Published August 2014 | Version v1
Miscellaneous

Representing Operational Knowledge of PWR Plant by Using Multilevel Flow Modelling

  • 1. Technical University of Denmark, Lyngby (Denmark)
  • 2. Safepark Consultancy, Slangerup (Denmark)

Description

Abstract: The aim of this paper is to explore the capability of representing operational knowledge by using Multilevel Flow Modelling (MFM) methodology. The paper demonstrates how the operational knowledge can be inserted into the MFM models and be used to evaluate the plant state, identify the current situation and support operational decisions. This paper will provide a general MFM model of the primary side in a standard Westinghouse Pressurized Water Reactor (PWR) system including sub-systems of Reactor Coolant System, Rod Control System, Chemical and Volume Control System, emergency heat removal systems. And the sub-systems' functions will be decomposed into sub-models according to different operational situations. An operational model will be developed based on the operating procedure by using MFM symbols and this model can be used to implement coordination rules for organize the utilization of different MFM models in different situation. Combining the operational model and different process models, MFM can be used to identify plant situation

Part of:
ISOFIC/ISSNP 2014: International Symposium on Future I and C for Nuclear Power Plants/International Symposium on Symbiotic Nuclear Power Systems

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the ISOFIC/ISSNP 2014
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[10 p.]

Conference

Title
ISOFIC/ISSNP 2014
Dates
24-28 Aug 2014
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
46074490
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CONTROL SYSTEMS; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; REACTOR OPERATION; REMOVAL
Descriptors DEC
COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; OPERATION; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
7 refs, 13 figs