SINBAD – Radiation shielding benchmark experiments

Kodeli, I.; Sartori, Enrico

doi:10.1016/j.anucene.2021.108254

Cited by 35 publications

(27 citation statements)

References 24 publications

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“…An international shielding benchmark was first proposed in 1988 at the 7 th International Conference on Radiation Shielding (ICRS-7), which resulted in the Shielding Integral Benchmark Archive Database (SINBAD) being established in 1996 as a joint effort between the Nuclear Energy Agency (NEA) and the Radiation Safety Information Computational Center (RSICC) (https://www. oecd-nea.org/jcms/pl_32139/shielding-integral-benchmarkarchive-and-database-sinbad) (Kodeli, Sartori, and Kirk, 2006;Kodeli, et al, 2014). The goal of this type of database is to provide the community a way to validate their shielding or fixed source simulations and evaluated nuclear data.…”

Section: Shielding Integral Benchmark and Archive Database (Sinbad)mentioning

confidence: 99%

Engagement opportunities in OECD NEA benchmark development

Bess¹,

Blaise

Buß

et al. 2023

Front. Energy Res.

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A myriad of opportunities is available to collaborate via international benchmark exercises and experimental data preservation activities. Many such opportunities abound under the auspices of the Nuclear Science Committee of the Organisation for Economic Co-operation and Development Nuclear Energy Agency (NEA). Key projects and activities of relevance to the development of advanced reactors design include the International Criticality Safety Benchmark Evaluation Project (ICSBEP), the International Reactor Physics Experiment Evaluation Project (IRPhEP), the International Assay Data of Spent Nuclear Fuel Database (SFCOMPO), the Shielding Integral Benchmark and Archive Database (SINBAD), and The International Experimental Thermal HYdraulicS Database (TIETHYS), and various cooperative benchmark exercises. Interested participants are encouraged to contact the leadership and secretariat of the various Technical Working Groups and Working Parties to become more engaged. This paper provides a summary of the current benchmark exercises and experimental databases available for international participation.

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Section: Shielding Integral Benchmark and Archive Database (Sinbad)mentioning

confidence: 99%

Engagement opportunities in OECD NEA benchmark development

Bess¹,

Blaise

Buß

et al. 2023

Front. Energy Res.

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“…The H.B. Robinson-2 (HBR-2) neutron dosimetry benchmark [11] from the SINBAD database [12] is widely used in the scientific community for the validation of calculation schemes designed to predict vessel aging, as shown in [13][14][15][16]. It features in-vessel (surveillance capsule) and ex-vessel (reactor cavity) dosimetry data acquired during the 9th cycle of the H.B.…”

Section: The Hb Robinson-2 Reactor Pressure Vessel Dosimetry Benchmarkmentioning

confidence: 99%

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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“…Some of these discrepancies could be the result of large experimental uncertainties or missing information details on the experiment conditions, material, or dimensions not incorporated into the validation models. It was noted that quality of information for measured reaction rates is likely much higher than that of measured spectra, which depends on the quality of the processing of pulse-heights through unfolding algorithm [21]. A comparison between MAVRIC validation calculations and measurement data is further provided for each of the analyzed benchmark experiments:…”

Section: Scale Validation For Shielding Applicationsmentioning

confidence: 99%

“…A shielding benchmark suite is distributed with MCNP [28]. A summary of the fission shielding benchmarks in SINBAD for which MCNP models exist and a quality review of these benchmarks is available [21]. These benchmarks currently include experiments conducted at the Activation and SPectroscopy in Shields and Ispra shielding facilities, which tested radiation attenuation in individual shielding materials, skyshine benchmarks, and the VENUS-3 reactor shielding benchmark.…”

Section: Code-to-code Comparisonsmentioning

confidence: 99%

Review of SCALE Validations Applicable to Spent Nuclear Fuel Shielding Calculations

Radulescu¹,

Alpan²

2022

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SINBAD – Radiation shielding benchmark experiments

Cited by 35 publications

References 24 publications

Engagement opportunities in OECD NEA benchmark development

Engagement opportunities in OECD NEA benchmark development

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

Review of SCALE Validations Applicable to Spent Nuclear Fuel Shielding Calculations

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