ADS-IDAC

Appearance

References ​

Inline References ​

The following sources are cited throughout the ADS-IDAC Input Manual and are particularly central to understanding the theoretical basis of the tool:

IDAC Model (Parts 1–5) — Chang and Mosleh (2007a–c) published the five-part IDAC series in Reliability Engineering & System Safety, covering the model overview (Part 1), performance influencing factors (Part 2), operator response model (Part 3), causal problem-solving model (Part 4), and dynamic probabilistic simulation (Part 5).

ADS-IDAC Implementation — Coyne and Mosleh (2008a, 2009) describe the application of a dynamic PRA approach for predicting operator errors and modeling operator knowledge and procedural adherence in ADS-IDAC.

Original ADS — Hsueh and Mosleh (1993, 1996) developed the Accident Dynamic Simulator (ADS), the thermal-hydraulic simulation framework on which ADS-IDAC is built, and demonstrated its application to dynamic probabilistic risk assessment.

IDA Cognitive Model — Smidts, Shen, and Mosleh (1997) introduced the IDA cognitive model for nuclear power plant operator response, a direct predecessor to the IDAC model incorporated in ADS-IDAC.

RELAP5/MOD3 — The U.S. Nuclear Regulatory Commission NUREG/CR-5535 (INEL-95/0174, 1995) documents the RELAP5/MOD3 thermal-hydraulic code used as the physics engine within ADS-IDAC simulations.

Bibliography ​

Dynamic PRA Methods ​

  • [11] N. Siu, "Technical Note — Dynamic Accident Sequence Analysis in PRA: A Comment on 'Human Reliability Analysis — Where Shouldst Thou Turn?'" Reliability Engineering and System Safety, vol. 29, pp. 359–364, 1990.
  • [45] A. Hakobyan, T. Aldemir, R. Denning, S. Dunagan, D. Kunsman, B. Rutt, and U. Catalyurek, "Dynamic generation of accident progression event trees," Nuclear Engineering and Design, vol. 238, pp. 3457–3467, 2008.
  • [46] E. Hofer, M. Kloos, B. Krzykacz-Hausmann, J. Peschke, and M. Sonnenkalb, "Dynamic Event Trees for Probabilistic Safety Analysis," in Eurosafe — 2002. Berlin: GRS, 2002.
  • [47] M. Kloos and J. Peschke, "Consideration of human actions in combination with the probabilistic dynamics method MCDET," presented at ESREL 2007, Stavanger, Norway, 2007.
  • [51] K. S. Hsueh and A. Mosleh, "The development and application of the accident dynamic simulator for dynamic probabilistic risk assessment of nuclear power plants," Reliability Engineering & System Safety, vol. 52, pp. 297–314, 1996.
  • [52] D. Zhu, Y. H. Chang, and A. Mosleh, "The Use of Distributed Computing for Dynamic PRA: The ADS Approach," presented at PSAM-9, Hong Kong, 2008.
  • [72] N. Siu, "Risk assessment for dynamic systems: An overview," Reliability Engineering and System Safety, vol. 43, pp. 43–73, 1994.

Human Reliability Analysis ​

  • [2] D. I. Gertman, B. P. Hallbert, M. W. Parrish, M. B. Sattision, D. Brownson, and J. P. Tortorelli, "Review of Findings for Human Error Contribution to Risk in Operating Events," U.S. NRC NUREG/CR-6753, 2001.
  • [7] NUREG, "PRA Procedures Guide," U.S. NRC NUREG/CR-2300, January 1983.
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  • [91] E. Lois, V. N. Dang, J. Forester, et al., "International HRA Empirical Study — Pilot Phase Report," OECD Halden Reactor Project HWR-844, 2008.
  • [92] E. Lois, V. N. Dang, G. Parry, et al., "The International HRA Empirical Study — Results from Comparing HRA Methods Predictions to HAMMLAB Simulator Data on SGTR Scenarios," OECD HRP HWR-915 (Draft), 2009.
  • [94] B. Hallbert and A. Kolaczkowski, "The Employment of Empirical Data and Bayesian Methods in Human Reliability Analysis: A Feasibility Study," U.S. NRC NUREG/CR-6949, 2007.
  • [95] B. Hallbert, R. Boring, D. Gertman, et al., "Human Event Repository and Analysis (HERA) System, Overview," U.S. NRC NUREG/CR-6903, 2006.
  • [100] V. N. Dang and A. Bye, "Evaluating HRA Methods in Light of Simulator Findings: Study Overview and Issues for an Empirical Test," presented at Enlarged Halden Programme Group Meeting, Storefjell, Norway, 2007.
  • [101] K. Coyne and A. Mosleh, "ADS-IDAC Analysis of Loss of Feedwater Accident Scenarios — OECD Halden Reactor Project International HRA Empirical Study," University of Maryland, Center for Risk and Reliability, August 30, 2008.

