Development of Safety Analysis Codes and Experimental Validation for a Very High Temperature Gas-Cooled Reactor - FY-05 Annual Report

Development of Safety Analysis Codes and Experimental Validation for a Very High Temperature Gas-Cooled Reactor - FY-05 Annual Report
Author :
Publisher :
Total Pages :
Release :
ISBN-10 : OCLC:316325296
ISBN-13 :
Rating : 4/5 (96 Downloads)

Book Synopsis Development of Safety Analysis Codes and Experimental Validation for a Very High Temperature Gas-Cooled Reactor - FY-05 Annual Report by : Chang Oh

Download or read book Development of Safety Analysis Codes and Experimental Validation for a Very High Temperature Gas-Cooled Reactor - FY-05 Annual Report written by Chang Oh and published by . This book was released on 2005 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The very high temperature gas-cooled reactors (VHTGRs) are those concepts that have average coolant temperatures above 9000C or operational fuel temperatures above 12500C. These concepts provide thepotential for increased energy conversion efficiency and for high-temperature process heat application in addition to power generation and nuclear hydrogen generation. While all the High Temperature Gas Cooled Reactor (HTGR) concepts have sufficiently high temperatures to support process heat applications, such as desalination and cogeneration, the VHTGR's higher temperatures are suitable for particular applications such as thermochemical hydrogen production. However, the high temperature operation can be detrimental to safety following a loss-of-coolant accident (LOCA) initiated by pipe breaks caused by seismic or other events. Following the loss of coolant through the break and coolant depressurization, air from the containment will enter the core by molecular diffusion and ultimately by natural convection, leading to oxidation of the in-core graphite structures and fuel. The oxidation will release heat and accelerate the heatup of the reactor core. Thus, without any effective countermeasures, a pipe break may lead to significant fuel damage and fission product release. The Idaho National Laboratory (INL) has investigated this event for the past three years forthe HTGR. However, the computer codes used, and in fact none of the world's computer codes, have been sufficiently developed and validated to reliably predict this event. New code development, improvement of the existing codes, and experimental validation are imperative to narrow the uncertainty in the predictions of this type of accident. The objectives of this Korean/United States collaboration are to develop advanced computational methods for VHTGR safety analysis codes and to validate these computer codes.


Development of Safety Analysis Codes and Experimental Validation for a Very High Temperature Gas-Cooled Reactor - FY-05 Annual Report Related Books

Development of Safety Analysis Codes and Experimental Validation for a Very High Temperature Gas-Cooled Reactor - FY-05 Annual Report
Language: en
Pages:
Authors: Chang Oh
Categories:
Type: BOOK - Published: 2005 - Publisher:

DOWNLOAD EBOOK

The very high temperature gas-cooled reactors (VHTGRs) are those concepts that have average coolant temperatures above 9000C or operational fuel temperatures ab
Development of Safety Analysis Codes and Experimental Validation for a Very High Temperature Gas-Cooled Reactor
Language: en
Pages:
Authors:
Categories:
Type: BOOK - Published: 2004 - Publisher:

DOWNLOAD EBOOK

The very high temperature gas-cooled reactors (VHTGRs) are those concepts that have average coolant temperatures above 900 degrees C or operational fuel tempera
Development of Safety Analysis Codes and Experimental Validation for a Very High Temperature Gas-cooled Reactor Final Report
Language: en
Pages:
Authors: Chang Oh
Categories:
Type: BOOK - Published: 2006 - Publisher:

DOWNLOAD EBOOK

The very high-temperature gas-cooled reactor (VHTR) is envisioned as a single- or dual-purpose reactor for electricity and hydrogen generation. The concept has
Validation of SCALE for High Temperature Gas-Cooled Reactors Analysis
Language: en
Pages:
Authors:
Categories:
Type: BOOK - Published: 2012 - Publisher:

DOWNLOAD EBOOK

This report documents verification and validation studies carried out to assess the performance of the SCALE code system methods and nuclear data for modeling a
High-temperature Gas-cooled Reactor Safety Studies for the Division of Reactor Safety Research Quarterly Progress Report
Language: en
Pages: 30