Neutron and Gamma Fluence and Radiation Damage Parameters of Ex-Core Components of Russian and German Light Water Reactors

Boehmer, B.; Konheiser, J.; Noack, K.; Rogov, A. D.; Borodkin, G. I.; Polke, E.; Vladimirov, P.

doi:10.1142/9789812705563_0036

Cited by 7 publications

(17 citation statements)

References 3 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…In addition, the gamma fluence was about one order higher than the relative neutron fluence, mainly because of the (n,γ) reaction of neutron with the iron composition in the vessel. Table III compared the results of neutron flux integrals onthe core mid-plane between our MCNP5 calculations and those reported in [2]. As shown in this Table, the difference in the MCNP5 and BUGLE-96 values could reach about 25% at the outer surface of the RPV.…”

Section: Calculation Resultsmentioning

confidence: 78%

“…As shown in this Table, the difference in the MCNP5 and BUGLE-96 values could reach about 25% at the outer surface of the RPV. The reason might be due to the discrepancy between our reactor core input data and those used in [2]. Namely, different core loading pattern, fuel assemblies, steel baffle, and water hole data were used in this calculation.…”

Section: Calculation Resultsmentioning

confidence: 99%

“…On that basis, the conclusion was that no firm judgement could be formed on the current international level of accuracy in pressure vessel fluence calculations. In 2002, Boehmer et al [2] presented the results of neutron and gamma spectra, several fluence integrals and radiation damage parameters of ex-core components of Russian (VVER-1000) and German (1300 MW PWR and 900 MW BWR) light water reactors, with special interest in the relative contributions of gamma radiation to the sum of gamma and neutron contributions. However, the neutron and gamma flux ditributions at the RPV were not reported and consequently the areas in the RPV where the maximum of displacement-peratom (DPA) were not identified.…”

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Calculation of neutron and gamma fluences on VVER reactor pressure vessel

Nguyen¹,

Nhu

Nguyen

2016

Nucl. Sci. and Tech.

View full text Add to dashboard Cite

Embrittlement is one of the most important effects affecting reactor pressure vessel (RPV) aging. RPV is irradiated with neutrons and gammas, especially fast neutrons, which mainly lead to embrittlement of RPV during operation lifetime of nuclear reactors. Therefore, the radiation-induced embrittlement of the RPV should be carefully evaluated. In this paper, a preliminary calculation was performed using the MCNP5 code to identify the areas in the RPV of the VVER-1000/V320 reactor where the neutron and gamma fluxes are maximum. Also, the neutron and gamma fluence distributions on the RPV were investigated and evaluated along with their energy spectra. These calculations are the starting point for the evaluation of radiation damage to RPV of VVER reactors.

show abstract

Section: Calculation Resultsmentioning

confidence: 78%

Section: Calculation Resultsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

Calculation of neutron and gamma fluences on VVER reactor pressure vessel

Nguyen¹,

Nhu

Nguyen

2016

Nucl. Sci. and Tech.

View full text Add to dashboard Cite

show abstract

“…Three-dimensional (3-D) synthesis method based on results of DORT calculations was used for neutron fluence rate evaluations [4]. Analytical justification of 3-D synthesis method by comparison with precise 3-D calculations based on Monte Carlo codes was carried out [5]. The calculation procedure based on code DORT applies routinely for RPV neutron fluence evaluation with the purpose of estimation of RPV lifetime.…”

Section: A Calculational Proceduresmentioning

confidence: 99%

Application of Integral Ex-Core and Differential In-Core Neutron Measurements for Adjustment of Fuel Burn-Up Distributions in VVER-1000

Borodkin¹,

Borodkin²,

Khrennikov³

2010

IEEE Trans. Nucl. Sci.

View full text Add to dashboard Cite

The paper deals with calculational and semi-analytical evaluations of VVER-1000 reactor core neutron source distributions and their influence on measurements and calculations of the integral through-vessel neutron leakage. Time-integrated neutron source distributions used for DORT calculations were prepared by two different approaches based on a) calculated fuel burn-up (standard routine procedure) and b) in-core measurements by means of SPD & TC (new approach). Taking into account that fuel burn-up distributions in operating VVER may be evaluated now by analytical methods (calculations) only it is needed to develop new approaches for testing and correction of calculational evaluations. Results presented in this paper allow to consider a reverse task of alternative estimation of fuel burn-up distributions. The approach proposed is based on adjustment (fitting) of time-integrated neutron source distributions, and hence fuel burn-up patterns in some part of reactor core, on the base of ex-core neutron leakage measurement, neutron-physical calculation and in-core SPD & TC measurement data.

show abstract

“…Three-dimensional (3D) synthesis method based on results of DORT calculations was used for neutron fluence rate evaluations [4]. Analytical justification of 3D synthesis method by comparison with precise 3D calculations based on Monte Carlo codes was carried out [5]. The calculation procedure based on code DORT applies routinely for RPV neutron fluence evaluation with the purpose of estimation of RPV lifetime.…”

Section: A Calculational Proceduresmentioning

confidence: 99%

Application of integral ex-core and differential in-core neutron measurements for adjustment of fuel burn-up distributions in VVER-1000

Borodkin¹,

Khrennikov²

2009

2009 1st International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and Their Applications

View full text Add to dashboard Cite

The paper deals with calculational and semianalytical evaluations of VVER-1000 reactor core neutron source distributions and their influence on measurements and calculations of the integral through-vessel neutron leakage. Timeintegrated neutron source distributions used for DORT calculations were prepared by two different approaches based on a) calculated fuel burn-up (standard routine procedure) and b) incore measurements by means of SPD & TC (new approach). Taking into account that fuel burn-up distributions in operating VVER may be evaluated now by analytical methods (calculations) only it is needed to develop new approaches for testing and correction of calculational evaluations. Results presented in this paper allow to consider a reverse task of alternative estimation of fuel burn-up distributions. The approach proposed is based on adjustment (fitting) of time-integrated neutron sourcedistributions, and hence fuel burn-up patterns in some part of reactor core, on the base of ex-core neutron leakage measurement, neutron-physical calculation and in-core SPD & TC measurement data.

show abstract

Neutron and Gamma Fluence and Radiation Damage Parameters of Ex-Core Components of Russian and German Light Water Reactors

Cited by 7 publications

References 3 publications

Calculation of neutron and gamma fluences on VVER reactor pressure vessel

Calculation of neutron and gamma fluences on VVER reactor pressure vessel

Application of Integral Ex-Core and Differential In-Core Neutron Measurements for Adjustment of Fuel Burn-Up Distributions in VVER-1000

Application of integral ex-core and differential in-core neutron measurements for adjustment of fuel burn-up distributions in VVER-1000

Contact Info

Product

Resources

About