Cognitive Models ​

  • [13] G. Klein, "The Recognition-Primed Decision (RPD) Model: Looking Back, Looking Forward," in Naturalistic Decision Making. Mahwah, NJ: Lawrence Erlbaum, 1997, pp. 285–292.
  • [15] J. Rasmussen, "Models of Mental Strategies in Process Plant Diagnosis," presented at NATO Symposium on Human Detection and Diagnosis of System Failures, Roskilde, Denmark, 1980.
  • [19] R. E. Mayer, Thinking, Problem Solving, Cognition, 2nd ed. New York: W. H. Freeman and Company, 1992.
  • [20] Y. H. Chang and A. Mosleh, "Cognitive modeling and dynamic probabilistic simulation of operating crew response to complex system accidents — Part 2: IDAC performance influencing factors model," Reliability Engineering & System Safety, vol. 92, pp. 1014–1040, 2007.
  • [22] Y. H. Chang and A. Mosleh, "Cognitive modeling and dynamic probabilistic simulation of operating crew response to complex system accidents — Part 1: Overview of the IDAC Model," Reliability Engineering & System Safety, vol. 92, pp. 997–1013, 2007.
  • [23] C. Smidts, S. H. Shen, and A. Mosleh, "The IDA cognitive model for the analysis of nuclear power plant operator response under accident conditions. Part I: Problem solving and decision making model," Reliability Engineering & System Safety, vol. 55, pp. 51–71, 1997.
  • [24] A. Mosleh and Y. H. Chang, "Model-based human reliability analysis: prospects and requirements," Reliability Engineering and System Safety, vol. 83, pp. 241–253, 2004.
  • [48] A. Mosleh, C. Smidts, and S. H. Shen, "Modeling cognition dynamics and its application to human reliability analysis," Transactions of the American Nuclear Society, vol. 75, pp. 84–85, 1996.
  • [49] S. H. Shen, C. Smidts, and A. Mosleh, "Application of a Model Based Human Error Taxonomy to the Analysis of Reactor Operating Events," presented at Topical Meeting on Computer-Based Human Support Systems, Philadelphia, PA, 1995.
  • [50] S. H. Shen, C. Smidts, and A. Mosleh, "A methodology for collection and analysis of human error data based on a cognitive model: IDA," Nuclear Engineering and Design, vol. 172, pp. 157–186, 1997.
  • [96] Y. H. Chang and A. Mosleh, "Cognitive modeling and dynamic probabilistic simulation of operating crew response to complex system accidents Part 3: IDAC operator response model," Reliability Engineering and System Safety, vol. 92, pp. 1041–1060, 2007.
  • [97] K. Furuta, Y. Soraji, T. Kanno, et al., "Cognitive model of team cooperation in en-route air traffic control," presented at ESREL-2009, Prague, Czech Republic, 2009.

Full Bibliography ​

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  23. C. Smidts, S. H. Shen, and A. Mosleh, "The IDA cognitive model for the analysis of nuclear power plant operator response under accident conditions. Part I: Problem solving and decision making model," Reliability Engineering & System Safety, vol. 55, pp. 51–71, 1997.
  24. A. Mosleh and Y. H. Chang, "Model-based human reliability analysis: prospects and requirements," Reliability Engineering and System Safety, vol. 83, pp. 241–253, 2004.
  25. E. M. Roth, R. J. Mumaw, and P. M. Lewis, "An Empirical Investigation of Operator Performance in Cognitively Demanding Simulated Emergencies," U.S. NRC NUREG-CR-6208, 1994.
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RELAP5 Documentation ​

  • [72] "RELAP5/MOD3 CODE MANUAL," U.S. Nuclear Regulatory Commission NUREG/CR-5535 (INEL-95/0174), 1995.

NRC Reports ​

  • [2] NUREG/CR-6753 — Human error contribution to risk in operating events.
  • [3] NUREG/CR-1250 — Three Mile Island report to commissioners.
  • [7] NUREG/CR-2300 — PRA Procedures Guide.
  • [9] NUREG/CR-1278 — Handbook of Human Reliability Analysis (THERP).
  • [10] NUREG-1624 — ATHEANA technical basis.
  • [25] NUREG-CR-6208 — Operator performance in cognitively demanding emergencies.
  • [35] NUREG-1792 — Good practices for implementing HRA.
  • [85] NUREG-1880 — ATHEANA User's Guide.
  • [88] NUREG/CR-6883 — SPAR-H HRA Method.
  • [89] Generic Letter 89-06 — Safety Parameter Display System.
  • [94] NUREG/CR-6949 — Bayesian methods in HRA feasibility study.
  • [95] NUREG/CR-6903 — HERA System Overview.

ADS-IDAC Engine Documentation

NC State PRAG · Input Manual: Final Revision, September 20, 2009