Chooz-B1, the new Electricite de France PWR: calculation scheme of neutron leakages from the reactor cavity
Creators
- 1. Electricite de France, 69 - Villeurbanne
Description
A new calculation scheme has been set up to assess the neutron field characteristics inside French PWR. In order to take into account multiple neutron scattering and the complexity of the reactor geometry, the use of Monte-Carlo methods have been heavily increased. They are coupled with classical SN.-methods. The main goal aimed at was to find out the neutron field characteristics at the level of the reactor pit openings. These radiation reference sources will be used to check the neutron shielding efficiencies. The new calculation scheme has been applied to CHOOZ-B1, the first unit of the new N4 program. The former results have been compared with the measurement results related to PALUEL-I and II PWR, two units of the previous P4 program. Although the core and the geometry are not entirely similar, it is possible to check with confidence the calculation results along the vessel and at the core midplane level with the measurement results at the same locations. It appears that they are in good agreement. Consequently, the new calculation scheme appears reliable
Files
19005732.pdf
Files
(390.7 kB)
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Additional details
Publishing Information
- Imprint Pagination
- 15 p.
- Report number
- CEA-CONF--9033
Conference
- Title
- American Nuclear Society international meeting on advances in reactor physics, mathematics and computation.
- Dates
- 27-30 Apr 1987.
- Place
- Paris (France).
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 19005732
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ARDENNES B-1 REACTOR; COMPUTER CALCULATIONS; CONTAINMENT BUILDINGS; MONTE CARLO METHOD; NEUTRON FLUX; NEUTRON LEAKAGE; PRESSURE VESSELS; SHIELDING
- Descriptors DEC
- BUILDINGS; CONTAINERS; CONTAINMENT; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; RADIATION FLUX; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS