U.S. Department of EnergyOffice of Scientific and Technical Information
Multidimensional reactor kinetics modeling
Abstract
There is general agreement that for many light water reactor transient calculations, it is-necessary to use a multidimensional neutron kinetics model coupled to a thermal-hydraulics model for satisfactory results. These calculations are needed for a variety of applications for licensing safety analysis, probabilistic risk assessment (PRA), operational support, and training. The latter three applications have always required best-estimate models, but in the past applications for licensing could be satisfied with relatively simple models. By using more sophisticated best-estimate models, the consequences of these calculations are better understood, and the potential for gaining relief from restrictive operating limits increases. Hence, for all of the aforementioned applications, it is important to have the ability to do best-estimate calculations with multidimensional neutron kinetics models. coupled to sophisticated thermal-hydraulic models. Specifically, this paper reviews the status of multidimensional neutron kinetics modeling which would be used in conjunction with thermal-hydraulic models to do core dynamics calculations, either coupled to a complete NSSS representation or in isolation. In addition, the paper makes recommendations as to what should be the state-of-the-art for the next ten years. The review is an update to a previous review of the status as of ten years ago. The general requirements formore »
- Authors:
- Publication Date:
- Research Org.:
- Brookhaven National Lab. (BNL), Upton, NY (United States)
- Sponsoring Org.:
- Nuclear Regulatory Commission, Washington, DC (United States)
- OSTI Identifier:
- 405746
- Report Number(s):
- BNL-NUREG-63337; CONF-961192-1
ON: DE96015055; TRN: 97:001172
- DOE Contract Number:
- AC02-76CH00016
- Resource Type:
- Conference
- Resource Relation:
- Conference: Organization for Economic Co-Operation and Development (OECD)/Committee on the Safety of Nuclear Installations (CSNI) workshop on transient thermal-hydraulic codes requirements, Annapolis, MD (United States), 5-8 Nov 1996; Other Information: PBD: [1996]
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; 22 NUCLEAR REACTOR TECHNOLOGY; 99 MATHEMATICS, COMPUTERS, INFORMATION SCIENCE, MANAGEMENT, LAW, MISCELLANEOUS; PWR TYPE REACTORS; REACTOR KINETICS; REACTOR PHYSICS; COMPUTER CODES; BWR TYPE REACTORS; HEAT TRANSFER; N CODES; T CODES; S CODES
Citation Formats
Diamond, D J. Multidimensional reactor kinetics modeling. United States: N. p., 1996.
Web.
Diamond, D J. Multidimensional reactor kinetics modeling. United States.
Diamond, D J. 1996.
"Multidimensional reactor kinetics modeling". United States. https://www.osti.gov/servlets/purl/405746.
@article{osti_405746,
title = {Multidimensional reactor kinetics modeling},
author = {Diamond, D J},
abstractNote = {There is general agreement that for many light water reactor transient calculations, it is-necessary to use a multidimensional neutron kinetics model coupled to a thermal-hydraulics model for satisfactory results. These calculations are needed for a variety of applications for licensing safety analysis, probabilistic risk assessment (PRA), operational support, and training. The latter three applications have always required best-estimate models, but in the past applications for licensing could be satisfied with relatively simple models. By using more sophisticated best-estimate models, the consequences of these calculations are better understood, and the potential for gaining relief from restrictive operating limits increases. Hence, for all of the aforementioned applications, it is important to have the ability to do best-estimate calculations with multidimensional neutron kinetics models. coupled to sophisticated thermal-hydraulic models. Specifically, this paper reviews the status of multidimensional neutron kinetics modeling which would be used in conjunction with thermal-hydraulic models to do core dynamics calculations, either coupled to a complete NSSS representation or in isolation. In addition, the paper makes recommendations as to what should be the state-of-the-art for the next ten years. The review is an update to a previous review of the status as of ten years ago. The general requirements for a core dynamics code and the modeling available for such a code, discussed in that review, are still applicable. The emphasis in the current review is on the neutron kinetics assuming that the necessary thermal-hydraulic capability exists. In addition to discussing the basic neutron kinetics, discussion is given of related modeling (other than thermal- hydraulics). The capabilities and limitations of current computer codes are presented to understand the state-of-the-art and to help clarify the future direction of model development in this area.},
doi = {},
url = {https://www.osti.gov/biblio/405746},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1996},
month = {11}
}