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Title: Watts Bar I Ex-Core Analyses using VERA

Abstract

The integration and direct coupling of the Oak Ridge National Laboratory (ORNL) Shift Monte Carlo code within the Consortium for Advanced Simulation of Light Water Reactors (CASL) Virtual Environment for Reactor Applications (VERA) offers unique capabilities that combine high-fidelity in-core and ex-core radiation transport. In this recent development activity, the deterministic neutronics code MPACT performs the incore radiation transport with temperature feedback using COBRA-TF (CTF), and provides the fission source to Shift for a follow-on fixed source radiation transport calculation to determine ex-core quantities of interest. The coupling of MPACT to Shift allows the neutron source for the ex-core transport to be calculated from the time-dependent, fully coupled MPACT solution. This paper presents the first use of VERA to perform coupon irradiation for validation of its ex-core capabilities.

Authors:
ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1];  [1]
  1. ORNL
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1470862
DOE Contract Number:  
AC05-00OR22725
Resource Type:
Conference
Resource Relation:
Conference: ANS RSPD 2018 - 20th Topical Meeting of the Radiation Protection & Shielding Division of ANS - Santa Fe, New Mexico, United States of America - 8/26/2018 4:00:00 AM-8/31/2018 4:00:00 AM
Country of Publication:
United States
Language:
English

Citation Formats

Davidson, Eva E., Pandya, Tara M., Godfrey, Andrew T., and Asgari, Mehdi. Watts Bar I Ex-Core Analyses using VERA. United States: N. p., 2018. Web.
Davidson, Eva E., Pandya, Tara M., Godfrey, Andrew T., & Asgari, Mehdi. Watts Bar I Ex-Core Analyses using VERA. United States.
Davidson, Eva E., Pandya, Tara M., Godfrey, Andrew T., and Asgari, Mehdi. Wed . "Watts Bar I Ex-Core Analyses using VERA". United States. https://www.osti.gov/servlets/purl/1470862.
@article{osti_1470862,
title = {Watts Bar I Ex-Core Analyses using VERA},
author = {Davidson, Eva E. and Pandya, Tara M. and Godfrey, Andrew T. and Asgari, Mehdi},
abstractNote = {The integration and direct coupling of the Oak Ridge National Laboratory (ORNL) Shift Monte Carlo code within the Consortium for Advanced Simulation of Light Water Reactors (CASL) Virtual Environment for Reactor Applications (VERA) offers unique capabilities that combine high-fidelity in-core and ex-core radiation transport. In this recent development activity, the deterministic neutronics code MPACT performs the incore radiation transport with temperature feedback using COBRA-TF (CTF), and provides the fission source to Shift for a follow-on fixed source radiation transport calculation to determine ex-core quantities of interest. The coupling of MPACT to Shift allows the neutron source for the ex-core transport to be calculated from the time-dependent, fully coupled MPACT solution. This paper presents the first use of VERA to perform coupon irradiation for validation of its ex-core capabilities.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2018},
month = {8}
}

Conference:
Other availability
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