Molten-salt-cooled advanced high-temperature reactor for production of hydrogen and electricity

被引:226
作者
Forsberg, CW
机构
[1] Oak Ridge Natl Lab, Div Chem Technol, Oak Ridge, TN 37831 USA
[2] Univ Calif Berkeley, Berkeley, CA 94720 USA
[3] Sandia Natl Labs, Albuquerque, NM 87185 USA
关键词
molten salt; high-temperature reactor; hydrogen production;
D O I
10.13182/NT03-1
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 [核科学与技术]; 082701 [核能科学与工程];
摘要
The molten-salt-cooled Advanced High-Temperature Reactor (AHTR) is a new reactor concept designed to provide very high-temperature (750 to 1000degreesC) heat to enable efficient low-cost thermochemical production of hydrogen (H-2) or production of electricity. This paper provides an initial description and technical analysis of its key features. The proposed AHTR uses coated-particle graphite-matrix fuel similar to that used in high-temperature gas-cooled reactors (HTGRs), such as the General Atomics gas turbine-modular helium reactor. However, unlike the HTGRs, the AHTR uses a molten-salt coolant and a pool configuration, similar to that of the General Electric Super Power Reactor Inherently Safe Module (S-PRISM) liquid-metal reactor. Because the boiling points for molten fluoride salts are near similar to1400degreesC, the reactor can operate at very high temperatures and atmospheric pressure. For thermochemical H-2 production, the heat is delivered at the required near-constant high temperature and low pressure. For electricity production, a multireheat helium Brayton (gas-turbine) cycle, with efficiencies >50%, is used. The low-pressure molten-salt coolant, with its high heat capacity and natural circulation heat transfer capability, creates the potential for robust safety (including fully passive decay-heat removal) and improved economics with passive safety systems that allow higher power densities and scaling to large reactor sizes [>1000 MW(electric)].
引用
收藏
页码:289 / 302
页数:14
相关论文
共 24 条
[1]
BOARDMAN CE, 2000, 8 INT C NUCL ENG BAL
[2]
BROWN CL, 2000, GAA23451
[3]
Emergency decay heat removal by reactor vessel auxiliary cooling system from an accelerator-driven system [J].
Carlsson, J ;
Wider, H .
NUCLEAR TECHNOLOGY, 2002, 140 (01) :28-40
[4]
Del Cul G.D., 2002, P 13 INT S MOLT SALT
[5]
DEVAN JH, 1995, P INT C ACC DRIV TRA
[6]
EL-WAKIL M. M., 1971, NUCL ENERGY CONVERSI
[7]
Forsberg CW, 2003, INT J HYDROGEN ENERG, V28, P1073
[8]
FORSBERG CW, 2001, NUCL NEWS, V44, P41
[9]
Forster SM, 2002, ANN RPT BEAN IMPROV, V45, P30
[10]
Fraas A. P., 1956, ORNL2095