Supplemental Thermal-Hydraulic Transient Analyses of BR2 in Support of Conversion to LEU Fuel [electronic resource]
Belgian Reactor 2 (BR2) is a research and test reactor located in Mol, Belgium and is primarily used for radioisotope production and materials testing. The Materials Management and Minimization (M3) Reactor Conversion Program of the National Nuclear Security Administration (NNSA) is supporting the c...
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Online Access (via OSTI) |
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| Format: | Government Document Electronic eBook |
| Language: | English |
| Published: |
Washington, D.C. : Oak Ridge, Tenn. :
United States. National Nuclear Security Administration ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,
2016.
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| Subjects: |
MARC
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| 245 | 0 | 0 | |a Supplemental Thermal-Hydraulic Transient Analyses of BR2 in Support of Conversion to LEU Fuel |h [electronic resource] |
| 260 | |a Washington, D.C. : |b United States. National Nuclear Security Administration ; |a Oak Ridge, Tenn. : |b distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, |c 2016. | ||
| 300 | |a 30 p. : |b digital, PDF file. | ||
| 336 | |a text |b txt |2 rdacontent. | ||
| 337 | |a computer |b c |2 rdamedia. | ||
| 338 | |a online resource |b cr |2 rdacarrier. | ||
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| 500 | |a 01/01/2016. | ||
| 500 | |a "anl/rtr/tm--16/3" | ||
| 500 | |a "130471" | ||
| 500 | |a J. Licht; B. Dionne; E. Sikik; G. Van den Branden; E. Koonen. | ||
| 520 | 3 | |a Belgian Reactor 2 (BR2) is a research and test reactor located in Mol, Belgium and is primarily used for radioisotope production and materials testing. The Materials Management and Minimization (M3) Reactor Conversion Program of the National Nuclear Security Administration (NNSA) is supporting the conversion of the BR2 reactor from Highly Enriched Uranium (HEU) fuel to Low Enriched Uranium (LEU) fuel. The RELAP5/Mod 3.3 code has been used to perform transient thermal-hydraulic safety analyses of the BR2 reactor to support reactor conversion. A RELAP5 model of BR2 has been validated against select transient BR2 reactor experiments performed in 1963 by showing agreement with measured cladding temperatures. Following the validation, the RELAP5 model was then updated to represent the current use of the reactor; taking into account core configuration, neutronic parameters, trip settings, component changes, etc. Simulations of the 1963 experiments were repeated with this updated model to re-evaluate the boiling risks associated with the currently allowed maximum heat flux limit of 470 W/cm<sup>2</sup> and temporary heat flux limit of 600 W/cm<sup>2</sup>. This document provides analysis of additional transient simulations that are required as part of a modern BR2 safety analysis report (SAR). The additional simulations included in this report are effect of pool temperature, reduced steady-state flow rate, in-pool loss of coolant accidents, and loss of external cooling. The simulations described in this document have been performed for both an HEU- and LEU-fueled core. | |
| 536 | |b AC02-06CH11357. | ||
| 650 | 7 | |a Slightly Enriched Uranium. |2 local. | |
| 650 | 7 | |a Highly Enriched Uranium. |2 local. | |
| 650 | 7 | |a Br-2 Reactor. |2 local. | |
| 650 | 7 | |a Thermal Hydraulics. |2 local. | |
| 650 | 7 | |a Conversion. |2 local. | |
| 650 | 7 | |a Nuclear Fuels. |2 local. | |
| 650 | 7 | |a Pressure Range Mega Pa. |2 local. | |
| 650 | 7 | |a Reactor Cores. |2 local. | |
| 650 | 7 | |a Secondary Coolant Circuits. |2 local. | |
| 650 | 7 | |a Losses. |2 local. | |
| 650 | 7 | |a Coolants. |2 local. | |
| 650 | 7 | |a Loss Of Coolant. |2 local. | |
| 650 | 7 | |a Safety Analysis. |2 local. | |
| 650 | 7 | |a Computerized Simulation. |2 local. | |
| 650 | 7 | |a Temperature Dependence. |2 local. | |
| 650 | 7 | |a Steady-State Conditions. |2 local. | |
| 650 | 7 | |a Flow Rate. |2 local. | |
| 650 | 7 | |a Heat Flux. |2 local. | |
| 650 | 7 | |a General Studies Of Nuclear Reactors. |2 edbsc. | |
| 710 | 2 | |a Argonne National Laboratory. |4 res. | |
| 710 | 1 | |a United States. |b National Nuclear Security Administration. |4 spn. | |
| 710 | 1 | |a United States. |b Department of Energy. |b Office of Scientific and Technical Information. |4 dst. | |
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