Automated importance generation and biasing techniques for Monte Carlo shielding techniques by the TRIPOLI-3 code

Both, J. P.; Nimal, J.C.; Vergnaud, T.

doi:10.1016/0149-1970(90)90046-8

Cited by 17 publications

(10 citation statements)

References 3 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The importance map generator INIPOND module of TRIPOLI-4 can also be used to improve the variance reduction performance and to reduce the user involvement, especially for the neutron deep penetration cases [3][4][5][6][7][8]. The generated important map is then used by TRIPOLI-4 in the same run to perform importance sampling through the exponential transform method, quota sampling, splitting and Russian roulette, and source biasing.…”

Section: Tripoli-4 Variance Reduction Techniquesmentioning

confidence: 99%

“…The β and K parameters of the INIPOND module were usually set in order to adjust the global strength of the "biasing" by the exponential transform techniques [4,7]. When using the INIPOND AUTO option, the values K were calculated in the code according to the β input by solving the Placzeck equation, after collapsing the pointwise cross-sections in each composition and each energy group.…”

Section: Tripoli-4 Variance Reduction Techniquesmentioning

confidence: 99%

“…For the neutron activation calculation of shielding and structure materials of nuclear facilities, the knowledge of 3D neutron flux map and the energy spectra must be first investigated. In this kind of neutron deep penetration calculation in shielding, variance reduction techniques are necessary in order to reduce the uncertainty of the Monte-Carlo calculations [3,4]. Different water shielding benchmarks are available from the OECD/NEA SINBAD database.…”

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Neutron Deep Penetration Calculations in Light Water with Monte Carlo TRIPOLI-4® Variance Reduction Techniques

Lee

2017

EPJ Web Conf.

View full text Add to dashboard Cite

Nuclear decommissioning takes place in several stages due to the radioactivity in the reactor structure materials. A good estimation of the neutron activation products distributed in the reactor structure materials impacts obviously on the decommissioning planning and the low-level radioactive waste management. Continuous energy Monte-Carlo radiation transport code TRIPOLI-4 has been applied on radiation protection and shielding analyses. To enhance the TRIPOLI-4 application in nuclear decommissioning activities, both experimental and computational benchmarks are being performed. To calculate the neutron activation of the shielding and structure materials of nuclear facilities, the knowledge of 3D neutron flux map and energy spectra must be first investigated. To perform this type of neutron deep penetration calculations with the Monte Carlo transport code, variance reduction techniques are necessary in order to reduce the uncertainty of the neutron activation estimation. In this study, variance reduction options of the TRIPOLI-4 code were used on the NAIADE 1 light water shielding benchmark. This benchmark document is available from the OECD/NEA SINBAD shielding benchmark database. From this benchmark database, a simplified NAIADE 1 water shielding model was first proposed in this work in order to make the code validation easier. Determination of the fission neutron transport was performed in light water for penetration up to 50 cm for fast neutrons and up to about 180 cm for thermal neutrons. Measurement and calculation results were benchmarked. Variance reduction options and their performance were discussed and compared.

show abstract

Section: Tripoli-4 Variance Reduction Techniquesmentioning

confidence: 99%

Section: Tripoli-4 Variance Reduction Techniquesmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

Neutron Deep Penetration Calculations in Light Water with Monte Carlo TRIPOLI-4® Variance Reduction Techniques

Lee

2017

EPJ Web Conf.

View full text Add to dashboard Cite

show abstract

“…2005 in MCNP, Exponential Transform in TRIPOLI-4® [9] [10]). In MCNP, the automatic weight windows generator is used on fictitious geometry with cells having artificially reduced material densities (by a factor 0.1).…”

Section: Icrs-13 and Rpsd-2016mentioning

confidence: 99%

A Monte-Carlo Benchmark of TRIPOLI-4® and MCNP on ITER neutronics

et al. 2017

View full text Add to dashboard Cite

Abstract. Radiation protection and shielding studies are often based on the extensive use of 3D Monte-Carlo neutron and photon transport simulations. ITER organization hence recommends the use of MCNP-5 code (version 1.60), in association with the FENDL-2.1 neutron cross section data library, specifically dedicated to fusion applications. The MCNP reference model of the ITER tokamak, the 'C-lite', is being continuously developed and improved. This article proposes to develop an alternative model, equivalent to the 'C-lite', but for the Monte-Carlo code TRIPOLI-4®. A benchmark study is defined to test this new model. Since one of the most critical areas for ITER neutronics analysis concerns the assessment of radiation levels and Shutdown Dose Rates (SDDR) behind the Equatorial Port Plugs (EPP), the benchmark is conducted to compare the neutron flux through the EPP. This problem is quite challenging with regard to the complex geometry and considering the important neutron flux attenuation ranging from 10 14 down to 10 8 n•cm -2 •s -1 . Such code-to-code comparison provides independent validation of the Monte-Carlo simulations, improving the confidence in neutronic results.

show abstract

“…The TRIPOLI-4 [1][2][3] Monte Carlo transport code provides an efficient biasing scheme with minimal user input data [1,2,4,5] for such simulations. However, when dealing with coupled neutron-photon simulations, variance reduction techniques used for only one of these two particle types do not always reach enough efficiency concerning the photon tallies convergence: thus, TRIPOLI-4 users must sometimes request variance reduction techniques for both neutron and photon transport.…”

mentioning

confidence: 99%

Variance reduction adjustment in Monte Carlo TRIPOLI-4® neutron gamma coupled calculations

Petit

Lee²,

Diop³

2014

Progress in Nuclear Science and Technology

View full text Add to dashboard Cite

This paper presents a diagnosis tool for the users of the TRIPOLI-4 Monte Carlo transport code. The aim is to facilitate the adjustment of the variance reduction scheme when dealing with coupled neutron-photon simulations. Up to now, neutron and photon importance functions have been generated independently by TRIPOLI-4 when transport biasing for both particles was necessary, leading to further adjustments by the user after running a first coupled simulation. The idea is here to combine in a fast step the TRIPOLI-4 photon importance map on the one hand, and the photon production data used by the simulation on the other hand, so as to provide at once a better knowledge of important points of neutron phase space with respect to photon tallies. The highest neutron importance mesh cells are then derived and optionally displayed on geometry graphs. The user's intervention consists then in different possible options defining the neutron variance reduction scheme of the TRIPOLI-4 coupled simulation, in the light of the previous diagnosis results. Finally, coupled neutron-photon simulations involving polyethylene and stainless steel slabs are investigated: an example of use of this diagnosis tool is provided and figures of merit related to photon tallies are then compared.

show abstract

Automated importance generation and biasing techniques for Monte Carlo shielding techniques by the TRIPOLI-3 code

Cited by 17 publications

References 3 publications

Neutron Deep Penetration Calculations in Light Water with Monte Carlo TRIPOLI-4® Variance Reduction Techniques

Neutron Deep Penetration Calculations in Light Water with Monte Carlo TRIPOLI-4® Variance Reduction Techniques

A Monte-Carlo Benchmark of TRIPOLI-4® and MCNP on ITER neutronics

Variance reduction adjustment in Monte Carlo TRIPOLI-4® neutron gamma coupled calculations

Contact Info

Product

Resources

About