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

Simulation of the Fast Reactor Fuel Assembly Duct-Bowing Reactivity Effect Using Monte Carlo Neutron Transport and Finite Element Analysis

Journal Article · · Nuclear Technology
 [1];  [2]
  1. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
  2. Idaho State Univ., Pocatello, ID (United States)

This paper discusses a new method of simulating the fuel assembly duct-bowing reactivity coefficient for EBR-II run 138B. Quantification of the fuel assembly duct-bowing reactivity effect in liquid metal–cooled fast reactors has been a persistent problem since they were first designed and operated. Simulation of the duct-bowing reactivity effect is difficult because the level of detail required to simulate the effect has exceeded most modeling capabilities. The new method outlined in this paper utilizes the finite element analysis code ANSYS to analyze the thermal and structural components. Here, the displacement of the fuel assembly duct due to thermal expansion and mechanical interaction was calculated by ANSYS using recorded EBR-II run 138B temperature and power boundary value data. The displacement values were incorporated into to a Monte Carlo model of EBR-II run 138B and keff was calculated. Multiple Monte Carlo calculations were performed with duct displacement values corresponding to different reactor temperatures. Using the calculated keff values associated with the different duct displacement results allowed calculation of the duct-bowing reactivity coefficient. The duct-bowing reactivity coefficient was calculated to be –14.5 × 10–4 $/°C/ ± 4.4%.

Research Organization:
Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA). Office of Defense Programs (DP) (NA-10)
Grant/Contract Number:
89233218CNA000001
OSTI ID:
1735900
Report Number(s):
LA-UR--20-22482
Journal Information:
Nuclear Technology, Journal Name: Nuclear Technology Journal Issue: 5 Vol. 207; ISSN 0029-5450
Publisher:
Taylor & Francis - formerly American Nuclear Society (ANS)Copyright Statement
Country of Publication:
United States
Language:
English

References (8)

Loss-of-primary-flow-without-scram tests: Pretest predictions and preliminary results journal April 1987
GODIVA-IV reactivity temperature coefficient calculation using finite element and Monte Carlo techniques journal May 2018
Design of an experimental breeder reactor run 138B reactor physics benchmark evaluation management application journal October 2019
Critical Experiment Tests of Bowing and Expansion Reactivity Calculations for Liquid-Metal-Cooled Fast Reactors journal October 1989
Development and Validation of ARKAS_cellule: An Advanced Core-Bowing Analysis Code for Fast Reactors journal May 2004
Observations of Dilation and Bowing in Experimental Breeder Reactor II Ducts and Cladding journal November 1979
Bow in Experimental Breeder Reactor II Reflector Subassemblies journal February 1981
Analysis of Mechanical Bowing Phenomena of Fuel Assemblies in Passively Safe Advanced Liquid-Metal Reactors journal November 1988

Similar Records

Bowing-reactivity trends in EBR-II assuming zero-swelling ducts
Conference · Mon Feb 28 23:00:00 EST 1994 · OSTI ID:10129580

Nonlinear PRD components of EBR-II compared with bowing analyses
Conference · Wed Dec 31 23:00:00 EST 1986 · Trans. Am. Nucl. Soc.; (United States) · OSTI ID:6869953

Observations of dilation and bowing in Experimental Breeder Reactor II ducts and cladding
Journal Article · Wed Oct 31 23:00:00 EST 1979 · Nucl. Technol.; (United States) · OSTI ID:5899533