Example of Science and Technology of Nuclear Installations format
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Example of Science and Technology of Nuclear Installations format Example of Science and Technology of Nuclear Installations format Example of Science and Technology of Nuclear Installations format Example of Science and Technology of Nuclear Installations format Example of Science and Technology of Nuclear Installations format Example of Science and Technology of Nuclear Installations format Example of Science and Technology of Nuclear Installations format
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open access Open Access

Science and Technology of Nuclear Installations — Template for authors

Publisher: Hindawi
Categories Rank Trend in last 3 yrs
Nuclear Energy and Engineering #34 of 66 down down by 4 ranks
journal-quality-icon Journal quality:
Medium
calendar-icon Last 4 years overview: 220 Published Papers | 365 Citations
indexed-in-icon Indexed in: Scopus
last-updated-icon Last updated: 19/06/2020
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Related Journals

open access Open Access

IEEE

Quality:  
High
CiteRatio: 3.5
SJR: 0.537
SNIP: 1.338
recommended Recommended

Royal Society of Chemistry

Quality:  
High
CiteRatio: 51.6
SJR: 14.486
SNIP: 4.922
open access Open Access

Elsevier

Quality:  
High
CiteRatio: 5.0
SJR: 1.123
SNIP: 1.381
open access Open Access

Elsevier

Quality:  
High
CiteRatio: 4.4
SJR: 1.324
SNIP: 0.995

Journal Performance & Insights

Impact Factor

CiteRatio

Determines the importance of a journal by taking a measure of frequency with which the average article in a journal has been cited in a particular year.

A measure of average citations received per peer-reviewed paper published in the journal.

0.825

24% from 2018

Impact factor for Science and Technology of Nuclear Installations from 2016 - 2019
Year Value
2019 0.825
2018 1.082
2017 0.939
2016 0.531
graph view Graph view
table view Table view

1.7

CiteRatio for Science and Technology of Nuclear Installations from 2016 - 2020
Year Value
2020 1.7
2019 1.7
2018 1.3
2017 1.2
2016 1.5
graph view Graph view
table view Table view

insights Insights

  • Impact factor of this journal has decreased by 24% in last year.
  • This journal’s impact factor is in the top 10 percentile category.

insights Insights

  • This journal’s CiteRatio is in the top 10 percentile category.

SCImago Journal Rank (SJR)

Source Normalized Impact per Paper (SNIP)

Measures weighted citations received by the journal. Citation weighting depends on the categories and prestige of the citing journal.

Measures actual citations received relative to citations expected for the journal's category.

0.417

8% from 2019

SJR for Science and Technology of Nuclear Installations from 2016 - 2020
Year Value
2020 0.417
2019 0.451
2018 0.488
2017 0.522
2016 0.708
graph view Graph view
table view Table view

0.718

15% from 2019

SNIP for Science and Technology of Nuclear Installations from 2016 - 2020
Year Value
2020 0.718
2019 0.842
2018 0.646
2017 0.727
2016 1.165
graph view Graph view
table view Table view

insights Insights

  • SJR of this journal has decreased by 8% in last years.
  • This journal’s SJR is in the top 10 percentile category.

insights Insights

  • SNIP of this journal has decreased by 15% in last years.
  • This journal’s SNIP is in the top 10 percentile category.

Science and Technology of Nuclear Installations

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Hindawi

Science and Technology of Nuclear Installations

Science and Technology of Nuclear Installations is an international scientific journal that aims to make available knowledge on issues related to the nuclear industry and to promote development in the area of nuclear sciences and technologies. The endeavour associated with the...... Read More

Energy

i
Last updated on
18 Jun 2020
i
ISSN
1687-6075
i
Impact Factor
Low - 0.453
i
Acceptance Rate
93%
i
Frequency
Not provided
i
Open Access
Yes
i
Sherpa RoMEO Archiving Policy
Green faq
i
Plagiarism Check
Available via Turnitin
i
Endnote Style
Download Available
i
Bibliography Name
unsrt
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Citation Type
Numbered
[25]
i
Bibliography Example
C. W. J. Beenakker. “Specular andreev reflection in graphene”. Phys. Rev. Lett., vol. 97, no. 6, 067007, 2006.

