Published November 1990 | Version v1
Report Metadata-only

Utilization of low leakage loading schemes for pressure vessel neutron exposure reduction

Creators

  • 1. Institut Jozef Stefan, Ljubljana (Yugoslavia)

Description

The possibility to use the low leakage loading pattern (LLLP) in-core fuel management in the pressurized water reactor (PWR) in order to obtain a significant reduction of the maximum fast neutron flux in the pressure vessel (PV) is presented. Methodology used at ''J. Stefan'' Institute to develop appropriate LLLPs is described. Examples of the LLLP for the two loop PWR are given and compared with the standard out-in-in loading scheme. Resulting fast flux distributions in the pressure vessel are shown. Computer codes and calculational procedures used for the determination of neutron flux and spectrum in the ex-core region are shortly outlined, as well as modelling applied in transport calculations. (author). 8 refs, 5 figs, 10 tabs

Part of:
In-core fuel management practices. Proceedings of two technical committee meetings and workshops held in Madrid, 12-15 July 1988, and Vienna, 4-7 December 1989

Additional details

Publishing Information

Imprint Title
In-core fuel management practices. Proceedings of two technical committee meetings and workshops held in Madrid, 12-15 July 1988, and Vienna, 4-7 December 1989
Imprint Pagination
438 p.
Journal Page Range
p. 60-67.
Report number
IAEA-TECDOC--567

Conference

Title
Technical committee meeting and workshop on improvements of in-core fuel management codes.
Dates
12-15 Jul 1988.
Place
Madrid (Spain).

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
22023356
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BURNUP; COMPUTER CODES; FUEL MANAGEMENT; KRSKO REACTOR; NEUTRON FLUX; NEUTRON SPECTRA; PRESSURE VESSELS; REACTOR FUELING
Descriptors DEC
CONTAINERS; ENRICHED URANIUM REACTORS; MANAGEMENT; NUCLEAR MATERIALS MANAGEMENT; POWER REACTORS; PWR TYPE REACTORS; RADIATION FLUX; REACTORS; SPECTRA; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information