Evaluation of B&W UO2/ThO2 VIII experimental core: criticality and thermal disadvantage factor analysis
Conference
·
OSTI ID:1349198
In the framework of the OECD/NEA International Reactor Physics Experiment (IRPHE) Project, an evaluation of core VIII of the Babcock & Wilcox (B&W) Spectral Shift Control Reactor (SSCR) critical experiment program was performed. The SSCR concept, moderated and cooled by a variable mixture of heavy and light water, envisaged changing of the thermal neutron spectrum during the operation to encourage breeding and to sustain the core criticality. Core VIII contained 2188 fuel rods with 93% enriched UO2-ThO2 fuel in a moderator mixture of heavy and light water. The criticality experiment and measurements of the thermal disadvantage factor were evaluated.
- Research Organization:
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy (NE)
- DOE Contract Number:
- AC07-05ID14517
- OSTI ID:
- 1349198
- Report Number(s):
- INL/CON-16-37848
- Resource Relation:
- Conference: 2016 ANS Annual Meeting, New Orleans, LA, 6/12/2016 - 6/16/2016
- Country of Publication:
- United States
- Language:
- English
Similar Records
Evaluation of B and W UO{sub 2}/ThO{sub 2} VIII Experimental Core: Criticality and Thermal Disadvantage Factor Analysis
The Behavior of ThO2 Based Fuel Rods During Normal Operation and Transient Events in LWRs
Preliminary FRAPCON3-3Th Steady State Fuel Analysis of ThO2 and UO2 Fuel Mixtures
Journal Article
·
Wed Jun 15 00:00:00 EDT 2016
· Transactions of the American Nuclear Society
·
OSTI ID:1349198
The Behavior of ThO2 Based Fuel Rods During Normal Operation and Transient Events in LWRs
Journal Article
·
Thu Jul 01 00:00:00 EDT 2004
· Nuclear Technology
·
OSTI ID:1349198
+4 more
Preliminary FRAPCON3-3Th Steady State Fuel Analysis of ThO2 and UO2 Fuel Mixtures
Journal Article
·
Sat Dec 01 00:00:00 EST 2001
· Nuclear Technology
·
OSTI ID:1349198
+1 more