Fast Reactors and Accelerator Driven Systems Knowledge Base

IAEA-TECDOC--166: Principles of hot-channel factor calculations for fast reactors

Summary report of a panel meeting held in Karlsruhe, 22-24 November 1973 on the recommendation of the International Working Group on Fast Reactors. 1974. p. 133-142

International Atomic Energy Agency, Vienna (Austria), IAEA-TECDOC--166

Abstract

Deviations of parameters from their average values in the manufacturing and construction of cores for nuclear reactors lead to deviations from the average operational regime. It is important to estimate the probability of such operational deviations in order to be able to operate reactors safely, economically and reliably.

The statistical task involved here is closely related to the fuel design, cooling system and core structure design. In the application of this task, the concept of the hot-channel factor permits a quantitative estimate of the safety margin in the thermal design of fuel elements, and thereby sepcification of the allowable manufacturing tolerances. <\p>

On recommendation of the International Working Group on Fast Reactors, a panel meeting on "Principles of Hot-Channel Factor Calculations" took place at the Karlsruhe Nuclear Centre in the Federal Republic of Germany from 22 to 24 November 1974.

The panel discussion focused on the following areas:
  1. Applied theories and mathematical methods of hot spot analysis.
  2. Application to practical calculation and analysis during the reactor operation.
  3. Consideration of detailed problems.
  4. Effect of the core design.
  5. Future development.
The papers presented at the meeting are published in this report in their original languages.

view the full text of this conference report (format: PDF, size= 21210kB, 229 pages)

see also:

Articles

Reliable core thermal design
Amendola, A. (Commission of the European Communities, Brussels (Belgium))

Method of calculation of hot channel factors for fast reactor fuel elements
Krasnoyarov, N.V. (Nauchno-Issledovatel'skij Inst. Atomnykh Reaktorov, Dimitrovgrad (USSR))

Consideration on safety margin in Joyo thermal design
Inoue, T.; Yoshino, F.; Izumi, A. (Power Reactor and Nuclear Fuel Development Corp., Tokyo (Japan))

A simple procedure for the combination of fuel pin, sub-assembly and reactor uncertainties in fast reactor clad hot spot temperature assessment
Linning, D.L. (UKAEA Reactor Group, Risley)

Hot-spot analysis procedures for fast reactors
Linning, D.L.; McAreavey, G.; Rowlinson, B. (UKAEA Reactor Group, Risley)

The objectives of design stage hot-spot analysis
Gatley, J.A. (Nuclear Power Group Ltd., Risley (UK))

The advances statistical hot spot analysis in gas breeder reactors
Franken, W.M.P. (Stichting Reactor Centrum Nederland, Petten)

Hot-spot computational method proposed for the start-up of Phenix
Skok, J. (CEA Centre d'Etudes Nucleaires de Cadarache, 13 - Saint-Paul-les-Durance (France))

Part 1 and 2 of CNEN activities on the thermal desing of fast reactor fuel elements (status report)
Amelotti, F.; Barbaro, M.; Spagna, F.; Iannuzzo, P.; Falzetti, L.; Martini, M

Application of hot channel analysis to KNK-II
Schaefer, H.; Klassmann, W. (Internationale Atomreaktorbau G.m.b.H. (INTERATOM), Bensberg/Koeln (F.R. Germany))

Discussion of some problems arising within the interpretation of irradiation experiments carried out in more than one reactor
Miegroet, J. van

An analytical method of evaluating the effect of rod displacement on circumferential temperature and heat flux distributions -- two and three dimensional treatments
Hishida, Hisashi (Mitsubishi Atomic Power Industries, Inc., Tokyo (Japan))

Effect of temperature dependency in material properties to hot spot subfactors
Hishida, Hisashi (Mitsubishi Atomic Power Industries, Inc., Tokyo (Japan))

Test sample: statistical hot spot analysis for a sodium cooled fast reactor core
Doetschmann, K. (Gesellschaft fuer Kernforschung m.b.H., Karlsruhe (F.R. Germany))