Top papers written in this journal

open accessOpen access Journal Article DOI: 10.1155/2008/798901
GRS Method for Uncertainty and Sensitivity Evaluation of Code Results and Applications

Abstract:

During the recent years, an increasing interest in computational reactor safety analysis is to replace the conservative evaluation model calculations by best estimate calculations supplemented by uncertainty analysis of the code results. The evaluation of the margin to acceptance criteria, for example, the maximum fuel rod cl... During the recent years, an increasing interest in computational reactor safety analysis is to replace the conservative evaluation model calculations by best estimate calculations supplemented by uncertainty analysis of the code results. The evaluation of the margin to acceptance criteria, for example, the maximum fuel rod clad temperature, should be based on the upper limit of the calculated uncertainty range. Uncertainty analysis is needed if useful conclusions are to be obtained from “best estimate” thermal-hydraulic code calculations, otherwise single values of unknown accuracy would be presented for comparison with regulatory acceptance limits. Methods have been developed and presented to quantify the uncertainty of computer code results. The basic techniques proposed by GRS are presented together with applications to a large break loss of coolant accident on a reference reactor as well as on an experiment simulating containment behaviour. read more read less

Topics:

Uncertainty analysis (64%)64% related to the paper, Source code (53%)53% related to the paper
View PDF
181 Citations
open accessOpen access Journal Article DOI: 10.1155/2013/702496
Radioactive Iodine and Krypton Control for Nuclear Fuel Reprocessing Facilities

Abstract:

The removal of volatile radionuclides generated during used nuclear fuel reprocessing in the US is almost certain to be necessary for the licensing of a reprocessing facility in the US. Various control technologies have been developed, tested, or used over the past 50 years for control of volatile radionuclide emissions from ... The removal of volatile radionuclides generated during used nuclear fuel reprocessing in the US is almost certain to be necessary for the licensing of a reprocessing facility in the US. Various control technologies have been developed, tested, or used over the past 50 years for control of volatile radionuclide emissions from used fuel reprocessing plants. The US DOE has sponsored, since 2009, an Off-gas Sigma Team to perform research and development focused on the most pressing volatile radionuclide control and immobilization problems. In this paper, we focus on the control requirements and methodologies for 85Kr and 129I. Numerous candidate technologies have been studied and developed at laboratory and pilot-plant scales in an effort to meet the need for high iodine control efficiency and to advance alternatives to cryogenic separations for krypton control. Several of these show promising results. Iodine decontamination factors as high as 105, iodine loading capacities, and other adsorption parameters including adsorption rates have been demonstrated under some conditions for both silver zeolite (AgZ) and Ag-functionalized aerogel. Sorbents, including an engineered form of AgZ and selected metal organic framework materials (MOFs), have been successfully demonstrated to capture Kr and Xe without the need for separations at cryogenic temperatures. read more read less

Topics:

Nuclear reprocessing (54%)54% related to the paper, Spent nuclear fuel (54%)54% related to the paper, Isotopes of krypton (52%)52% related to the paper, Radioactive waste (51%)51% related to the paper, Krypton-85 (51%)51% related to the paper
View PDF
155 Citations
open accessOpen access Journal Article DOI: 10.1155/2008/460795
Thermal-Hydraulic System Codes in Nulcear Reactor Safety and Qualification Procedures

Abstract:

In the last four decades, large efforts have been undertaken to provide reliable thermal-hydraulic system codes for the analyses of transients and accidents in nuclear power plants. Whereas the first system codes, developed at the beginning of the 1970s, utilized the homogenous equilibrium model with three balance equations t... In the last four decades, large efforts have been undertaken to provide reliable thermal-hydraulic system codes for the analyses of transients and accidents in nuclear power plants. Whereas the first system codes, developed at the beginning of the 1970s, utilized the homogenous equilibrium model with three balance equations to describe the two-phase flow, nowadays the more advanced system codes are based on the so-called “two-fluid model” with separation of the water and vapor phases, resulting in systems with at least six balance equations. The wide experimental campaign, constituted by the integral and separate effect tests, conducted under the umbrella of the OECD/CSNI was at the basis of the development and validation of the thermal-hydraulic system codes by which they have reached the present high degree of maturity. However, notwithstanding the huge amounts of financial and human resources invested, the results predicted by the code are still affected by errors whose origins can be attributed to several reasons as model deficiencies, approximations in the numerical solution, nodalization effects, and imperfect knowledge of boundary and initial conditions. In this context, the existence of qualified procedures for a consistent application of qualified thermal-hydraulic system code is necessary and implies the drawing up of specific criteria through which the code-user, the nodalization, and finally the transient results are qualified. read more read less
View PDF
122 Citations
open accessOpen access Journal Article DOI: 10.1155/2013/343492
Current Status of Pyroprocessing Development at KAERI

Abstract:

