Neutron fluence determination for operation effectiveness assessment and prediction of WWER pressure vessel lifetime at the Kozloduy NPP
Creators
- 1. Bylgarska Akademiya na Naukite, Sofia (Bulgaria). Inst. za Yadrena Izsledvaniya i Yadrena Energetika
- 2. Kombinat Atomna Energetika, Kozloduj (Bulgaria)
Description
Embrittlement processes in reactor pressure vessel (RPV) metal have been investigated by neutron dosimetry. A software package for fluence calculations has been developed and used for evaluation of the accumulated neutron fluence, the critical temperature of radiation embrittlement and the RPV lifetime. A digital reactivity meter DR-8 has been introduced for continuous neutron fluence monitoring. Estimates of the neutron fluence and the radiation state of all 6 units of the Kozloduy NPP are presented. The Unit 4 RPV is in the best state regarding metal embrittlement, while the Units 2 and 3 can be safely operated up to the end of their design lifetime only using dummy cassettes. The neutron fluence accumulation in the Unit 1 RPV is quite big and can not be reduced with annealing. Activity measurements of the Unit 1 internal wall shavings are made after the 14-th cycle which show a good agreement with calculated values (1.105 Bq/g). The critical embrittlement temperature of the Units 1 - 4 is estimated as a function of the working cycles. 11 figs., 1 tab
Files
28033284.pdf
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Additional details
Publishing Information
- Imprint Title
- Proceedings of a scientific-technical conference dedicated to the 20-th anniversary of Kozloduy NPP with international participation
- Imprint Pagination
- 442 p.
- Journal Page Range
- p. 189-200.
- Report number
- INIS-BG--0013
Conference
- Title
- Scientific-technical conference dedicated to the 20-th anniversary of Kozloduy NPP with international participation.
- Dates
- 25-26 Oct 1994.
- Place
- Kozloduy (Bulgaria).
INIS
- Country of Publication
- Bulgaria
- Country of Input or Organization
- Bulgaria
- INIS RN
- 28033284
- Subject category
- S36: MATERIALS SCIENCE; S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- CRITICAL TEMPERATURE; DAMAGING NEUTRON FLUENCE; EMBRITTLEMENT; EXPERIMENTAL DATA; KOZLODUY-1 REACTOR; KOZLODUY-2 REACTOR; KOZLODUY-3 REACTOR; KOZLODUY-4 REACTOR; LIFETIME; NEUTRON DOSIMETRY; NEUTRONIC DAMAGE FUNCTIONS; PHYSICAL RADIATION EFFECTS; PRESSURE VESSELS
- Descriptors DEC
- CONTAINERS; DATA; DOSIMETRY; ENRICHED URANIUM REACTORS; INFORMATION; NEUTRON FLUENCE; NUMERICAL DATA; PHYSICAL PROPERTIES; POWER REACTORS; PWR TYPE REACTORS; RADIATION EFFECTS; REACTORS; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; TRANSITION TEMPERATURE; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS