Feasibility studies for simultaneous irradiation of NBSR and MITR fuel elements in the BR2 reactor
Creators
- 1. SCK-CEN Belgian Nucler Research Centre, BR2 Reactor, Boeretang 200, 2400 Mol (Belgium)
Description
The BR2 reactor is involved in preliminary neutronics feasibility studies for irradiation of four Design Demonstration Element (Dde) tests foreseen in the US High Performance Research Reactor (US HPRR) conversion program: MURR, MITR, NBSR and HFIR. The purpose of the irradiation will be to qualify the new Leu fuel material for each Dde Lead Test Assembly in the BR2 reactor at conditions that are similar for the reactor of origin. The present paper focuses on the preliminary feasibility scenarios for simultaneous irradiation of two Dde s: the MITR and the NBSR Lead Test Assemblies in the BR2 reactor. The MITR and the NBSR fuel elements will be loaded in the 200 mm diameter channels (H5 and H3). In order to mimic the irradiation conditions for each Dde in the BR2 reactor as in the original reactors, a number of optimization scenarios are considered. The flux and burn-up calculations are performed using the fully automatic option of the MCNP6/CINDER90 code. (Author)
Availability note (English)
Available from the Instituto Nacional de Investigaciones Nucleares, Centro de Informacion y Documentacion, 52750 Ocoyoacac, Estado de Mexico (MX), e-mail: mclaudia.gonzalez@inin.gob.mxAdditional details
Publishing Information
- Publisher
- Sociedad Nuclear Mexicana
- Imprint Place
- Ciudad de Mexico (Mexico)
- Imprint Pagination
- 13 p.
Conference
- Title
- reactor physics paving the way towards more efficient systems
- Acronym
- PHYSOR 2018
- Dates
- 22-26 Apr 2018
- Place
- Cancun, Q. R. (Mexico)
INIS
- Country of Publication
- Mexico
- Country of Input or Organization
- Mexico
- INIS RN
- 50006181
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BR-2 REACTOR; BURNUP; COMPUTER-AIDED DESIGN; CONVERSION; FEASIBILITY STUDIES; FUEL ELEMENTS; IRRADIATION; LEAD; M CODES; NUCLEAR FUELS; OPTIMIZATION; PERFORMANCE; RESEARCH REACTORS
- Descriptors DEC
- COMPUTER CODES; DESIGN; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; IRRADIATION REACTORS; MATERIALS; MATERIALS TESTING REACTORS; METALS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; TANK TYPE REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS