Published 1995 | Version v1
Book Metadata-only

Verification of the WWER-440 pressure vessel neutron fluence calculation by activity measurement

Creators

  • 1. Inst. of Nuclear Research and Nuclear Energy, Sofia (Bulgaria).
  • 2. Kozloduy NPP, (Bulgaria).

Description

A nondestructive method is presented for estimating the critical temperature of the metal embrittlement, based on the evaluation of the fast neutron fluence on reactor pressure vessel (RPV). The accuracy of the obtained neutron fluxes is of crucial importance for the reliability of fluence evaluation. To qualify the calculation methodology, measurements of neutron flux responses in the proximity of WWER-440 RPV are used. (author). 8 refs., 1 tab

Part of:
Topsafe '95 Vol. 2

Additional details

Publishing Information

Publisher
European Nuclear Society.
Imprint Place
Berne (Switzerland)
ISBN
3-9520691-1-6
Imprint Title
Topsafe '95 Vol. 2
Imprint Pagination
[228 p.].
Journal Page Range
p. 33-36.

Conference

Title
International East-West Topical Meeting.
Dates
24-27 Sep 1995.
Place
Budapest (Hungary).

INIS

Country of Publication
Switzerland
Country of Input or Organization
Hungary
INIS RN
27048204
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ACTIVITY LEVELS; EMBRITTLEMENT; FAST NEUTRONS; KOZLODUY-1 REACTOR; NEUTRON FLUENCE; NEUTRON FLUX; REACTOR VESSELS
Descriptors DEC
BARYONS; CONTAINERS; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; FERMIONS; HADRONS; NEUTRONS; NUCLEONS; POWER REACTORS; PWR TYPE REACTORS; RADIATION FLUX; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS

Optional Information