Pyroprocessing technology has been actively developed at Korea Atomic Energy Research Institute (KAERI) to meet the necessity of addressing spent fuel management issue. This technology has advantages over aqueous process such as less proliferation risk, treatment of spent fuel with relatively high heat and radioactivity, and ... Pyroprocessing technology has been actively developed at Korea Atomic Energy Research Institute (KAERI) to meet the necessity of addressing spent fuel management issue. This technology has advantages over aqueous process such as less proliferation risk, treatment of spent fuel with relatively high heat and radioactivity, and compact equipments. This paper describes the pyroprocessing technology development at KAERI from head-end process to waste treatment. The unit process with various scales has been tested to produce the design data associated with scale-up. Pyroprocess integrated inactive demonstration facility (PRIDE) was constructed at KAERI and it began test operation in 2012. The purpose of PRIDE is to test the process regarding unit process performance, remote operation of equipments, integration of unit processes, scale-up of process, process monitoring, argon environment system operation, and safeguards-related activities. The test of PRIDE will be promising for further pyroprocessing technology development. read more read less

Topics:

Pyroprocessing (58%)58% related to the paper
View PDF
102 Citations
open accessOpen access Journal Article DOI: 10.1155/2016/6547318
MCNP-X Monte Carlo Code Application for Mass Attenuation Coefficients of Concrete at Different Energies by Modeling 3 × 3 Inch NaI(Tl) Detector and Comparison with XCOM and Monte Carlo Data

Abstract:

Gamma-ray measurements in various research fields require efficient detectors. One of these research fields is mass attenuation coefficients of different materials. Apart from experimental studies, the Monte Carlo (MC) method has become one of the most popular tools in detector studies. An NaI(Tl) detector has been modeled, a... Gamma-ray measurements in various research fields require efficient detectors. One of these research fields is mass attenuation coefficients of different materials. Apart from experimental studies, the Monte Carlo (MC) method has become one of the most popular tools in detector studies. An NaI(Tl) detector has been modeled, and, for a validation study of the modeled NaI(Tl) detector, the absolute efficiency of 3 × 3 inch cylindrical NaI(Tl) detector has been calculated by using the general purpose Monte Carlo code MCNP-X (version 2.4.0) and compared with previous studies in literature in the range of 661–2620 keV. In the present work, the applicability of MCNP-X Monte Carlo code for mass attenuation of concrete sample material as building material at photon energies 59.5 keV, 80 keV, 356 keV, 661.6 keV, 1173.2 keV, and 1332.5 keV has been tested by using validated NaI(Tl) detector. The mass attenuation coefficients of concrete sample have been calculated. The calculated results agreed well with experimental and some other theoretical results. The results specify that this process can be followed to determine the data on the attenuation of gamma-rays with other required energies in other materials or in new complex materials. It can be concluded that data from Monte Carlo is a strong tool not only for efficiency studies but also for mass attenuation coefficients calculations. read more read less

Topics:

Monte Carlo method (60%)60% related to the paper, Detector (52%)52% related to the paper, Attenuation (51%)51% related to the paper
View PDF
92 Citations
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Frequently asked questions

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Of course! We support all the top citation styles, such as APA style, MLA style, Vancouver style, Harvard style, and Chicago style. For example, when you write your paper and hit autoformat, our system will automatically update your article as per the Science and Technology of Nuclear Installations citation style.

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12. Is Science and Technology of Nuclear Installations's impact factor high enough that I should try publishing my article there?

To be honest, the answer is no. The impact factor is one of the many elements that determine the quality of a journal. Few of these factors include review board, rejection rates, frequency of inclusion in indexes, and Eigenfactor. You need to assess all these factors before you make your final call.

13. What is Sherpa RoMEO Archiving Policy for Science and Technology of Nuclear Installations?

SHERPA/RoMEO Database

We extracted this data from Sherpa Romeo to help researchers understand the access level of this journal in accordance with the Sherpa Romeo Archiving Policy for Science and Technology of Nuclear Installations. The table below indicates the level of access a journal has as per Sherpa Romeo's archiving policy.

RoMEO Colour Archiving policy
Green Can archive pre-print and post-print or publisher's version/PDF
Blue Can archive post-print (ie final draft post-refereeing) or publisher's version/PDF
Yellow Can archive pre-print (ie pre-refereeing)
White Archiving not formally supported
FYI:
  1. Pre-prints as being the version of the paper before peer review and
  2. Post-prints as being the version of the paper after peer-review, with revisions having been made.

14. What are the most common citation types In Science and Technology of Nuclear Installations?

The 5 most common citation types in order of usage for Science and Technology of Nuclear Installations are:.

S. No. Citation Style Type
1. Author Year
2. Numbered
3. Numbered (Superscripted)
4. Author Year (Cited Pages)
5. Footnote

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Yes, SciSpace provides this functionality. After signing up, you would need to import your existing references from Word or Bib file to SciSpace. Then SciSpace would allow you to download your references in Science and Technology of Nuclear Installations Endnote style according to Elsevier guidelines.

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