DOT-IV two-dimensional discrete ordinates transport code with space-dependent mesh and quadrature. [In FORTRAN for IBM 360, 370, 3033, and CDC 7600, CYBER 176 and STAR 100]

Rhoades, W.A.; Simpson, D.B.; Childs, R.L.; Engle, W.W.

doi:10.2172/6358599

Cited by 4 publications

(4 citation statements)

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“…The reference values are calculated from the single adjoint neutron flux calculation for the first operational cycle. They were determined using old Sailor (Simmons and Roussin, 1983) nuclear data library and 2D deterministic calculation with the DOT-4.2 code (Rhoades et al, 1979). However, the power range detectors used for the measurements of the control rod worth actually measure the 10 B(n,α) reaction rate and not the total neutron flux at their position.…”

Section: Neutron Flux Redistribution Factorsmentioning

confidence: 99%

“…The neutron flux redistribution factors currently used at the Krško NPP were obtained using a single adjoint flux distribution calculation for the first operational cycle (Kromar et al, 2015). The calculation was performed using the deterministic 2D code DOT (Rhoades et al, 1979) and therefore could not accurately describe the geometry. The first operational cycle, unlike subsequent cycles, had fresh fuel at the periphery of the core, resulting in about 30% higher neutron leakage out of the core.…”

Section: Introductionmentioning

confidence: 99%

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Determination of neutron flux redistribution factors for a typical pressurized water reactor ex-core measurements using Monte Carlo technique

et al. 2023

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In a typical pressurized water reactor, neutron detectors located outside the reactor core monitor reactor power. In addition, they are also used to measure the reactivity of the control rods. A novel approach to calculate the ex-core neutron detector response in a typical pressurized water reactor using the Monte Carlo technique is presented. A detailed ex-core model of the Krško nuclear power plant was developed using the Monte Carlo neutron transport code MCNP. Due to the location of the ex-core neutron detectors, the hybrid code ADVANTG is used to generate variance reduction parameters to accelerte the convergence of the results outside the reactor core. To use ADVANTG, the fixed neutron source had to be reconstructed from the criticality core calculation. This paper presents the sensitivity analysis of the response of the ex-core detectors to the neutron data libraries used, the description of the fixed neutron source and the ADVANTG parameters. It was found that a pin-wise description of the neutron source for at least two rows of fuel assemblies at the core periphery is necessary for accurate results. Our results show the importance of a correct description of the prompt neutron spectra in the high energy region and the impact this has on the response of the ex-core detectors. The method in which the prompt neutron fission spectra for important fission nuclides are weighted by the calculated reaction rates has been shown to be the best approximation, with deviations from the reference calculation within statistical uncertainty. The effect of nuclear data libraries on the response of the ex-core detector was investigated, and the difference between the ENDF/B-VII.0 and the ENDF/B-VIII.0 nuclear data libraries was ∼11%. When the deficient evaluation of the 56Fe isotope included in the ENDF/B-VIII.0 nuclear data library was replaced by the improved evaluation from the IAEA INDEN project, the differences decreased to ∼3.7%. In addition, neutron flux redistributions due to control rod movement were investigated and flux redistribution factors were updated using Monte Carlo particle transport methods. The reaction rate redistribution factors obtained with methods presented in this paper are within 1% agreement with the currently used factors.

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Section: Neutron Flux Redistribution Factorsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Determination of neutron flux redistribution factors for a typical pressurized water reactor ex-core measurements using Monte Carlo technique

et al. 2023

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“…Mainframes introduced large powerful computers with a lot of memory accessed by many people at the same time (Christ, 2015). IBM dominated this market with its mainframes-IBM 360 and 370 since early 1860s until late 1970s (Rhoades, et al, 1979).…”

Section: Introductionmentioning

confidence: 99%

A Theoretical Framework for Ubiquitous Computing

Hashemi

Sadeghi‐Niaraki

2016

International Journal of Advanced Pervasive and Ubiquitous Computing

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You may forget where you left your keys when you need them. In ubiquitous computing space your keys will find you and inform you where they are. Ubiquitous computing, the third generation of computing spaces, following mainframes and personal computers, is in its incipient evolution steps. In ubiquitous computing space, sensors and computing nodes are invisibly, inconspicuously, and overwhelmingly embedded in all real-world objects and are all connected to each other through omnipresent wireless networks. The goal is to make real-world objects seem intelligent and autonomous in providing users with electronic and Internet services with users not even noticing how they are provided with these services. The real world, cyberspace, modeling, and mathematics are identified as the main constituents of ubiquitous computing in this study. These four areas are investigated one-by-one and in combination to show how they create a solid foundation for ubiquitous computing. An application of ubiquitous computing in car navigation systems is used to indicate the reliability of the proposed framework.

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“…Recently the DOT-IV discrete ordinates code, originally developed for coupled neutrongamma transport calculations, 8 was used to study radiative transfer through gray participating media in finite axisymmetrical enclosures. 9 The discrete ordinates solutions compared well with the available exact solutions.…”

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confidence: 99%

Heat transfer by combined conduction and radiation in axisymmetric enclosures

Yücel

Williams

1987

Journal of Thermophysics and Heat Transfer

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Combined conductive and radiative heat transfer through a gray, absorbing, emitting, and scattering medium with internal heat generation in a finite cylindrical enclosure is analyzed. The radiative transport equation is solved by the discrete ordinates method using the DOT-IV transport code, which is coupled to a compatible control-volume-based finite-difference code for the temperature field calculations. The coupled radiative transfer and the energy equations are solved by an iterative procedure. The effects of the conduction-radiation parameter, scattering, optical thickness, and wall emissivity on the medium temperatures and surface heat fluxes are discussed. Nomenclature a = aspect (half-height-to-radius) ratio, H/R I = dimensionless radiation intensity, i/4oT 4 w k = thermal conductivity N = conduction-radiation parameter, kp/4dT 3 w Q R = dimensionless radiative heat flux, q R /oT* w Q T = dimensionless total heat flux, q T /oT 4 w r -position vector T w = wall temperature U = dimensionless internal heat generation, up P = extinction coefficient, K 4-o e =wall emissivity 6 = dimensionless temperature, T/T W K = absorption coefficient o = scattering coefficient a = Stefan-Boltzmann constant r = optical distance, PS, s = r or z T R ,T H = optical depths in the r-, ^-direction, PR, PH fl = direction vector co = single scattering albedo, a/P V T = dimensionless gradient operator, P~l V

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DOT-IV two-dimensional discrete ordinates transport code with space-dependent mesh and quadrature. [In FORTRAN for IBM 360, 370, 3033, and CDC 7600, CYBER 176 and STAR 100]

Cited by 4 publications

References 0 publications

Determination of neutron flux redistribution factors for a typical pressurized water reactor ex-core measurements using Monte Carlo technique

Determination of neutron flux redistribution factors for a typical pressurized water reactor ex-core measurements using Monte Carlo technique

A Theoretical Framework for Ubiquitous Computing

Heat transfer by combined conduction and radiation in axisymmetric enclosures

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