Radial and Azimuthal 235U Fission and 238U Capture Distributions in BWR UO2 Pins: CASMO-4 and MCNP4C versus Activation Foil Measurements

Macku, K.; Jatuff, F.; Murphy, Mike; Plaschy, M.; Grimm, P.; Joneja, Om Prakash; Chawla, R.

doi:10.13182/nse07-a2647

Cited by 14 publications

(8 citation statements)

References 3 publications

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“…Neutron measurements with high spatial resolution are paramount for the investigation of complex in-core phenomena and for the validation of modern high-fidelity neutron transport codes. Highly-resolved experiments have been performed in the past in the zero-power research reactor PROTEUS, operated at Paul Scherrer Institut (PSI) from 1968 to 2011, by means of neutron activation techniques [1], [2], [3] or standard reactor instrumentation like miniature fission chambers [4]. The idea to perform extensive investigations of threedimensional static and dynamic in-core phenomena in research reactors [5], [6] triggered the development of advanced neutron detection techniques for highly localized measurements.…”

Section: Introductionmentioning

confidence: 99%

Developing and testing a miniature fiber-coupled scintillator for in-core neutron counting in CROCUS

et al. 2020

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An advanced neutron detection system for highly localized measurements in nuclear reactor cores was developed and tested in the Laboratory for Reactor Physics and System Behaviour (LRS) at the École polytechnique fédérale de Lausanne (EPFL), Switzerland, in close collaboration with the Detector group of the Laboratory for Particle Physics (LTP) at the Paul Scherrer Institute (PSI), Switzerland. The miniature-size detector is based on the coupling of a ZnS:6LiF scintillator/converter screen of 1 mm2 and 0.2 mm thickness with a 10-m optical fiber, the latter being connected to a silicon photomultiplier (SiPM). In this development version, the output signal is processed via analog read-out electronics. The present work documents the characterization of a detection system prototype in the mixedradiation fields o f t he C ARROUSEL f acility a nd i ts t esting in the CROCUS zero-power reactor operated at LRS. The fibercoupled scintillator shows a linear response with the reactor power increase up to 6.5 W (i.e. around 108 cm-2s-1 total neutron flux), with a s ubsequent l oss o f l inearity d ue t o e lectronic dead time of the analog system. Nevertheless, the detector shows excellent neutron counting capabilities whether compared to other localized detection systems available at LRS, e.g. miniature fission chambers and an sCVD diamond detector.

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Section: Introductionmentioning

confidence: 99%

Developing and testing a miniature fiber-coupled scintillator for in-core neutron counting in CROCUS

et al. 2020

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“…In order to validate the approach, intra-pellet neutron flux distribution measurements and uncertainty estimation should be conducted. However, there are few critical experiments that can validate the approach, because an intra-pellet neutron flux distribution measurement requires expensive cost and complex experimental procedure such as gamma rays tomography technique [5,6].…”

Section: Introductionmentioning

confidence: 99%

Intra-pellet neutron flux distribution measurements in LWR critical lattices

Yoshioka

Kikuchi

Gunji

et al. 2013

Journal of Nuclear Science and Technology

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We have developed inexpensive and easy-handling measurement methods on intra-pellet neutron flux. A foil activation method with metallic foils, which were fabricated by punching out technique and etching technique to reduce fabrication error and positioning error, was used for the intra-pellet neutron flux distribution measurement. The developed method was applied to measure intra-pellet neutron flux distributions in a reduced-moderation light water reactor (LWR) lattices, and uncertainty of the distributions was estimated to be 1% to 2%. Measured values were analyzed with a continuous energy Monte Carlo code.Comparison of measurements and analyses revealed that the developed method is useful for the validation of an advanced fuel design method considering neutron behavior in fuel pellets.

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“…It should be mentioned that a comparison of experimental results with high-precision Monte Carlo reaction rate predictions provides useful complementary information in the benchmarking of deterministic reactor calculations. In the context of the current measurements, the benchmarking of LWR deterministic design tools and the role of MCNP calculations have been presented elsewhere [8]. The three different copper foil activation techniques employedstandard foil punching, spirals, and LIGA foils-are discussed in Section 3.…”

Section: Introductionmentioning

confidence: 99%

Advanced foil activation techniques for the measurement of within-pin distributions of the 63Cu(n,γ)64Cu reaction rate in nuclear fuel

Macku

Jatuff

Murphy

et al. 2006

Nuclear Instruments and Methods in Physics Research Section A:

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Radial and Azimuthal ²³⁵U Fission and ²³⁸U Capture Distributions in BWR UO₂ Pins: CASMO-4 and MCNP4C versus Activation Foil Measurements

Cited by 14 publications

References 3 publications

Developing and testing a miniature fiber-coupled scintillator for in-core neutron counting in CROCUS

Developing and testing a miniature fiber-coupled scintillator for in-core neutron counting in CROCUS

Intra-pellet neutron flux distribution measurements in LWR critical lattices

Advanced foil activation techniques for the measurement of within-pin distributions of the 63Cu(n,γ)64Cu reaction rate in nuclear fuel

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