skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Development status and potential program for development of proliferation-resistant molten-salt reactors

Abstract

Preliminary studies of existing and conceptual molten-salt reactor (MSR) designs have led to the identification of conceptual systems that are technologically attractive when operated with denatured uranium as the principal fissile fuel. These denatured MSRs would also have favorable resource-utilization characteristics and substantial resistance to proliferation of weapons-usable nuclear materials. The report presents a summary of the current status of technology and a discussion of the major technical areas of a possible base program to develop commercial denatured MSRs. The general areas treated are (1) reactor design and development, (2) safety and safety related technology, (3) fuel-coolant behavior and fuel processing, and (4) reactor materials. A substantial development effort could lead to authorization for construction of a molten-salt test reactor about 5 years after the start of the program and operation of the unit about 10 years later. A prototype commercial denatured MSR could be expected to begin operating 25 years from the start of the program. The postulated base program would extend over 32 years and would cost about $700 million (1978 dollars, unescalated). Additional costs to construct the MSTR, $600 million, and the prototype commercial plant, $1470 million, would bring the total program cost to about $2.8 billion.more » Additional allowances probably should be made to cover contingencies and incidental technology areas not explicitly treated in this preliminary review.« less

Authors:
; ; ; ;
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
OSTI Identifier:
6368411
Report Number(s):
ORNL/TM-6415
TRN: 79-008998
DOE Contract Number:  
W-7405-ENG-26
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BREEDER REACTORS; PLANNING; MOLTEN SALT REACTORS; COST; DENATURED FUEL; DESIGN; FUEL CYCLE; REACTOR COMPONENTS; REACTOR CORES; ENERGY SOURCES; FUELS; NUCLEAR FUELS; REACTOR MATERIALS; REACTORS; 210500* - Power Reactors, Breeding

Citation Formats

Engel, J. R., Bauman, H. F., Dearing, J. F., Grimes, W. R., and McCoy, Jr., H. E. Development status and potential program for development of proliferation-resistant molten-salt reactors. United States: N. p., 1979. Web. doi:10.2172/6368411.
Engel, J. R., Bauman, H. F., Dearing, J. F., Grimes, W. R., & McCoy, Jr., H. E. Development status and potential program for development of proliferation-resistant molten-salt reactors. United States. https://doi.org/10.2172/6368411
Engel, J. R., Bauman, H. F., Dearing, J. F., Grimes, W. R., and McCoy, Jr., H. E. 1979. "Development status and potential program for development of proliferation-resistant molten-salt reactors". United States. https://doi.org/10.2172/6368411. https://www.osti.gov/servlets/purl/6368411.
@article{osti_6368411,
title = {Development status and potential program for development of proliferation-resistant molten-salt reactors},
author = {Engel, J. R. and Bauman, H. F. and Dearing, J. F. and Grimes, W. R. and McCoy, Jr., H. E.},
abstractNote = {Preliminary studies of existing and conceptual molten-salt reactor (MSR) designs have led to the identification of conceptual systems that are technologically attractive when operated with denatured uranium as the principal fissile fuel. These denatured MSRs would also have favorable resource-utilization characteristics and substantial resistance to proliferation of weapons-usable nuclear materials. The report presents a summary of the current status of technology and a discussion of the major technical areas of a possible base program to develop commercial denatured MSRs. The general areas treated are (1) reactor design and development, (2) safety and safety related technology, (3) fuel-coolant behavior and fuel processing, and (4) reactor materials. A substantial development effort could lead to authorization for construction of a molten-salt test reactor about 5 years after the start of the program and operation of the unit about 10 years later. A prototype commercial denatured MSR could be expected to begin operating 25 years from the start of the program. The postulated base program would extend over 32 years and would cost about $700 million (1978 dollars, unescalated). Additional costs to construct the MSTR, $600 million, and the prototype commercial plant, $1470 million, would bring the total program cost to about $2.8 billion. Additional allowances probably should be made to cover contingencies and incidental technology areas not explicitly treated in this preliminary review.},
doi = {10.2172/6368411},
url = {https://www.osti.gov/biblio/6368411}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Mar 01 00:00:00 EST 1979},
month = {Thu Mar 01 00:00:00 EST 1979}
}