BOT3P: Bologna Radiation Transport Analysis Pre-Post-Processors Version 4.0

Orsi, Roberto

doi:10.13182/nse05-a2524

Cited by 11 publications

(3 citation statements)

References 3 publications

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“…Two computational methods are known to solve the Boltzmann equation, a deterministic method and the Monte Carlo method (MC). 4) With consideration of the popularity or reputation of a solver, we selected two works mainly intended for the former, BOT3P 5) and Attila 6) and others for the latter that are mostly code-specific, Moritz 7) /Vised 8) for MCNP 9) /MCNPX, 10) SimpleGEO for FLUKA, 11) and GGE for GEANT4.…”

Section: Discussion Of Development Issuesmentioning

confidence: 99%

TORTWARE:Development of an Input-Making Support System for a Three-Dimensional DeterministicS_NCode,TORT

Hirao

AHIKO

2010

Journal of Nuclear Science and Technology

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A preprocessor system TORTWARE has been developed to integrate the task of input data creation and management for the three-dimensional (3-D) radiation transport deterministic S N code, TORT. It consists of three component modules: 1) 3-D geometry mesh generator responsible for modeling, meshing, and displaying, in conjunction with a commercial CAD program, 2) an input contents creator used to edit and complete the input on a spreadsheet, and 3) a Web service that acts as an analysis information manager to manage all information concerning the analysis activity, featuring a user workbench and a case database. First, the role and purpose of the system is outlined. Second, in order to formulate our development policy concerning geometry or file management, important issues peculiar to the 3-D preprocessor of the transport code are discussed while existing preprocessor works are surveyed. Then, a system overview is shown and unique functions of each module are described including auto-meshing and simple mesh display. Finally, in order to demonstrate the usability and performance of these functions, a preprocessing example is shown for a tokamak-type fusion reactor model.

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Section: Discussion Of Development Issuesmentioning

confidence: 99%

TORTWARE:Development of an Input-Making Support System for a Three-Dimensional DeterministicS_NCode,TORT

Hirao

AHIKO

2010

Journal of Nuclear Science and Technology

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“…To avoid neg a tive neu tron fluxes and ob tain re li able re sults, EDW spa tial dif fer enc ing scheme is adopted. And a Car te sian struc tured grid con tain ing 520 ´ 322 ´ 58 meshes is con structed by GGTM [12]. For an gu lar discretization, we em ploy Legendre-Chebyshev quad ra ture set, which is de rived by set ting the po lar an gles equal to the roots of the Legendre poly no mial and the az i muthal an gles equal to the roots of Chebyshev poly no mi als.…”

Section: Trans Port Cal Cu La Tionmentioning

confidence: 99%

Evaluation of PWR pressure vessel fast neutron fluence benchmarks from NUREG/CR-6115 with ares transport code

Zhang

Liu

et al. 2017

NUCL TECH RAD PROT

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An ac cu rate eval u a tion of PWR pres sure ves sel fast neu tron fluence is es sen tial to en sure pressure ves sel in teg rity over the de sign life time. The dis crete or di nates method is one of the main meth ods to treat such prob lems. In this pa per, eval u a tions have been per formed for three PWR benchmarks de scribed in NUREG/CR-6115 us ing ARES trans port code. The cal cu lated results were com pared to the ref er ence val ues and a sat is fac tory agree ment was ob tained. In ad dition, the ef fects of S N nu meric and source dis tri bu tion mod el ing for pres sure ves sel fast neu tron fluence cal cu la tion are in ves ti gated. Based on the fine enough grids adopted, the dif fer ent spatial and an gu lar discretization in tro duces der i va tions less than 3 %, and fix-up for neg a tive scatter ing source causes no no tice able ef fects when cal cu lat ing pres sure ves sel fast neu tron fluence. How ever, the dis crep ancy of as sem bly-wise and pin-wise source mod el ing for pe riph eral as semblies reaches ~20 %, which in di cates that pin-wise mod el ing for pe riph eral as sem blies is es sential. These re sults pro vide guide lines for pres sure ves sel fast neu tron fluence cal cu la tion and dem on strate that the ARES trans port code is ca pa ble of per form ing neu tron trans port cal cu lations for eval u at ing PWR pres sure ves sel fast neu tron fluence.

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“…Figure 1 illustrates the geometry configuration modeled with GGTM. GGTM is a program which is included in the BOT3P software package and aimed at describing the geometry, the material, and the fixed neutron source for three-dimensional transport applications [7].…”

Section: Pressure Vessel Fast Neutron Fluence Calculationmentioning

confidence: 99%

Analysis for the Effect of Spatial Discretization Method on AP1000 Reactor Pressure Vessel Fluence Calculation

Zheng

Zhang

Shi

et al. 2016

Science and Technology of Nuclear Installations

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Maintaining the structural integrity of the reactor pressure vessel (RPV) is a critical concern related to the safe operation of nuclear power plants. To estimate the structural integrity over the designed lifetime and to support analyses for a potential plant life extension, an accurate calculation of the fast neutron fluence (E>1.0 MeV orE>0.1 MeV) at the RPV is significant. The discrete ordinates method is one of the main methods to solve such problems. During the calculation process, many factors will affect the results. In this paper, the deviations introduced by different differencing schemes and mesh sizes on the AP1000 RPV fast neutron fluence have been studied, which are based on new discrete ordinates code ARES. The analysis shows that the differencing scheme (diamond difference with or without linear zero fix-up, theta weighted, directional theta weighted, and exponential directional weighted) introduces a deviation within 4%. The coarse mesh (4 × 4 cm meshes inXYplane) leads to approximately 23.7% calculation deviation compared to those of refined mesh (1 × 1 cm meshes inXYplane). Comprehensive study on the deviation introduced by differencing scheme and mesh size has great significance for reasoned evaluation of RPV fast neutron fluence calculation results.

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BOT3P: Bologna Radiation Transport Analysis Pre-Post-Processors Version 4.0

Cited by 11 publications

References 3 publications

TORTWARE:Development of an Input-Making Support System for a Three-Dimensional DeterministicS_NCode,TORT

TORTWARE:Development of an Input-Making Support System for a Three-Dimensional DeterministicS_NCode,TORT

Evaluation of PWR pressure vessel fast neutron fluence benchmarks from NUREG/CR-6115 with ares transport code

Analysis for the Effect of Spatial Discretization Method on AP1000 Reactor Pressure Vessel Fluence Calculation

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BOT3P: Bologna Radiation Transport Analysis Pre-Post-Processors Version 4.0

Cited by 11 publications

References 3 publications

TORTWARE:Development of an Input-Making Support System for a Three-Dimensional DeterministicSNCode,TORT

TORTWARE:Development of an Input-Making Support System for a Three-Dimensional DeterministicSNCode,TORT

Evaluation of PWR pressure vessel fast neutron fluence benchmarks from NUREG/CR-6115 with ares transport code

Analysis for the Effect of Spatial Discretization Method on AP1000 Reactor Pressure Vessel Fluence Calculation

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TORTWARE:Development of an Input-Making Support System for a Three-Dimensional DeterministicS_NCode,TORT

TORTWARE:Development of an Input-Making Support System for a Three-Dimensional DeterministicS_NCode,TORT