Results 31 to 40 of about 15,370 (183)
RADIATION DAMAGE AND DPA IN IRON USING MCNP5 [PDF]
European Journal of Materials Science and Engineering, 2020 A Monte Carlo simulation code is developed for the study of neutron induced radiation damage in the materials which results from nuclear collision as well as reactions that create energetic recoil atoms of the host material or reaction creates.
Hiwa Mohammad QADR
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MCNP: Neutron benchmark problems [PDF]
, 1991 The recent widespread and increased use of radiation transport codes has produced greater user and institutional demand for assurances that such codes give correct results. Responding to these requirements for code validation, the general purpose Monte Carlo transport code MCNP has been tested on criticality, pulsed sphere, and shielding neutron ...
Whalen, D. J. +3 more
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Neutronic Evaluation of Using a Thorium Sulfate Solution in an Aqueous Homogeneous Reactor
Atom Indonesia, 2022 Radioisotope 99Mo is one of the most essential radioisotopes in nuclear medicine. Its production in an Aqueous Homogeneous Reactor (AHR) could be potentially advantageous compared to the traditional technology, based on target irradiation in a ...
D. Pérez +5 more
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, 1997 The Monte Carlo code MCNP-DSP was developed from the Los Alamos MCNP4a code to calculate the time and frequency response statistics obtained from subcritical measurements. The code can be used to simulate a variety of subcritical measurements including source-driven noise analysis, Rossi-{alpha}, pulsed source, passive frequency analysis, multiplicity,
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MCNP variance reduction overview [PDF]
, 2006 The MCNP code is rich in variance reduction features. Standard variance reduction methods found in most Monte Carlo codes are available as well as a number of methods unique to MCNP. We discuss the variance reduction features presently in MCNP as well as new ones under study for possible inclusion in future versions of the code.
Hendricks, J. S., Booth, T. E.
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Long Term Neutron Activation in JET DD Operation [PDF]
EPJ Web of Conferences, 2021 In the 2019 C38 Deuterium-Deuterium campaign at JET several different ITER-relevant materials and dosimetry foils were irradiated in a specially designed long-term irradiation station located inside the vacuum vessel with the purpose of testing the ...
Žohar Andrej +18 more
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Study on efficiency calibrating method of well-type γ ray spectrometer for soil samples
He jishu, 2021 BackgroundPutting samples into the well-type γ ray spectrometer can greatly improve the activity measurement efficiency, therefore it can reduce the measurement time and the mass of samples.PurposeThis study aims to accurately obtain detection ...
LAI Yongfang +4 more
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MCNP certification package [PDF]
, 1992 In response to a Department of Energy (DOE) request, Westinghouse Savannah River Company committed to certify all computer codes used in critical calculations at the site. Since the Monte Carlo Neutron Photon Transport (MCNP) code will be used to perform critical analyses involving criticality and shielding, the code must be certified. Certification as
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Mammographic Dosimetry Using MCNP-4B [PDF]
Journal of Nuclear Science and Technology, 2000 Three doses involved in the female breast, Adipose, Glandular and Total Doses, were calculated for different adipose tissue ratio and four breast thickness using MCNP-4B code. Glandular Dose is the most important contribution to the breast carcinogenesis risk.
G Verdú +5 more
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Underwater detection of dangerous substances: status the SABAT project [PDF]
, 2017 The Neutron Activation Analysis (NAA) plays an exceptional role in the modern nuclear engineering, especially in detection of hazardous substances. However, in the aquatic environment, there are still many problems to be solved for effective usage of ...
Moskal, P. +5 more
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