Published 2009 | Version v1
Miscellaneous Open

Solving nodal kinetic equations by using a global reactivity way

Creators

  • 1. Turkish Atomic Energy Authority, CNAEM, Istanbul (Turkey)

Description

Computation codes which can analyze accident and transient cases sufficiently accurate and fast should be developed for safely operation of nuclear power and research reactors. Nodal kinetics is one of the computation methods which deal neutron dynamics in the reactors fast, accurately and in detail. In the calculation of the coupling reactivity, a convergency matter may arise depending on the problem being handled and so solving of the nodal kinetic equations may get in trouble. This situation is ousted by using a global reactivity way. In this solution technique, first, a neutron flux profile is computed by using the global reactivity calculated from the regional parameters in the nodal kinetic equations. Then, this flux profile is adjusted according to the coupling reactivity of each region. As a result, convergency problem in determining the coupling reactivity and limitations on computation time interval and nodal sizes dismiss and so an accurate neutron flux profile is fast calculated without any problem.

Files

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Part of:
10. National Nuclear Science and Technology Congress Proceedings Book, Volume 2

Additional details

Additional titles

Original title (Turkish)
Nodal kinetik denklemlerin global reaktivite yoentemi ile coezuemue

Publishing Information

Imprint Title
10. National Nuclear Science and Technology Congress Proceedings Book, Volume 2
Imprint Pagination
557 p.
Journal Page Range
p. 16-23
Report number
INIS-TR--0145

Conference

Title
10. National Nuclear Science and Technologies Congress
Original Conference Title
10. Ulusal Nuekleer Bilimler ve Teknolojileri Kongresi
Dates
6-9 Oct 2009
Place
Mugla (Turkey)

INIS

Country of Publication
Turkey
Country of Input or Organization
Turkey
INIS RN
42046320
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
ACCIDENTS; CALCULATION METHODS; COMPUTER CODES; EVALUATED DATA; FINITE DIFFERENCE METHOD; NODAL EXPANSION METHOD; REACTIVITY; REACTOR ACCIDENT SIMULATION; REACTORS
Descriptors DEC
CALCULATION METHODS; DATA; INFORMATION; ITERATIVE METHODS; MATHEMATICAL SOLUTIONS; NUMERICAL DATA; NUMERICAL SOLUTION; SIMULATION

Optional Information

Notes
Imprint:10. Ulusal Nuekleer Bilimler ve Teknolojileri Kongresi Bildiri Tam Metinleri Cilt 2