Feasibility study of applying the passive safety system concept to fusion–fission hybrid reactor
Creators
Description
The fusion–fission hybrid reactor can produce energy, breed nuclear fuel, and handle the nuclear waste, etc., with the fusion neutron source striking the subcritical blanket. The passive safety system consists of passive residual heat removal system, passive safety injection system and automatic depressurization system was adopted into the fusion–fission hybrid reactor in this paper. Modeling and nodalization of primary loop, partial secondary loop and passive core cooling system for the fusion–fission hybrid reactor using relap5 were conducted and small break LOCA on cold leg was analyzed. The results of key transient parameters indicated that the actuation of passive safety system could mitigate the accidental consequence of the 4-inch cold leg small break LOCA on cold leg in the early time effectively. It is feasible to apply the passive safety system concept to fusion–fission hybrid reactor. The minimum collapsed liquid level had great increase if doubling the volume of CMTs to increase its coolant injection and had no increase if doubling the volume of ACCs
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2014.03.049Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2014.03.049;
- PII
- S0920-3796(14)00228-2;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 89
- Journal Issue
- 4
- Journal Page Range
- p. 370-377
- ISSN
- 0920-3796
- CODEN
- FEDEEE
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 46019458
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- AFTER-HEAT REMOVAL; BREEDING BLANKETS; DEPRESSURIZATION SYSTEMS; FEASIBILITY STUDIES; FISSION; HYBRID REACTORS; LOSS OF COOLANT; RHR SYSTEMS; SAFETY INJECTION; SUBCRITICAL ASSEMBLIES; THERMONUCLEAR REACTORS; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; ENERGY SYSTEMS; EXPERIMENTAL REACTORS; NUCLEAR REACTIONS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; REMOVAL; RESEARCH AND TEST REACTORS
Optional Information
- Copyright
- Copyright (c) 2014 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.