Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Uncertainty Quantification of the Decay Gamma Source in Mesh-Based Shutdown Dose Rate Calculations

Journal Article · · Fusion Science and Technology
 [1];  [2];  [3]
  1. University of Wisconsin–Madison, Madison, Wisconsin; Karlsruhe Institute of Technology, Karlsruhe, Germany; OSTI
  2. University of Wisconsin–Madison, Madison, Wisconsin; United Kingdom Atomic Energy Authority, Culham, United Kingdom
  3. University of Wisconsin–Madison, Madison, Wisconsin
Not provided.
Research Organization:
Univ. of Wisconsin, Madison, WI (United States)
Sponsoring Organization:
USDOE Office of Science (SC)
DOE Contract Number:
FG02-99ER54513; SC0017122
OSTI ID:
2419540
Journal Information:
Fusion Science and Technology, Journal Name: Fusion Science and Technology Journal Issue: 1 Vol. 79; ISSN 1536-1055
Publisher:
Taylor & Francis
Country of Publication:
United States
Language:
English

References (11)

On-the-fly Estimation Strategy for Uncertainty Propagation in Two-Step Monte Carlo Calculation for Residual Radiation Analysis journal June 2016
Validation of the Alara Activation Code journal November 1998
The examination of the FNSF maintenance approach journal October 2018
Rigorous mcnp based shutdown dose rate calculations: computational scheme, verification calculations and application to ITER journal December 2002
The Fusion Nuclear Science Facility, the Critical Step in the Pathway to Fusion Energy journal September 2015
What must DEMO do? conference January 1995
Neutronics aspects of the FESS-FNSF journal October 2018
Verification and validation of the R2Smesh approach for the calculation of high resolution shutdown dose rate distributions journal August 2012
FISPACT-II: An Advanced Simulation System for Activation, Transmutation and Material Modelling journal January 2017
Calculation of Shutdown Dose Rate in Fusion Nuclear Science Facility During a Proposed Maintenance Scheme journal August 2019
Transmutation Approximations for the Application of Hybrid Monte Carlo/Deterministic Neutron Transport to Shutdown Dose Rate Analysis journal May 2017

Similar Records

The Multi-Step CADIS method for shutdown dose rate calculations and uncertainty propagation
Journal Article · 2015 · Nuclear Technology · OSTI ID:1245347

Development of the Advanced D1S for Shutdown Dose Rate Calculations in Fusion Reactors
Journal Article · 2017 · Transactions of the American Nuclear Society · OSTI ID:23047395

The Multi-Step CADIS Method for Shutdown Dose Rate Calculations and Uncertainty Propagation - Paper 137
Conference · 2014 · OSTI ID:23082955