Preliminary materials selection issues for the next generation nuclear plant reactor pressure vessel.

Natesan, K; Majumdar, S; Shankar, P S; Shah, V N

doi:10.2172/925328

Title: Preliminary materials selection issues for the next generation nuclear plant reactor pressure vessel.

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Abstract

In the coming decades, the United States and the entire world will need energy supplies to meet the growing demands due to population increase and increase in consumption due to global industrialization. One of the reactor system concepts, the Very High Temperature Reactor (VHTR), with helium as the coolant, has been identified as uniquely suited for producing hydrogen without consumption of fossil fuels or the emission of greenhouse gases [Generation IV 2002]. The U.S. Department of Energy (DOE) has selected this system for the Next Generation Nuclear Plant (NGNP) Project, to demonstrate emissions-free nuclear-assisted electricity and hydrogen production within the next 15 years. The NGNP reference concepts are helium-cooled, graphite-moderated, thermal neutron spectrum reactors with a design goal outlet helium temperature of {approx}1000 C [MacDonald et al. 2004]. The reactor core could be either a prismatic graphite block type core or a pebble bed core. The use of molten salt coolant, especially for the transfer of heat to hydrogen production, is also being considered. The NGNP is expected to produce both electricity and hydrogen. The process heat for hydrogen production will be transferred to the hydrogen plant through an intermediate heat exchanger (IHX). The basic technology for the NGNP hasmore »« less

Authors:: Natesan, K; Majumdar, S; Shankar, P S; Shah, V N

Publication Date:: Wed Mar 21 00:00:00 EDT 2007

Research Org.:: Argonne National Lab. (ANL), Argonne, IL (United States)

Sponsoring Org.:: NE

OSTI Identifier:: 925328

Report Number(s):: ANL/EXT-06-45
TRN: US200809%%749

DOE Contract Number:: DE-AC02-06CH11357

Resource Type:: Technical Report

Country of Publication:: United States

Language:: ENGLISH

Subject:: 08 HYDROGEN; 29 ENERGY PLANNING, POLICY AND ECONOMY; DEMONSTRATION PLANTS; DESIGN; ELECTRICITY; ENERGY SUPPLIES; FOSSIL FUELS; GRAPHITE; GREENHOUSE GASES; HEAT EXCHANGERS; HELIUM; HYDROGEN; HYDROGEN PRODUCTION; MOLTEN SALTS; PRESSURE VESSELS; PROCESS HEAT; REACTOR CORES; TEST REACTORS; THERMAL NEUTRONS

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                    Natesan, K, Majumdar, S, Shankar, P S, Shah, V N, and Nuclear Engineering Division. Preliminary materials selection issues for the next generation nuclear plant reactor pressure vessel..  United States: N. p., 2007. 
        Web.  doi:10.2172/925328.

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                    Natesan, K, Majumdar, S, Shankar, P S, Shah, V N, & Nuclear Engineering Division. Preliminary materials selection issues for the next generation nuclear plant reactor pressure vessel..  United States.  https://doi.org/10.2172/925328

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                    Natesan, K, Majumdar, S, Shankar, P S, Shah, V N, and Nuclear Engineering Division. 2007.  
        "Preliminary materials selection issues for the next generation nuclear plant reactor pressure vessel.".  United States.  https://doi.org/10.2172/925328.  https://www.osti.gov/servlets/purl/925328.

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@article{osti_925328,

  title        = {Preliminary materials selection issues for the next generation nuclear plant reactor pressure vessel.},

  author       = {Natesan, K and Majumdar, S and Shankar, P S and Shah, V N and Nuclear Engineering Division},

  abstractNote = {In the coming decades, the United States and the entire world will need energy supplies to meet the growing demands due to population increase and increase in consumption due to global industrialization. One of the reactor system concepts, the Very High Temperature Reactor (VHTR), with helium as the coolant, has been identified as uniquely suited for producing hydrogen without consumption of fossil fuels or the emission of greenhouse gases [Generation IV 2002]. The U.S. Department of Energy (DOE) has selected this system for the Next Generation Nuclear Plant (NGNP) Project, to demonstrate emissions-free nuclear-assisted electricity and hydrogen production within the next 15 years. The NGNP reference concepts are helium-cooled, graphite-moderated, thermal neutron spectrum reactors with a design goal outlet helium temperature of {approx}1000 C [MacDonald et al. 2004]. The reactor core could be either a prismatic graphite block type core or a pebble bed core. The use of molten salt coolant, especially for the transfer of heat to hydrogen production, is also being considered. The NGNP is expected to produce both electricity and hydrogen. The process heat for hydrogen production will be transferred to the hydrogen plant through an intermediate heat exchanger (IHX). The basic technology for the NGNP has been established in the former high temperature gas reactor (HTGR) and demonstration plants (DRAGON, Peach Bottom, AVR, Fort St. Vrain, and THTR). In addition, the technologies for the NGNP are being advanced in the Gas Turbine-Modular Helium Reactor (GT-MHR) project, and the South African state utility ESKOM-sponsored project to develop the Pebble Bed Modular Reactor (PBMR). Furthermore, the Japanese HTTR and Chinese HTR-10 test reactors are demonstrating the feasibility of some of the planned components and materials. The proposed high operating temperatures in the VHTR place significant constraints on the choice of material selected for the reactor pressure vessel for both the PBMR and prismatic design. The main focus of this report is the RPV for both design concepts with emphasis on material selection.},

  doi          = {10.2172/925328},

  url          = {https://www.osti.gov/biblio/925328},
  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {Wed Mar 21 00:00:00 EDT 2007},

  month        = {Wed Mar 21 00:00:00 EDT 2007}

}

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