25
Views
5
CrossRef citations to date
0
Altmetric
Technical Paper

Using SCALE6/MAVRIC to Determine the Dose Rate Distribution in the IRIS Power Plant Control Room and Preliminary Estimate Throughout the Reactor Building

&
Pages 187-197 | Published online: 10 Apr 2017

References

  • “SCALE: A Modular Code System for Performing Standardized ComputerAnalyses for Licensing Evaluation,” ORNL/TM-2005/39, Version 6, Vols. I, II, and III (Jan. 2009); see also C00750, available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory.
  • D. E. PEPLOW, “MAVRIC: MONACO with Automated Variance Reduction using Importance Calculations,” ORNL/TM-2005/39, Version 6, Vol. I, Sec. S6, Oak Ridge National Laboratory (Jan. 2009).
  • J. C. WAGNER, E. D. BLAKEMAN, and D. E. PEPLOW, “Forward-Weighted CADIS Method for Global Variance Reduction,” Trans. Am. Nucl. Soc., 97, 630 (2007).
  • D. E. PEPLOW, T. M. EVANS, and J. C. WAGNER, “Simultaneous Optimization of Tallies in Difficult Shielding Problems,” Nucl. Technol., 168, 785 (2009).
  • M. B. EMMETT, “MORSE-CGA: A Monte Carlo Radiation Transport Code with Array Geometry Capability,” ORNL-6174, Oak Ridge National Laboratory (Apr. 1985).
  • M. D. CARELLI, L. E. CONWAY, L. ORIANI, B. PETROVIC, C. V. LOMBARDI, M. E. RICOTTI, A. C. O. BARROSO, J. M. COLLADO, L. CINOTTI, N. E. TODREAS, D. GRGIC, M. M. MORAES, R. D. BOROUGHS, H. NINOKATA, D. T. INGERSOLL, and F. ORIOLO, “The Design and Safety Features of the IRIS Reactor,” Nucl. Eng. Des., 230, 151 (2004).
  • M. CARELLI and B. PETROVIC, “Here’s Looking at IRIS,” Nucl. Eng. Int., 51, 620, 12 (Mar. 2006).
  • B. PETROVIC et al., “Design Features of the IRIS Reactor to Reduce Collective Dose During Operation and Maintenance, and to Simplify D&D,” Proc. 8th Int. Conf. Nuclear Option in Countries with Small and Medium Electricity Grids, Dubrovnik, Croatia, May 16–20, 2010, Croatian Nuclear Society (2010).
  • K. BURN, “IRIS: Monte Carlo Results for Selected Ex-Core Radiation Responses,” Internal IRIS Project Report, ENEA (2010).
  • K. W. BURN, “A New Weight-Dependent Direct Statistical Approach Model,” Nucl. Sci. Eng., 125, 128 (1997).
  • M. SAROTTO, “IRIS Preliminary Shielding Analysis of the Vessel by Deterministic Methods,” Internal IRIS Project Report, ENEA (May 2008).
  • M. CIOTTI, M. SAROTTO, and R. ORSI, “Deterministic Shielding Calculations for the IRIS Reactor,” Internal IRIS Project Report, ENEA (2009).
  • W. A. RHODES and D. B. SIMPSON, “The TORT Three Dimensional Discrete Ordinates Neutron/Photon Transport Code,” ORNL/TM-13221, Oak Ridge National Laboratory; see also CCC-650/DOORS3.2, available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory (1997).
  • B. PETROVIC, “Preliminary Evaluation of the SCALE MAVRIC Code and FW-CADIS Method for Efficient Scoping of the Radiation Field Throughout the IRIS Containment,” Nucl. Technol., 168, 438 (2009).
  • B. PETROVIC and J. McKILLOP, “Design of the IRIS Reactor to Simplify Dismantling of Concrete Structures During Decommissioning,” Proc. European Nuclear Conf. (ENC-2010), Barcelona, Spain, May 30–June 3, 2010, European Nuclear Society (2010).

Reprints and Corporate Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

To request a reprint or corporate permissions for this article, please click on the relevant link below:

Academic Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

Obtain permissions instantly via Rightslink by clicking on the button below:

If you are unable to obtain permissions via Rightslink, please complete and submit this Permissions form. For more information, please visit our Permissions help page.