Numerical benchmarks TRIPOLI−MCNP with use of MCAM on FNG ITER bulk shield and FNG HCLL TBM mock-up experiments

Fausser, C.; Lee, Yi-Kang; Villari, R.; Zeng, Qin; Serikov, A.; Trama, Jean-Christophe; Gabriel, Franck

doi:10.1016/j.fusengdes.2011.04.018

Cited by 14 publications

(5 citation statements)

References 11 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…For supporting the neutronics study of the ITER TBM with the TRIPOLI-4 code, previous studies [4,7] and this study demonstrate TRIPOLI-4's capability to calculate the TBR and the neutron leakage multiplication.…”

Section: Neutron Leakage Multiplications Calculation With Tripoli-4 Msupporting

confidence: 56%

“…TBM mock-up benchmarks have been taken into account to validate the code and its associated nuclear data libraries for tritium production calculations [7]. But current calculation studies with beryllium on fission criticality, neutron leakage spectra, and TBR benchmarks show a trend of underestimation of neutron multiplications with JEFF-3.1 library [4,8].…”

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

Analysis of the KANT experiment on beryllium using TRIPOLI-4 Monte Carlo code

Lee

2011

Fusion Engineering and Design

Self Cite

View full text Add to dashboard Cite

Section: Neutron Leakage Multiplications Calculation With Tripoli-4 Msupporting

confidence: 56%

Section: Introductionmentioning

confidence: 99%

Analysis of the KANT experiment on beryllium using TRIPOLI-4 Monte Carlo code

Lee

2011

Fusion Engineering and Design

Self Cite

View full text Add to dashboard Cite

“…TRIPOLI-4 ® on two benchmarks TRIPOLI-4 ® is a continuous-energy radiation transport Monte Carlo code developed since mid-90s at CEA-Saclay and devoted to shielding, reactor physics with depletion, criticalitysafety and nuclear instrumentation for both fission and fusion systems. It is used as a reference code by the main french nuclear companies [12] and benefits from a very large verification and validation database gathering more than 1000 experimental benchmarks (ICSBEP benchmarks [21], reactor physics experiments [22]) as well as from many comparison to the US reference Monte Carlo code MCNP (see for instance [23]). It is qualified for various applications (criticality-safety, burn-up credit, reactor physics, etc.…”

Section: Methods: Comparing Geant4 Tomentioning

confidence: 99%

Improvement of Geant4 Neutron-HP package: from methodology to evaluated nuclear data library

Thulliez,

Jouanne,

Dumonteil

2021

Preprint

View full text Add to dashboard Cite

An accurate description of interactions between thermal neutrons (below 4 eV) and materials is key to simulate the transport of neutrons in a wide range of applications such as criticality-safety, reactor physics, compact accelerator-driven neutron sources, radiological shielding or nuclear instrumentation, just to name a few. While the Monte Carlo transport code Geant4 was initially developed to simulate particle physics experiments, its use has spread to neutronics applications, requiring evaluated cross-sections for neutrons and gammas between 0 and 20 MeV (the so-called neutron High Precision -HP-package), as well as a proper offline or on-the-flight treatment of these cross-sections. In this paper we will point out limitations affecting Geant4 (version 10.07.p01) thermal neutron treatment and associated nuclear data libraries, by using comparisons with the reference Monte Carlo neutron transport code TRIPOLI-4 ® , version 11, and we will present the results of various modifications of the Geant4 neutron-HP package, required to overcome these limitations. Also, in order to broaden the support of nuclear data libraries compatible with Geant4, a nuclear processing tool has been developed and validated allowing the use of the code together with ENDF-BVIII.0 and JEFF-3.3 libraries for example. These changes should be taken into account in an upcoming Geant4 release.

show abstract

“…The TRIPOLI-4 Monte Carlo radiation transport code has been widely used in radiation shielding, criticality safety and fission reactor physics fields to support French nuclear energy research and industrial applications [4]. Based on the international benchmarks and the CEA internal measurements, extensive validation studies of TRIPOLI-4 on nuclear heating of research reactors, radiation damage of reactor grade steels, neutron dosimeter activation analysis, shielding materials optimization, time-of-flight D-T neutron experiments, and reactor radiation skyshine calculations have been performed [11][12][13][14][15][16][17].…”

Section: Tripoli-4 Neutron and Gamma Calculationsmentioning

confidence: 99%

Analysis of the ITER computational shielding benchmark with the Monte Carlo TRIPOLI-4® neutron gamma coupled calculations

Lee

2016

Fusion Engineering and Design

Self Cite

View full text Add to dashboard Cite

With the growing interest in using the continuous-energy TRIPOLI-4 ® Monte Carlo radiation transport code for ITER applications, a key issue that arises is whether or not the released TRIPOLI-4 code and its associated nuclear data libraries are verified and validated for the D-T fusion neutronics calculations. Previous published benchmark results of TRIPOLI-4 code on the ITER related activities have concentrated on the first wall loading, the reactor dosimetry, the nuclear heating, and the tritium breeding ratio. To enhance the TRIPOLI-4 verification and validation on neutron-gamma coupled calculations for fusion device application, the computational ITER shielding benchmark of M. E. Sawan was performed in this work by using the 2013 released TRIPOLI-4.9S code and the associated CEA-V5.1.1 data library. First wall, blanket, vacuum vessel and toroidal field magnet of the inboard and outboard components were fully modelled in this 1-D toroidal cylindrical benchmark. The 14.1 MeV source neutrons were sampled from a uniform isotropic distribution in the plasma zone. Nuclear responses including neutron and gamma fluxes, nuclear heating, and material damage indicator were benchmarked against previous published results. The capabilities of the TRIPOLI-4 code on the evaluation of above physics parameters were presented. The nuclear data library from the new FENDL-3.0 evaluation was also benchmarked against the CEA-V5.1.1 results for the neutron transport calculations. In general, relevant benchmark results were obtained. Both data libraries can thus be run with TRIPOLI-4 for the fusion neutronics study. This work also demonstrates that the "safety factors" concept is necessary in the nuclear analyses of ITER.

show abstract

Numerical benchmarks TRIPOLI−MCNP with use of MCAM on FNG ITER bulk shield and FNG HCLL TBM mock-up experiments

Cited by 14 publications

References 11 publications

Analysis of the KANT experiment on beryllium using TRIPOLI-4 Monte Carlo code

Analysis of the KANT experiment on beryllium using TRIPOLI-4 Monte Carlo code

Improvement of Geant4 Neutron-HP package: from methodology to evaluated nuclear data library

Analysis of the ITER computational shielding benchmark with the Monte Carlo TRIPOLI-4® neutron gamma coupled calculations

Contact Info

Product

Resources

About