Reactor radiation skyshine calculations with TRIPOLI-4 code for Baikal-1 experiments

Fusion Engineering and Design

2019

Self Cite

For the future ITER (International Thermonuclear Experimental Reactor) operation needs, D-T fusion experiments named DTE2 will be conducted in 2019 at JET (Joint European Torus). During the DTE2 operations, 14 MeV fusion neutrons will be generated. One of the aims of the DTE2 neutronics experiments is to investigate the D-T neutron streaming along the penetrations of biological shield of the JET Torus Hall. The TRIPOLI-4 Monte-Carlo radiation transport code has been extensively used on radiation shielding analyses. The purpose of this study is to evaluate the variance reduction (VR) techniques of TRIPOLI-4 on the 14 MeV neutron streaming calculations for JET-like maze entrance. A JET-like torus hall building of 40 m x 40 m and a maze entrance of 11.8 m length in 5-section configuration of concrete were first modeled. The new developed VR method AMS (Adaptive Multilevel Splitting) was then presented and discussed. Using the single-step approach combined with AMS techniques, the TRIPOLI-4 calculations results including neutron flux and ambient dose equivalent maps, the VR performance, and the user-friendly AMS input of TRIPOLI-4 code were reported.

Section: Calculation Resultsmentioning

confidence: 99%

14 MeV neutron streaming calculations for JET-like maze entrance using TRIPOLI-4 Monte Carlo code

Fusion Engineering and Design

2019

Self Cite

“…Individual dose equivalent rates of Hp(10, 0 deg) and Hp (10, 45 deg) were also calculated in a slab phantom of ICRU soft tissue [10]. In addition, ambient dose equivalent rates of H* (10) were evaluated by using the flux-to-dose conversion coefficients implemented in TRIPOLI-4 [11][12][13]. But the beta rays and the secondary electron transport were not applied on those previous analyses.…”

Section: Introductionmentioning

confidence: 99%

Organ Dose Calculations Using ICRP Adult Voxel Phantoms and TRIPOLI-4 Monte Carlo Code

Journal of Nuclear Engineering and Radiation Science

2020

Self Cite

The ICRP 110 adult male and female voxel phantoms are the official computational models representing the ICRP Reference Male and Reference Female. In 2018 the Working Group 6 (WG6) of European Radiation Dosimetry Group (EURADOS) organized a study on the usage of the ICRP voxel reference phantoms. Organ dose calculation tasks with radiation transport codes were proposed in occupational and environmental dosimetry for nuclear engineering application. The TRIPOLI-4 Monte Carlo radiation transport code has been widely used in radiation shielding, criticality safety and reactor physics fields for supporting French nuclear energy research and industrial applications. To enhance the application fields of TRIPOLI-4, the 2018 EURADOS-WG6 voxel phantom tasks are being taken into account by using different features of TRIPOLI-4 code. In this work, the ICRP reference voxel phantoms were first adapted into TRIPOLI-4. More than 14 million voxels were represented in a mixed lattice geometry including 140 organs-tissues and 52 tissue media. Diverse exposure scenarios were then investigated by using Co-60 and Am-241 gamma-ray sources, N-16 beta source, and 10 keV neutron source. The TRIPOLI-4 standard nuclear data library was utilized on these neutron, photon, electron, and positron coupled transport calculations. Energy deposition estimators for electron, neutron, and photon coupled with mesh tally options were used to calculate the organ absorbed dose DT and the effective dose E. TRIPOLI-4 calculation methods and primary results for the 2018 EURADOS-WG6 voxel phantom organ dose study tasks are reported here.

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

Fusion Engineering and Design

2016

Self 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.