Article
Licensed
Unlicensed Requires Authentication

Social impact theory based modeling for security analysis in the nuclear fuel cycle

Published/Copyright: March 21, 2015
Become an author with De Gruyter Brill
Submit Manuscript Author Information
Kerntechnik
From the journal Kerntechnik Volume 80 Issue 1

Abstract

The nuclear fuel cycle is investigated for the perspective of the nuclear non-proliferation. The random number generation of the Monte-Carlo method is utilized for the analysis. Five cases are quantified by the random number generations. These values are summed by the described equations. The higher values are shown in 52nd and 73rd months. This way could be a useful obligation in the license of the plant construction. The security of the nuclear fuel cycle incorporated with nuclear power plants (NPPs) is investigated using social impact theory. The dynamic quantification of the theory shows the non-secured time for act of terrorism which is considered for the non-secured condition against the risk of theft in nuclear material. For a realistic consideration, the meta-theoretical framework for modeling is performed for situations where beliefs, attributes or behaviors of an individual are influenced by those of others.

Kurzfassung

Der nukleare Brennstoffkreislauf wurde untersucht im Hinblick auf die Nichtverbreitung von Kernwaffen. Für diese Analyse wurden 5 Fälle mit Hilfe der Monte-Carlo-Methode quantifiziert und mit den beschriebenen Gleichungen zusammengefasst. Die höheren Werte zeigen sich im 52. und 73. Monat. Diese Vorgehensweise könnte im Rahmen von Genehmigungsanforderungen für Kernkraftwerke von Nutzen sein. Die Sicherheit des nuklearen Brennstoffkreislaufs wurde untersucht auf der Basis von Überlegungen zum sozialen Einfluss. Die dynamische Quantifizierung dieser Überlegungen zeigt die nicht gesicherte Zeitspanne für terroristische Gewalttaten die im Zusammenhang mit dem Risiko des Diebstahls von spaltbaren Kernmaterialien betrachtet werden muss. Für eine realistische Analyse wird das meta-theoretische Bezugssystem für die Modellierung von Situationen herangezogen, in denen Überzeugungen, Eigenschaften oder Handlungsweise eines Individuums beeinflusst werden von denen anderer Individuen.

References

1 IAEA: Guidelines and Format for Preparation and Submission of Declarations Pursuant to Articles 2 and 3 of the Model Protocol Additional to Safeguards Agreements. IAEA Services Series No. 11 (2004)Search in Google Scholar

2 IAEA: The evolution of IAEA safeguards. International nuclear verification series No. 2, Vienna (1998)Search in Google Scholar

3 Michael, A. G.; ScottT.: Blackwell Handbook of Social Psychology: Group Processes, John Wiley & Sons (2008)Search in Google Scholar

4 Bhondekar, A. P.; Kaur, P.; Kumar, R.; Vig, R.; Kapur, P.: A novel approach using Dynamic Social Impact Theory for optimization of impedance-Tongue (iTongue). Chemo. and Intel. Lab. Syst.109 (2011) 65–7610.1016/j.chemolab.2011.08.002Search in Google Scholar

5 Nettle, D.: Using Social Impact Theory to simulate language change. Lingua.108 (1999) 95–11710.1016/S0024-3841(98)00046-1Search in Google Scholar

6 Ni, S.; WengW.; ZhangH.: Modeling the effects of social impact on epidemic spreading in complex networks. Phys A: Stat. Mech. and its Applic.390 (2011) 4528–453410.1016/j.physa.2011.07.042Search in Google Scholar

7 IAEA: ISSAS Guidelines Reference Report for the IAEA SSAC Advisory Service. IAEA Services Series No. 13 (2005)Search in Google Scholar

8 USDOE: Safeguards and Security Program Glossary, Office of Security and Safety Performance Assurance. Washington, D.C., USA (2005)Search in Google Scholar

9 IAEA: Nuclear Fuel Cycle Information System. IAEA-TECDOC-1613 (2009)Search in Google Scholar

10 IAEA: Design Measures to Facilitate Implementation of Safeguards at Future Water Cooled Nuclear Power Plants. Technical Reports Series No. 392 (1999)Search in Google Scholar

11 KHNP: A Government Report for Nuclear Power Generation. Korea Hydro & Nuclear Power Co. Ltd (2013)Search in Google Scholar

12 Close, D. A.: IAEA Safeguards for the Fissile Materials Disposition Project. Los Alamos National Laboratory, LA-12929-MA (1995)10.2172/71647Search in Google Scholar

13 Pedersen, E. R.; LabrieJ.W.; LacA.: Assessment of perceived and actual alcohol norms in varying contexts: Exploring Social Impact Theory among college students. Addi. Behav.33 (2008) 552–56410.1016/j.addbeh.2007.11.003Search in Google Scholar PubMed PubMed Central

14 Latane, B.: The psychology of social impact. Ameri. Psycho.36 (1981) 343–35610.1037/0003-066X.36.4.343Search in Google Scholar

15 Nowak, A.; Szamrej, J.; Latane, B.: From Private Attitude to Public Opinion: A Dynamic Theory of Social Impact. Psycho. Rev.97 (1990) 362–37610.1037/0033-295X.97.3.362Search in Google Scholar

16 Vensim: Vensim Manual. Ventana Systems, Inc (2014)Search in Google Scholar

Received: 2014-11-25
Published Online: 2015-03-21
Published in Print: 2015-03-17

© 2015, Carl Hanser Verlag, München

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Technical Contributions/Fachbeiträge
  6. Evaluation of advanced displacement cross-sections for the major EUROFER constituents based on an atomistic modelling approach
  7. Tarapur atomic power station: analysis of station blackout scenario
  8. Estimating steady state and transient characteristics of molten salt natural circulation loop using CFD
  9. Thermal hydraulic analysis of ETRR-2 using RELAP5 code
  10. Transient performance during stopping the research reactor primary loop pump
  11. Neutronic performance calculations with alternative fluids in a hybrid reactor by using the Monte Carlo method
  12. A study on the criticality of modified neutron transport equation by using alternative scattering phase functions
  13. Production cross–section calculations of medical 32P, 117Sn, 153Sm and 186,188Re radionuclides used in bone pain palliation treatment
  14. Study on carbonated hydroxyapatite as a thermoluminescence dosimeter
  15. Social impact theory based modeling for security analysis in the nuclear fuel cycle
  16. Analysis of a homogenous and heterogeneous stylized half core of a CANDU reactor
https://doi.org/10.3139/124.110480

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Technical Contributions/Fachbeiträge
  6. Evaluation of advanced displacement cross-sections for the major EUROFER constituents based on an atomistic modelling approach
  7. Tarapur atomic power station: analysis of station blackout scenario
  8. Estimating steady state and transient characteristics of molten salt natural circulation loop using CFD
  9. Thermal hydraulic analysis of ETRR-2 using RELAP5 code
  10. Transient performance during stopping the research reactor primary loop pump
  11. Neutronic performance calculations with alternative fluids in a hybrid reactor by using the Monte Carlo method
  12. A study on the criticality of modified neutron transport equation by using alternative scattering phase functions
  13. Production cross–section calculations of medical 32P, 117Sn, 153Sm and 186,188Re radionuclides used in bone pain palliation treatment
  14. Study on carbonated hydroxyapatite as a thermoluminescence dosimeter
  15. Social impact theory based modeling for security analysis in the nuclear fuel cycle
  16. Analysis of a homogenous and heterogeneous stylized half core of a CANDU reactor
Downloaded on 12.4.2026 from https://www.degruyterbrill.com/document/doi/10.3139/124.110480/html
Scroll to top button