A Versatile Methodology for Reactor Pressure Vessel Aging Assessments

Vuiart, Romain; Brovchenko, Mariya; Taforeau, Julien; Jaiswal, Vaibhav; Dumonteil, Éric

doi:10.1080/00295639.2021.1991761

Cited by 3 publications

(11 citation statements)

References 22 publications

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“…To help the reader better understand the following results, Figure 3 shows the activation cross sections for the six types of dosimeters considered, processed at 600K using the NJOY2016 code [18] with ENDF files taken from the JEFF-3.3 data library [19]. Figure 3 shows that all dosimeters are sensitive to fast neutrons (i.e., those with energies above 1 MeV), making them highly relevant for assessing the reliability of vessel aging assessments (given that fast neutrons are the primary contributors to radiation damage [6]). Finally, it is interesting to note that 58 Ni(n,p), 54 Fe(n,p), 46 Ti(n,p) and 63 Cu(n,α) represent reactions with a strong energy threshold.…”

Section: Description Of the Hb Robinson-2 Reactormentioning

confidence: 99%

“…In this second approach, the fission neutron source term averaged over the 9th cycle of the HBR-2 reactor was computed using VACS. A detailed description of this methodology can be found in [6], and in this section we only recall the main principles of the calculation scheme. In addition, this section details the few approximations not present in the methodology as described in [6] that had to be made in order to carry out the analysis of the HBR-2 benchmark.…”

Section: The β Approach: Use Of Vacsmentioning

confidence: 99%

“…Processed energycontinuous cross sections (ACE format) Then, the pin-scale fission neutron emission distributions calculated by following the above methodology are used to compute the cycle-averaged fission neutron distribution within the reactor, according to Equation (6).…”

Section: Mcnp6 Input File Mcnp6mentioning

confidence: 99%

“…In this context, efforts have been made at the Institut de Radioprotection et de Sûreté Nucléaire (IRSN) to develop a versatile, best-estimate calculation scheme for the analysis of RPV embrittlement under neutron irradiation [6], named VACS (vessel aging calculation scheme). The methodology relies on a two-step approach, coupling deterministic and Monte Carlo calculations.…”

Section: Introductionmentioning

confidence: 99%

“…The first step estimates the full-core fission neutron source term and the second step considers the transport of neutrons from the core to the RPV, using the fission neutron distribution determined in the previous step. Throughout the construction of the methodology, several studies were conducted to minimize the inherent methodological biases [6][7][8][9] and to pave the way towards the quantification of the global uncertainty in its predictions [9,10]. In order to validate the numerical predictions using experimental dosimeter data from ex-core locations, a detailed analysis of the H.B.…”

Section: Introductionmentioning

confidence: 99%

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A Detailed Analysis of the H.B. Robinson-2 Reactor Pressure Vessel Dosimetry Benchmark

et al. 2022

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The operation of many nuclear pressurized water reactors is being extended beyond their design lifetime limit. From the perspective of possible further lifetime extension, safety requirements are a priority. Therefore, the quantification of the neutron irradiation embrittlement of the reactor pressure vessel (RPV) is an important issue, as this is a guiding parameter that influences the reactor lifetime. In this context, the Institut de Radioprotection et de Sûreté Nucléaire developed a calculation scheme for the analysis of RPV aging under neutron irradiation, named VACS (vessel aging calculation scheme). VACS couples a deterministic approach (CASMO5 and SIMULATE5) to evaluate the full-core fission neutron source term and a Monte Carlo modeling (MCNP6) approach to model the neutron attenuation from the core to sites of interest (RPV, surveillance capsules, etc.). To ensure the reliability of aging predictions, this paper describes a detailed analysis of the neutron H.B. Robinson-2 reactor pressure vessel dosimetry benchmark. The results indicate that VACS shows satisfactory accuracy when the ENDF-B/VII.1 or JEFF-3.3 nuclear data libraries are used in the attenuation calculation. However, the use of ENDF-B/VIII.0 leads to significantly worse results.

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Section: Description Of the Hb Robinson-2 Reactormentioning

confidence: 99%

Section: The β Approach: Use Of Vacsmentioning

confidence: 99%

Section: Mcnp6 Input File Mcnp6mentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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A Detailed Analysis of the H.B. Robinson-2 Reactor Pressure Vessel Dosimetry Benchmark

et al. 2022

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Fabrication and characterization of high-resolution 4H-SiC epitaxial radiation detectors for challenging reactor dosimetry environments

Mandal

Chaudhuri

Ruddy³

2023

EPJ Web Conf.

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Reactor dosimetry environments require radiation detectors that are capable of operating at high temperatures in extremely high neutron and gamma-ray dose rates. Silicon carbide (SiC) is one of the most promising wide bandgap semiconductors (3.27 eV) for harsh environment applications due to its radiation hardness, high breakdown voltage, high electron saturation velocity, and high thermal conductivity. In this paper, we summarize the prospect of Schottky barrier radiation detectors, fabricated on highly crystalline low-defect detector-grade n-type 4H-SiC epitaxial layers with thickness ranging from 20 to 250 lm, for harsh environment applications. A comprehensive discussion on the characterization of the parameters that influence the energy resolution has been included. The usage of electrical and radiation spectroscopic measurements for characterizing the junction and rectification properties, minority carrier diffusion lengths, and energy resolution has been elaborated. Characterization of crucial factors that limit the energy resolution of the detectors such as charge trap centers using thermally stimulated transient techniques is summarized. Finally, the effect of neutron fluence on the performance of the 4H-SiC detectors is discussed.

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PRATIC: A soluble-boron-free, pressurized water cooled, SMR core benchmark

Vuiart,

Eustache,

Eveillard

et al. 2024

EPJ Nuclear Sci. Technol.

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Current nuclear reactor research is actively exploring small modular pressurized water reactors (PWRs), particularly soluble-boron-free (SBF) configurations. SBF designs utilize control rods and gadolinium-poisoned fuel rods to manage reactivity. Additionally, small modular reactors (SMRs) commonly integrate steel reflectors to minimize neutron leakage. However, the compactness of SMRs and the adoption of these technical solutions result in notable fluctuations in neutron flux within the core during normal cycle operation. Hence, comprehensive analysis is essential, especially concerning reactor performance under normal and accident conditions, the reliability of neutronics calculation assumptions, etc. Research into these issues requires reactor core neutronics benchmarks that are consistent with industrial concepts so that the analysis results can be applied to real reactors. In this context, this article introduces PRATIC, a SBF-PWR SMR core neutronics benchmark designed to match the global performances of industrial concepts. The development of PRATIC was conducted using a deterministic calculation scheme coupling the APOLLO2 and CRONOS2 codes. PRATIC features a thermal power of 350 MWth, an equilibrium cycle length of 1.9 years, and an average discharge burnup of about 34 GWd/t, while maintaining controlled power distributions. The article elaborates on the design assumptions for PRATIC, then details the reactor core and its equilibrium cycle. Access to the PRATIC modeling data is available via a GIT repository, accessible upon request via email at pratic@cea.fr.

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A Versatile Methodology for Reactor Pressure Vessel Aging Assessments

Cited by 3 publications

References 22 publications

A Detailed Analysis of the H.B. Robinson-2 Reactor Pressure Vessel Dosimetry Benchmark

A Detailed Analysis of the H.B. Robinson-2 Reactor Pressure Vessel Dosimetry Benchmark

Fabrication and characterization of high-resolution 4H-SiC epitaxial radiation detectors for challenging reactor dosimetry environments

PRATIC: A soluble-boron-free, pressurized water cooled, SMR core benchmark

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