Neutronic design studies for an unattended, low power reactor
Conference
·
OSTI ID:5466591
The Los Alamos National Laboratory is involved in the design and demonstrations of a small, long-lived nuclear heat and electric power source for potential applications at remote sites where alternate fossil energy systems would not be cost effective. This paper describes the neutronic design analysis that was performed to arrive at two conceptual designs, one using thermoelectric conversion, the other using an organic Rankine cycle. To meet the design objectives and constraints a number of scoping and optimization studies were carried out. The results of calculations of control worths, temperature coefficients of reactivity and fuel depletion effects are reported.
- Research Organization:
- Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 5466591
- Report Number(s):
- LA-UR-86-1879; CONF-860906-13; ON: DE86011228
- Resource Relation:
- Conference: Advances in reactor physics and safety meeting, Saratoga Springs, NY, USA, 17 Sep 1986; Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
Similar Records
Reactor physics methods, models, and applications used to support the conceptual design of the Advanced Neutron Source
REACTOR PHYSICS STUDIES FOR THE FINAL CONCEPTUAL DESIGN OF THE ADVANCED TEST REACTOR
Transformational challenge reactor analysis to inform preconceptual core design decisions: Sensitivity study of transient analysis in a hydride-moderated microreactor
Technical Report
·
Tue Aug 01 00:00:00 EDT 1995
·
OSTI ID:5466591
+3 more
REACTOR PHYSICS STUDIES FOR THE FINAL CONCEPTUAL DESIGN OF THE ADVANCED TEST REACTOR
Technical Report
·
Fri Mar 24 00:00:00 EST 1961
·
OSTI ID:5466591
Transformational challenge reactor analysis to inform preconceptual core design decisions: Sensitivity study of transient analysis in a hydride-moderated microreactor
Journal Article
·
Mon Mar 01 00:00:00 EST 2021
· Nuclear Engineering and Design
·
OSTI ID:5466591
+1 more
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
GRAPHITE MODERATED REACTORS
DESIGN
REACTOR CORES
REACTOR PHYSICS
POWER REACTORS
COMPUTERIZED SIMULATION
GRAPHITE
HEAT PIPES
POWER RANGE 10-100 KW
RANKINE CYCLE
THERMOELECTRIC CONVERSION
CARBON
CONVERSION
DIRECT ENERGY CONVERSION
ELEMENTAL MINERALS
ELEMENTS
ENERGY CONVERSION
MINERALS
NONMETALS
PHYSICS
REACTOR COMPONENTS
REACTORS
SIMULATION
THERMODYNAMIC CYCLES
210300* - Power Reactors
Nonbreeding
Graphite Moderated
210600 - Power Reactors
Auxiliary
Mobile Package
& Transportable
GRAPHITE MODERATED REACTORS
DESIGN
REACTOR CORES
REACTOR PHYSICS
POWER REACTORS
COMPUTERIZED SIMULATION
GRAPHITE
HEAT PIPES
POWER RANGE 10-100 KW
RANKINE CYCLE
THERMOELECTRIC CONVERSION
CARBON
CONVERSION
DIRECT ENERGY CONVERSION
ELEMENTAL MINERALS
ELEMENTS
ENERGY CONVERSION
MINERALS
NONMETALS
PHYSICS
REACTOR COMPONENTS
REACTORS
SIMULATION
THERMODYNAMIC CYCLES
210300* - Power Reactors
Nonbreeding
Graphite Moderated
210600 - Power Reactors
Auxiliary
Mobile Package
& Transportable