...S. Belousov; K. Ilieva; M. Mitev Reactor dosimetry (RD) is a tool that provides data for neutron fluence accumulated over the reactor pressure vessel (RPV) during the reactor operation. This information, however, is not sufficient for RPV lifetime assessment. The life management of RPV...

...D. A. Thornton; D. A. Allen; A. P. Huggon; D. J. Picton; A. T. Robinson; R. J. Steadman; T. Serén; M. Lipponen; T. Kekki Specimens for the Sizewell B reactor pressure vessel (RPV) in-service steels surveillance program are irradiated inside eight capsules located within the reactor pressure vessel...

...Milan Marek; Jan Rataj; Stanislav Vandlik The paper summarizes the attenuation coefficient of the neutron fluence with E > 0.5 MeV through a reactor pressure vessel for vodo-vodyanoi energetichesky reactor (VVER) reactor types measured and/or calculated for mock-up experiments, as well...

... International, Vol. 9, No. 4 Paper ID JAI104022 Available online at www.astm.org P. G. Borodkin,1 G. I. Borodkin,1 N. N. Khrennikov,1 and J. Konheiser2 Application of Ex-vessel Neutron Dosimetry Combined with In-core Measurements for Correction of Neutron Source Used for Reactor Pressure Vessel Fluence...

.... In structural integrity assessment of reactor pressure vessels submitted to an accidental loading condition called pressurized thermal shock, the cladding is generally considered not to play any role and is neglected. However, cladding has the ability to restrain the crack from opening due to its good ductility...

...Naoki Soneda; Kenji Dohi; Akiyoshi Nomoto; Kenji Nishida; Shiori Ishino A new embrittlement correlation method developed for the Japanese reactor pressure vessel (RPV) steels is presented. The Central Research Institute of Electric Power Industry and the Japanese electric utilities conducted...

... of impurities of Japanese reactor pressure vessel ones. The neutron irradiation was conducted at 563 K to a fluence of 1.3× 10 24 n/m 2 ( E >1 MeV) using material testing reactors. The neutron irradiation induced the P and Ni segregation and the reduction in C in some cases at grain-boundaries. The increase...

...Naoki Soneda; Kenji Dohi; Kenji Nishida; Akiyoshi Nomoto; Minoru Tomimatsu; Hiroshi Matsuzawa Understanding the embrittlement of reactor pressure vessel (RPV) steels at high fluence region is very important for the long term operation of nuclear power plants. In this study, extensive...

... constraint condition in standard specimens, remain a subject of concern. In this work a study of the transferability of the fracture toughness measurements from laboratory specimens to structural components is performed. The structural component of interest is the Reactor Pressure Vessel subjected...

... of the rst generation of VVER-440 RPV steels is discussed. KEYWORDS: reactor pressure vessel, radiation embrittlement, ductile-to-brittle transition temperature, subsize impact bend specimens, specimen reconstitution Nomenclature Latin Symbols F AF DBTT TT E Fast neutron uence Radiation embrittlement coef...

... temperatures and showed the Master Curve to be nonconservative relative to the results, although that observation is uncertain due to evidence of intergranular fracture. 17 07 2007 02 02 2008 20 03 2008 Master Curve reactor pressure vessel irradiation intergranular fracture temper...

... embrittlement requires developing a correlation between transition temperature values evaluated using test results of standard (full-size) and subsize CVN specimens. Such a correlation is discussed. 12 01 2007 02 02 2008 27 03 2008 reactor pressure vessel radiation embrittlement ductile...

...Yu. A. Nikolaev; A. V. Nikolaeva Results of VVER-440/213 reactor pressure vessel (RPV) surveillance specimens studies showed that all surveillance impact bend specimens were irradiation with a lead factor more than 20 compared to irradiation of the pressure vessel inner surface. This is a special...

... and evaluated integral uxes, space-energy indices, like the spectral indices and attenuation factors in measuring points. KEYWORDS: reactor pressure vessel, dosimetry, neutron and photon spectra measurement, transport calculations, WWER-1000 Introduction The project REDOS was divided in the following four...

... and representative results of research programs. The trend curves for VVER-440 and VVER-1000 RPV steels are proposed. The mechanisms of radiation embrittlement of Cr Ni Mo and Cr Mo RPV steels are supposed. KEYWORDS: reactor pressure vessel, surveillance specimens, radiation embrittlement, post irradiation annealing...

...Yutaka Nishiyama; Kunio Onizawa; Masahide Suzuki A study on phosphorus (P) segregation at grain boundaries and intergranular embrittlement of reactor pressure vessel steels due to thermal aging and neutron irradiation has been performed for A533B steel plates and weld metals doped with different...

... covered. The lifetime extension problem for the rst and second generation of VVER units is considered. KEYWORDS: reactor pressure vessel, radiation embrittlement, post irradiation annealing, re-irradiation, ductile-to-brittle transition temperature List of Notation Symbols F AF TT E C Greek Symbols...

...SM Zaritsky; VI Vikhrov; DY Erak; VN Kochkin; EB Brodkin; AL Egorov Activity of templates (specimens), which were cut out from the inner surface of Kola-1 and Kola-2 WWER-440 reactor pressure vessels (RPVs), were measured, and the results were used to support the RPV dosimetry. Twelve weld and two...

... libraries is obtained for neutrons with energy above 0.1 MeV. The worst consistency is obtained for the thermal neutrons. For gammas a better consistency between DO and MC results is obtained when BGL1000 library is applied. KEYWORDS: neutron uence, reactor pressure vessel, radiation damage, multigroup...

...SI Belousov; KD Ilieva; VL Matushko Adjustment of the neutron fluence on the VVER-440 reactor pressure vessel (RPV) inner wall has been carried out. For the purpose of this adjustment the neutron flux responses' sensitivity to the main parameters of calculation uncertainty has been calculated...