Monte Carlo fluence calculations and spectrum adjustment for the pressure vessel of the VVER-1000 Balakovo-3

Journal Article · Mon Dec 01 04:00:00 EST 1997 · Transactions of the American Nuclear Society

OSTI ID:552569

Barz, H U; Boehmer, B; Konheiser, J ^[1]

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1. 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--
• Journal Information: Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 77; ISSN 0003-018X; ISSN TANSAO
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
66 PHYSICS
EMBRITTLEMENT
NEUTRON FLUENCE
NEUTRON FLUX
PRESSURE VESSELS
PWR TYPE REACTORS