Výsledky vyhledávání - "R.E. Maerker"

Autor: R.E. Maerker, J.E. Horwedel, R.Q. Wright

A sensitivity analysis of EQ3, a computer code which has been proposed to be used as one link in the overall performance assessment of a national high-level waste repository, has been performed. EQ3 is a geochemical modeling code used to calculate th

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::df97078fdc888e16b730b177e21b708b
https://doi.org/10.2172/7079359

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Application of the LEPRICON Unfolding Procedure to the Arkansas Nuclear One-Unit 1 Reactor

Autor: M. L. Williams, J.J. Wagschal, B. A. Worley, B.L. Broadhead, R.E. Maerker

Publikováno v: Nuclear Science and Engineering. 93:137-170

The development and demonstration of a new unfolding procedure involving pressure vessel surveillance dosimetry in pressurized water reactors are described. The complete methodology is contained in the LEPRICON code system, and provides techniques fo

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::f65b3c42991f0d81fc9fbb46752b3749
https://doi.org/10.13182/nse86-a17665

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Accounting for Changing Source Distributions in Light Water Reactor Surveillance Dosimetry Analysis

Autor: R.E. Maerker, B.L. Broadhead, M. L. Williams

Publikováno v: Nuclear Science and Engineering. 94:291-308

A technique is described to account for effects of space- and time-dependent core source variations on pressure vessel surveillance dosimetry analysis. The procedure first defines an easily implemented geometry for a single adjoint transport calculat

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::5d123fbf5e9d6f6829e28726d449485a
https://doi.org/10.13182/nse86-a18342

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Validation of neutron transport calculations in benchmark facilities for improved damage fluence predictions

Autor: F.W. Stallmann, F.B.K. Kam, M.L. Williams, R.E. Maerker

Publikováno v: Nuclear Engineering and Design. 86:87-91

Neutron transport calculations play a vital role in the determination of the amount of radiation damage accumulated by reactor pressure vessels, and hence are an important factor in establishing reactor lifetime. Benchmark experiments are required to

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::a525b9f70d0a9f2b6118d6f73afea5e0
https://doi.org/10.1016/0029-5493(85)90212-2

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Theory of a New Unfolding Procedure in Pressurized Water Reactor Pressure Vessel Dosimetry and Development of an Associated Benchmark Data Base

Autor: J.J. Wagschal, B.L. Broadhead, R.E. Maerker

Publikováno v: Nuclear Science and Engineering. 91:369-392

The theory of a new methodology for quantifying and then reducing the uncertainties in the pressure vessel fluences (or fluxes) of a pressurized water reactor (PWR) is described. The theory involves combining the results of calculated and measured do

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::789c824610af6a03ba013d13abfb2748
https://doi.org/10.13182/nse85-a18355

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Calculation of Doubly Differential Current Albedos for Epicadmium Neutrons Incident on Concrete and Comparison of the Reflected Subcadmium Component with Experiment

Autor: R.E. Maerker, W. A. Coleman, F.J. Muckenthaler, P. N. Stevens

Publikováno v: Nuclear Science and Engineering. 27:411-422

Extensive Monte Carlo calculations were performed to determine the distribution in energy and angle of neutrons reflected from steel-reinforced concrete for five incident directions and ten inciden...

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::d0a136ae9b9fe59406c5bfe8c59423ef
https://doi.org/10.13182/nse67-a18280

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SB3. Experiment on secondary gamma-ray production cross sections averaged over a fast-neutron spectrum for each of 13 different elements plus a stainless steel

Autor: R.E. Maerker

The experimental and calculational details for a CSEWG integral data testing shielding experiment are presented. This particular experiment measured the secondary gamma-ray production cross sections averaged over a fast-neutron spectrum for iron, oxy

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::290354a24209fe4aa8e8be7af21f853b
https://doi.org/10.2172/4073726

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Uncertainty Analysis of Benchmark Dosimetry Measurements

Autor: R.E. Maerker, J. J. Wagschal, B.L. Broadhead

Publikováno v: Nuclear Data for Science and Technology ISBN: 9789400971011

The joint consistency of a series of measured quantities and their calculated counterparts is defined. Ten measurements of average cross-sections or average cross-section ratios in benchmark 252Cf spontaneous fission neutron fields are analyzed. The

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::c77150881cfefd805185f50d5482de2b
https://doi.org/10.1007/978-94-009-7099-1_94

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