Analysis of representative unprotected accidents for a sub-critical lead-bismuth eutectic reactor using IMPC-transient
Creators
- 1. Institute of Modern Physics Chinese Academy of Sciences, Lanzhou, 730000 (China)
- 2. Shanghai Nuclear Engineering Research and Design Institute Co., Ltd., Shanghai, 200000 (China)
- 3. School of Nuclear Science and Technology, University of Chinese Academy of Sciences, Beijing, 100049 (China)
- 4. Advanced Energy Science and Technology Guangdong Laboratory, Huizhou, 516000 (China)
Description
For an accelerator driven sub-critical system (ADS), the transient analysis of the sub-critical reactor is very important. It is better to use the 3D neutron transport kinetic model rather than the 0D point reactor kinetic model due to the change of the neutron spatial distribution in some conditions. The code IMPC-transient has been developed to provide an effective system safety analysis tool for Chinese ADS project, in which 3D neutron transport kinetics is available. A 10 MW ADS conceptual scheme, in which the target power is 2.5 MW and the reactor power is 7.5 MW, was proposed to test the applicability of IMPC-transient in sub-critical lead-bismuth eutectic (LBE) reactor. The steady state and three accident cases including unprotected loss of flow (ULOF), unprotected beam overpower (UBOP) and unprotected beam-trip (UBT) have been simulated, and the dynamic thermal-hydraulic response was focused on. The results show that IMPC-transient has the function of analyzing the ULOF, UBOP and UBT conditions for the sub-critical LBE reactor, and the 7.5 MW reactor conceptual scheme is feasible under steady state and has remarkable resistance against ULOF, UBOP and UBT
Additional details
Publishing Information
- Journal Title
- Journal of Radiation Research and Applied Sciences
- Journal Volume
- 16
- Journal Issue
- 1
- Journal Page Range
- p. 1-8
- ISSN
- 1687-8507
INIS
- Country of Publication
- Egypt
- Country of Input or Organization
- Egypt
- INIS RN
- 54092264
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- ACCELERATORS; ACCIDENTS; BISMUTH; LEAD; NEUTRON TRANSPORT; REACTORS; THERMAL HYDRAULICS
- Descriptors DEC
- ELEMENTS; FLUID MECHANICS; HYDRAULICS; MECHANICS; METALS; NEUTRAL-PARTICLE TRANSPORT; RADIATION TRANSPORT