bradley

Oak Ridge National Laboratory

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George F. Flanagan

Oak Ridge National Laboratory

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