Published 1986
| Version v1
Book
Fuel management nodal model validation for the Maine Yankee Atomic Power Station
Creators
- 1. Yankee Atomic Electric Co., 1671 Worcester Road, Framingham, MA 01701
Description
A physics nodal model employing the CASMO and SIMULATE codes has been validated for future cycle predictions of a full range of core physics parameters. Comparisons to both plant-measured and reload licensing calculated parameters for Maine Yankee Cycles 6 through 9 provide confidence in the predictive capabilities of the model. These cycles comprised changes in reload enrichment, a reconfigured control rod pattern and a transition from traditional OUT-IN to low-fluence and low-leakage core loading patterns. Despite these design obstacles, the model has provided sufficient physics parameter accuracy to establish core loading patterns and identify physics parameter changes which could impact core reload licensing
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- La Grange Park, IL (USA)
- ISBN
- 0-89448-123-1
- Imprint Title
- Proceedings of the topical meeting on advances in fuel management
- Journal Page Range
- p. 473-481.
Conference
- Title
- Topical meeting on advances in fuel management.
- Dates
- 2-5 Mar 1986.
- Place
- Pinehurst, NC (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18070153
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCURACY; C CODES; COMPUTERIZED SIMULATION; CONFIGURATION; FUEL CYCLE; FUEL MANAGEMENT; ISOTOPE SEPARATION; MAINE YANKEE REACTOR; NEUTRON FLUENCE; NEUTRON LEAKAGE; REACTOR FUELING; REACTOR KINETICS; REACTOR LICENSING; S CODES
- Descriptors DEC
- COMPUTER CODES; ENRICHED URANIUM REACTORS; KINETICS; LICENSING; MANAGEMENT; NUCLEAR MATERIALS MANAGEMENT; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SEPARATION PROCESSES; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS