Nodal formulation relating assembly power and reactivity
Creators
- 1. Massachusetts Institute of Technology, Cambridge
Description
Although nodal methods for light water reactor physics calculations have long been part of the fuel manager's repertoire, most involve computation of the neutron flux given cross-section data as input. Work at the Massachusetts Institute of Technology by a number of students over the past several years has shown that it is sometimes advantageous to formulate nodal relations that directly compute node (e.g., assembly) average power given reactivity as input. For example, since (poison-free) reactivity is, to an excellent approximation, a linear function of burnup, a nodel model of this type is ideally suited as a module in core reload optimization computations, since they typically require many rapid calculations shuttling back and forth between the beginning and end of cycle for a variety of loading patterns. The approach is also particularly useful for teaching purposes
Additional details
Publishing Information
- Journal Title
- Trans. Am. Nucl. Soc.
- Journal Volume
- 50
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 86-88
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- American Nuclear Society winter meeting.
- Dates
- 10-15 Nov 1985.
- Place
- San Francisco, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17083189
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNABLE POISONS; BURNUP; BWR TYPE REACTORS; COMPUTER CODES; FUEL ASSEMBLIES; FUEL MANAGEMENT; NEUTRON ABSORBERS; NEUTRON FLUX; POWER DENSITY; PWR TYPE REACTORS; REACTIVITY; REACTOR KINETICS
- Descriptors DEC
- ENRICHED URANIUM REACTORS; KINETICS; MANAGEMENT; MATERIALS; NUCLEAR MATERIALS MANAGEMENT; NUCLEAR POISONS; POWER REACTORS; RADIATION FLUX; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-851115--.