Monte Carlo fluence calculations and spectrum adjustment for the pressure vessel of the VVER-1000 Balakovo-3
- Forschungszentrum Rossendorf e.V., Dresden (Germany); and others
The neutron embrittlement problem of current pressure vessel reactors is of great safety and economic concern. It culminates in Russian VVER-type reactors. Compared with Western pressurized water reactors, the shorter distance to the core results in substantially higher neutron fluences for the pressure vessels. In the case of the VVER-1000, the increased content of nickel and the position of a weld at a height near to the maximum flux are additional, unfavorable peculiarities. These circumstances caused the embrittlement problem of VVER pressure vessels to become the objective of many international research collaborations. In this field, the development and application of advanced methods of fluence evaluations play an important part. It is further emphasized by the special location of the surveillance specimens that are installed above the upper core edge in a strong flux gradient. This fact gives rise to questioning the transferability of the embrittlement behavior of the specimens to the pressure vessel. A reliable answer may be given on the basis of advanced, well-validated neutron fluence evaluations only.
- OSTI ID:
- 552569
- Report Number(s):
- CONF-971125-; ISSN 0003-018X; TRN: 98:001770
- Journal Information:
- Transactions of the American Nuclear Society, Vol. 77; Conference: 1997 American Nuclear Society (ANS) winter meeting, Albuquerque, NM (United States), 16-20 Nov 1997; Other Information: PBD: 1997
- Country of Publication:
- United States
- Language:
- English
Similar Records
Pressure vessel fluence monitoring at NPP with VVER: Routine technique and new approaches
Three-dimensional neutron flux calculations for the VVER pressure vessel