Intercomparison of Predicted Displacement Rates Based on Neutron Spectrum Adjustments (REAL-80 Exercise)

Zijp, W.L.; Zsolnay, E.M.; Nolthenius, H. J.; Szondi, E. J.; Verhaag, Gerardus C. H. M.

doi:10.13182/nt84-a33517

Cited by 4 publications

(1 citation statement)

References 5 publications

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“…The energy group structure includes 640 groups with a total energy span of 10 -10 MeV to 20 MeV. This group structure has 45 energy groups per energy decade below 1 MeV and a group width of 100 keV above 1 MeV [8]. The dimensions of the modelled detector in the center are 6 x 6 cm, which corresponds with the stilbene detector used in real experiments.…”

Section: B Models and Calculationsmentioning

confidence: 99%

Position evaluation of ex-core neutron flux measurement in new type graphite reactors

Vilimova

Peltan

Škoda³

2021

EPJ Web Conf.

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Several concepts of new reactors use graphite. Some of them use graphite as a moderator, some of them as a reflector. There are at least two concepts of these graphitetype reactors under development in the Czech Republic. Both reactors use graphite as the reflector. An in-core measurement might be impossible to use because of various reasons, for instance, high temperature or aggressive environment. Therefore, this article focuses on ex-core neutron flux measurement system placed in the graphite reflector and the optimization of ex-core detector position. A set of experiments were performed at LR-0 reactor. The LR-0 is a light water reactor with a well-defined neutron field, which can be used for different material insertion tests and testing of its influence on criticality. Several modifications of LR-0 cores were modelled in Monte Carlo codes Serpent and KENO. A set of calculations were performed for verification of the criticality and neutron flux course in the reactor core and graphite reflector. Further investigation was focused on the influence of the presence of a graphite reflector on the neutron distribution in the reactor core. The LR-0 graphite experiments were also used to verify the calculations. Based on the results of this article, the optimal position of ex-core detectors in the graphite reflector is proposed.

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Section: B Models and Calculationsmentioning

confidence: 99%

Position evaluation of ex-core neutron flux measurement in new type graphite reactors

Vilimova

Peltan

Škoda³

2021

EPJ Web Conf.

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Plans for a REAL-84 Exercise

et al. 1985

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Experimental and numerical calibration of the neutron activation system on the FTU tokamak

Angelone

Batistoni

Bertalot

et al. 1990

Review of Scientific Instruments

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A benchmark experiment has been performed for the absolute calibration of the FTU tokamak neutron activation system with the purpose of comparing experimental and numerical absolute reaction rates. Indium samples have been activated by a 252Cf neutron source located on the torus axis at three different toroidal angles with respect to the irradiation ends. The same experimental arrangements have been simulated with the Monte Carlo neutron and photon transport code MCNP, in order to reproduce numerically the experimental results. The comparison was intended to assess the accuracy of the numerical simulation and of the modeling of the FTU device. The activation technique will be routinely used as a complementary method to the use of neutron counters for the determination of the absolute neutron yield. An agreement within 22% between experiment and calcul.ation has been found, showing that the model used in MCNP provides an acceptable representation for FTU.

show abstract

Intercomparison of Predicted Displacement Rates Based on Neutron Spectrum Adjustments (REAL-80 Exercise)

Cited by 4 publications

References 5 publications

Position evaluation of ex-core neutron flux measurement in new type graphite reactors

Position evaluation of ex-core neutron flux measurement in new type graphite reactors

Plans for a REAL-84 Exercise

Experimental and numerical calibration of the neutron activation system on the FTU tokamak

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