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Title: Completely automated nuclear reactors for long-term operation II: toward a conceptual-level point design of a high-temperature, gas-cooled central power station system

Conference ·
OSTI ID:442215
; ;  [1]; ;  [2]
  1. Stanford Univ., CA (United States)
  2. Lawrence Livermore National Lab., CA (United States)

We discuss a new type of nuclear fission power reactor optimized for the generation of heat for use in obviously safe, economic, and long- duration electricity production in large central power stations. These reactors are fundamentally different in design, implementation, and operation from conventional light-water-cooled and- moderated reactors (LWRs) currently in widespread use. they feature a low- average-enrichment initial fuel loading which lasts the entire 30 year, full-power design life of the power plant, and which is intended never to be removed from the reactor. The reactor contains a cylindrical core comprised of a nuclear ignitor and a much larger nuclear [breeding + burning] wave propagating region containing natural thorium or uranium fuel, a surrounding neutron reflector and radiation shield, distributed means for implementing a thermostating function on the reactivity and local power density, a redundant pressurized gas coolant transport system, and automatic and redundant heat dumping means to obviate concerns regarding all classes of loss-of-coolant accidents during the plants operational and post operational life. These reactors are proposed to be situated at {>=}100 meter depths underground. There operation will be completely automatic, with no powered mechanisms, no operator controls and no provision for human access during or after their operational lifetime, in order to avoid both error and misuse. The power plant`s heat engine and electrical generator sub-systems are located above ground and are connected to the nuclear heat source only with readily sealed coolant conduits. This paper outlines a concept level point design of a 1 GWe member of this type of reactor, one oriented to production of high temperature, high pressure coolant gas and directed towards 60% efficiency, combined-cycle electricity generation.

Research Organization:
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Sponsoring Organization:
USDOE, Washington, DC (United States)
DOE Contract Number:
W-7405-ENG-48
OSTI ID:
442215
Report Number(s):
UCRL-JC-122708-Pt.2; CONF-9606224-3; ON: DE96050503
Resource Relation:
Conference: ICENES `96: emerging nuclear energy systems, Obninsk (Russian Federation), Jun 1996; Other Information: PBD: Jun 1996
Country of Publication:
United States
Language:
English