Neutron fluence determination for VVER-440 reactor pressure vessel aging surveillance
- Inst. for Nuclear Research and Nuclear Energy, Sofia (Bulgaria). Neutron and Reactor Physics Dept.
The neutron flux and fluence determination on Bulgarian VVER-440/230 (Units No. 1--4 of Kozloduy NPP) Reactor Pressure Vessels is discussed. In these reactors weld 4 of RPV undergoes the most severe irradiation embrittlement. The choice of the neutron transport calculational parameters is substantiated. The inconsistency of 3D neutron flux values obtained by the 3D code TORT and by the synthesis method of DOT 2D results in the point of most severe irradiation embrittlement is within 3% limits range. Radiochemical analysis of the templets sampled out from the Unit No. 2 vessel after 16 cycles of exploitation, before and after the annealing, was carried out. The calculated and experimental values of the neutron fluence on the Unit 2 RPV are compared.
- OSTI ID:
- 55572
- Report Number(s):
- CONF-930809-; ISBN 0-8031-1899-6; TRN: 95:012817
- Resource Relation:
- Conference: 8. ASTM-EURATOM symposium on reactor dosimetry, Vail, CO (United States), 29 Aug - 3 Sep 1993; Other Information: PBD: 1994; Related Information: Is Part Of Reactor dosimetry. ASTM STP 1228; Farrar, H. IV; Lippincott, E.P.; Williams, J.G.; Vehar, D.W. [eds.]; PB: 871 p.
- Country of Publication:
- United States
- Language:
- English
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