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Oral presentation

Remarks and validation on shielding group constants

Konno, Chikara

no journal, , 

The self-shielding correction is very important for shielding group constants, but the adequate correction method of the self-shielding is not always known well. In this workshop I will explain the adequate correction method of the self-shielding and key points in using shielding group constants. Moreover accuracy of shielding group constants will be described.

Oral presentation

Current status of PHITS and development of analysis function

Hashimoto, Shintaro

no journal, , 

PHITS can simulate a behavior of various radiation particles such as neutrons. The number of users is more than 4,000 in the world. For further spread of PHITS, we have validated the reliability and developed useful functions. Recently, we performed a benchmark study by comparing experimental data for various cases, and confirmed the reliability quantitatively. We implemented dose conversion factors, which were shown in ICRP Publication 116 and 123, into PHITS. By using this function, PHITS users can evaluate easily various effective doses and dose equivalents for shielding design of accelerator facilities or study of radiation protection. We are developing analysis functions; estimation of systematic uncertainties related to errors of input information, dependence on input information such as source energies, and convergence as the number of trials increases. We will introduce the current status of PHITS and the analysis functions implemented later.

Oral presentation

Present status of PHITS development for radiation shielding

Iwamoto, Yosuke

no journal, , 

PHITS is a general purpose Monte Carlo particle transport simulation code developed under collaboration between JAEA and several other institutes. It can deal with the transport of all particles in all materials. Main improvement related with radiation shielding are as follows: implementing function for reading high-energy nuclear data library JENDL-4.0/HE and dealing of xyz mesh in [weight window], [t-wwg] and [t-dchain]. It is enable us to calculate neutron energy spectrum for proton-light target nuclear reaction using JENDL-4.0/HE and calculate neutron transport in the shield without division of defined region. In this time, we will present feature of main improvement and their application to shielding calculations.

Oral presentation

Decommissioning and waste management for research facilities

Tsuji, Tomoyuki

no journal, , 

no abstracts in English

Oral presentation

Development of nuclear data processing code FRENDY

Tada, Kenichi

no journal, , 

JAEA has been developed the nuclear data processing code FRENDY to process the evaluated nuclear data library JENDL. FRENDY version 1 was released as a open source software. The processing method of FRENDY is similar to that of NJOY. Author investigated the processing method of NJOY and found some problems. Development of FRENDY is also contributed to improve the nuclear data processing method. This presentation explains the overview of FRENDY.

Oral presentation

History and status of JENDL

Iwamoto, Osamu

no journal, , 

no abstracts in English

Oral presentation

Activity evaluation method for accelerator facilities

Matsuda, Norihiro

no journal, , 

no abstracts in English

Oral presentation

JENDL special purpose file and activation cross section

Iwamoto, Osamu

no journal, , 

no abstracts in English

Oral presentation

Overview of the DCHAIN-PHITS activation code and its application in accelerator environments

Ratliff, H.

no journal, , 

This presentation serves as an introduction to using DCHAIN with PHITS for modeling accelerator activation problems. The core methodology behind DCHAIN-PHITS, in terms of the mathematic principles and how the codes are connected on a practical level, is discussed followed by highlighting what decisions can be made (what options are available) when assembling a problem and assessing its output. This includes choices such as geometry type (region/xyz/tetrahedral mesh), designation of irradiation schedule and output times, determining what data libraries to use, and more. The contents of the most important output files is described along with an example demonstrating use of DCHAIN-PHITS in an accelerator-like environment.

Oral presentation

Activities on the OECD/NEA shielding integral experimental database SINBAD

Tsuda, Shuichi

no journal, , 

The Shielding Integral Benchmark Archive Database (SINBAD) is managed by Nuclear Energy Agency (NEA) in Organisation for Economic Co-operation and Development (OECD), and widely used as benchmark data for verification of simulation codes of shielding calculations in accelerator facilities. Activities for reviewing uncertainties of data registered in SINBAD have been ongoing since 2018 to improve the reliability of SINBAD, and more collaborations of experts from shielding field are needed. This presentation in this workshop will provide information of the current status of SINBAD and the recent activity of its technical review group that is indispensable for completing reliable database.

Oral presentation

Demonstration of radiation imaging at Fukushima Daiichi Nuclear Power Station

Sato, Yuki

no journal, , 

no abstracts in English

Oral presentation

Radionuclide databases used for dosimetry calculations; DECDC and DECDC2

Endo, Akira

no journal, , 

Radiation shielding calculations for radionuclides require radionuclide-specific data on half-lives, and energies and intensities of radiations emitted during nuclear decay. For the information, radionuclide databases developed by the International Commission on Radiological Protection (ICRP) and the Society of Nuclear Medicine and Molecular Imaging (SNMMI) have been used in the fields of radiological protection and nuclear medicine. This presentation reviews historical development of these databases dating back to the 1970s, the features and utilization of the databases currently in use, and prospects for these databases, together with the efforts of development of the databases performed at JAEA.

Oral presentation

G(E) function for calculating dose rate from pulse height spectra in gamma-ray measurement

Tsuda, Shuichi

no journal, , 

The car-borne survey system KURAMA-II has been used for dose rate mapping in the environment after the Fukushima Dai-ichi Nuclear Power Plant accident. The dose rate on the road is calculated by multiplying the pulse-height spectra of the on-board CsI(Tl) scintillation detector by the spectrum-dose conversion operator (G(E) function), which is determined from the response functions for monoenergetic gamma-rays and the dose conversion coefficients. In this study, we calculated the G(E) function for CsI(Tl) scintillation detectors with various crystal shapes using the PHITS code, and investigated the dependence of the dose rate on the incident direction of gamma-rays. The directional characteristics of the CsI(Tl) scintillation detector and the calculation of the gamma-ray energy spectrum using the unfolding method will be presented, as well as the introduction of the G(E) function.

Oral presentation

Evaluated nuclear data library JENDL-5

Iwamoto, Osamu

no journal, , 

no abstracts in English

Oral presentation

On radiation detector study at Kyoto University

Kanno, Ikuo

no journal, , 

no abstracts in English

16 (Records 1-16 displayed on this page)
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