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Title: Process heat reactor design and analysis. Final report. [HTGR]

Abstract

The report presents the results of a study performed for the Department of Energy to initiate the concept definition phase of an HTGR-based nuclear process heat source development program. Alternate conceptual arrangements for an 842-MW(t) Very High Temperature Gas-Cooled Reactor (VHTR) are described and evaluated. Development of a VHTR parametric design computer code to guide and support nuclear system and process plant definitions and parameter selections is also discussed. The conceptual plant designs for six alternate plant configurations are presented in detail. These designs are evaluated with respect to feasibility, engineering design, economics, safety, reliability, and development considerations. The selected design is a two-loop plant with separate secondary helium loops to transport heat to externally located reformers. The plant has intermediate heat exchangers mounted in side wall cavities. Requirements and criteria are given for the major systems and components.

Publication Date:
Research Org.:
General Atomic Co., San Diego, CA (USA)
OSTI Identifier:
6159496
Report Number(s):
GA-A-15137
TRN: 79-009006
DOE Contract Number:  
EY-76-C-03-0167-061
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; HTGR TYPE REACTORS; DESIGN; PROCESS HEAT REACTORS; ECONOMICS; PLANNING; REACTOR COMPONENTS; SPECIFICATIONS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; REACTORS; 210900* - Nuclear Power Plants- Process Heat Reactors- (-1987); 210300 - Power Reactors, Nonbreeding, Graphite Moderated

Citation Formats

Not Available. Process heat reactor design and analysis. Final report. [HTGR]. United States: N. p., 1979. Web.
Not Available. Process heat reactor design and analysis. Final report. [HTGR]. United States.
Not Available. Thu . "Process heat reactor design and analysis. Final report. [HTGR]". United States.
@article{osti_6159496,
title = {Process heat reactor design and analysis. Final report. [HTGR]},
author = {Not Available},
abstractNote = {The report presents the results of a study performed for the Department of Energy to initiate the concept definition phase of an HTGR-based nuclear process heat source development program. Alternate conceptual arrangements for an 842-MW(t) Very High Temperature Gas-Cooled Reactor (VHTR) are described and evaluated. Development of a VHTR parametric design computer code to guide and support nuclear system and process plant definitions and parameter selections is also discussed. The conceptual plant designs for six alternate plant configurations are presented in detail. These designs are evaluated with respect to feasibility, engineering design, economics, safety, reliability, and development considerations. The selected design is a two-loop plant with separate secondary helium loops to transport heat to externally located reformers. The plant has intermediate heat exchangers mounted in side wall cavities. Requirements and criteria are given for the major systems and components.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1979},
month = {2}
}

Technical Report:
Other availability
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