Pressure Vessel Calculations for Vver-440 Reactors

Hordósy, G.; Hegyi, György; Keresztúri, A.; Maráczy, Cs.; Temesvári, E.; Vertes, P.; Zsolnay, E.M.

doi:10.1142/9789812705563_0071

Cited by 2 publications

(5 citation statements)

References 0 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…As mentioned above, the calculations were made using the KARATE-MCNP code system developed at the Centre for Energy Research of the Hungarian Academy of Sciences [1,2]. In order to take into account the influence of the various core loads and operational parameters, the neutron source was determined on the boundaries of the reactor core with the aid of the KARATE reactor core design code.…”

Section: Neutron Transport Calculationsmentioning

confidence: 99%

“…Prior to the start of the calculations, the code system was validated in the framework of the REDOS project [14] in reference neutron fields of the LR-0 reactor, constituting VVER-440 and VVER-1000 mock-up cores [1], and by comparison with in situ measurements at the RPV surveillance positions of the different reactor units of the Paks NPP [15]. In both cases, good agreement was obtained between the calculated and experimental data.…”

Section: Neutron Transport Calculationsmentioning

confidence: 99%

“…• Neutron transport calculations have been performed using the KARATE-MCNP code system [1,2] to determine the fast neutron exposure of the RPV wall during the operation of the reactors.…”

Section: Introductionmentioning

confidence: 99%

“…The KARATE-MCNP code system was developed for this purpose (see in the next subsection) [1,2,9]. The results of the neutron transport calculations can then be compared with the corresponding experimental data, and applied further on in the dosimetry calculations (examples for the results of the neutron transport calculations can be found in the next subsection).…”

Section: Development and Introduction Of A New Rpv Surveillance Progrmentioning

confidence: 99%

See 3 more Smart Citations

Reactor Dosimetry Aspects of the Service Life Extension of the Hungarian Paks NPP

Zsolnay

Czifrus

Fehér

et al. 2016

EPJ Web of Conferences

View full text Add to dashboard Cite

Abstract. The service life of the Hungarian Paks Nuclear Power Plant (NPP) will be extended from the originally planned 30 years to 50 years. To improve the reliability of the results obtained in frame of the old reactor pressure vessel (RPV) surveillance programme, new methods have been developed, and based on them, the old exposition data have been re-evaluated for all the four reactor units. At the same time, a new RPV surveillance programme has been developed and introduced, and long term irradiations have been performed to determine the radiation damage of the surveillance specimens due to the high fast neutron exposition. Neutron transport calculations have been performed with a validated neutron transport code system to determine the fast neutron exposition of the RPVs during the extended service life. The cavity dosimetry is in the introductory phase. This paper presents the new developments in the field of the RPV surveillance dosimetry and summarises the results obtained. According to the results the service life of the NPP can safely be extended for the planned 50 years.

show abstract

Section: Neutron Transport Calculationsmentioning

confidence: 99%

Section: Neutron Transport Calculationsmentioning

confidence: 99%

“…• Neutron transport calculations have been performed using the KARATE-MCNP code system [1,2] to determine the fast neutron exposure of the RPV wall during the operation of the reactors.…”

Section: Introductionmentioning

confidence: 99%

Section: Development and Introduction Of A New Rpv Surveillance Progrmentioning

confidence: 99%

See 2 more Smart Citations

Reactor Dosimetry Aspects of the Service Life Extension of the Hungarian Paks NPP

Zsolnay

Czifrus

Fehér

et al. 2016

EPJ Web of Conferences

View full text Add to dashboard Cite

show abstract

“…number of cycles) a number of shielding calculations were performed. To speed up this process, a mixed procedure was developed, validated and applied at KFKI AERI earlier [1]. In this procedure the neutron source was determined on the boundaries of the core from deterministic calculations, and this source is used in the subsequent Monte Carlo calculations performed by MCNP.…”

Section: Introductionmentioning

confidence: 99%

Pressure Vessel Fluence Calculations for the Hungarian VVER-440 Units for the Power Uprate and the Llifetime Extension

Hordósy

Hegyi

Keresztúri

et al. 2016

EPJ Web of Conferences

View full text Add to dashboard Cite

Abstract.A major project was launched at Paks NPP, Hungary, to investigate the possibility of lifetime extension up to 60 years. At the same time, new fuel types with higher enrichment and containing pins with gadolinium have been introduced. Due to these plans, the radiation load of the pressure vessel was evaluated up to 60 years irradiation, taking into account the past and planned future cycles. The computational procedure, elaborated and validated earlier for the fast flux calculation in the pressure vessel was modified for the new fuel types. The neutron source at the core boundaries was taken from core design calculations and the neutron transport from the source to and through the pressure vessel was followed by Monte Carlo calculations. A number of calculations were performed to adequately follow the change of the neutron source. The paper details this procedure, the used Monte Carlo model, the influence of the different reloading schemes on the radiation load and the calculated results.

show abstract

Pressure Vessel Calculations for Vver-440 Reactors

Cited by 2 publications

References 0 publications

Reactor Dosimetry Aspects of the Service Life Extension of the Hungarian Paks NPP

Reactor Dosimetry Aspects of the Service Life Extension of the Hungarian Paks NPP

Pressure Vessel Fluence Calculations for the Hungarian VVER-440 Units for the Power Uprate and the Llifetime Extension

Contact Info

Product

Resources

About