The Mass Tracking System for the Integral Fast Reactor Fuel Cycle

Conference · Sun Jul 17 00:00:00 EDT 1994

OSTI ID:10167486

Adams, Cyrus H. ^[1]; Beitel, Jon C. ^[1]; Birgersson, Goran ^[1]; Bucher, Ronald G. ^[1]; Carrico, Chad B. ^[1]; Daly, Thomas A. ^[1]; Keyes, Roy W. ^[2]

---

1. Argonne National Lab. (ANL), Argonne, IL (United States)
2. Argonne National Lab., Idaho Falls, ID (United States)

As part of the Fuel Cycle Facility (FCF) of Argonne National Laboratory’s Integral Fast Reactor (IFR) demonstration, a computer-based Mass-Tracking (MTG) System has been developed. The MTG System collects, stores, retrieves and processes data on all operations which directly affect the flow of process material through FCF and supports such activities as process modeling, compliance with operating limits (e.g., criticality safety), material control and accountability and operational information services. Its architecture is client/server, with input and output connections to operator’s equipment-control stations on the floor of FCF as well as to terminal sessions. Its heterogeneous database includes a relational- database manager as well as both binary and ASCII data files. The design of the database, and the software that supports it, is based on a model of discrete accountable items distributed in space and time and constitutes a complete historical record of the material processed in FCF. Although still under development, much of the MTG System has been qualified and is in production use.

• Research Organization: Argonne National Lab. (ANL), Argonne, IL (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); USDOE Nuclear Energy Programs
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 10167486
• Report Number(s): ANL/RA/CP-83425; CONF-940748-7; ON: DE94015082; TRN: 94:014628
• Resource Relation: Conference: 35. Annual Meeting of the Institute of Nuclear Materials Management (INMM), Naples, FL (United States), 17-20 Jul 1994; Other Information: PBD: [1994]
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
97 MATHEMATICS AND COMPUTING
LIQUID METAL COOLED REACTORS
SPENT FUELS
REPROCESSING
FUEL REPROCESSING PLANTS
NUCLEAR MATERIALS MANAGEMENT
INFORMATION SYSTEMS
ANL
DATA BASE MANAGEMENT
MONITORING
DATA ACQUISITION
MEMORY DEVICES
INFORMATION RETRIEVAL
Nuclear Criticality Safety Program (NCSP)
Fuel Cycle Facility (FCF)
Mass-Tracking (MTG) System
Integral Fast Reactor (IFR)
American Standard Code for Information Interchange (ASCII)
Materials Control and Account (MC&A)
Programmable Logic Controllers (PLCs)
Operator Control Stations (OCSs)
055001
050800
210500
TECHNICAL ASPECTS
SPENT FUELS REPROCESSING
POWER REACTORS
BREEDING