FIELD: power industry.
SUBSTANCE: active zone (AZ) of fast U-Pu reactor consists of alternating zones of little (ZLE) and major (ZME) enrichment. In these zones 239Pu concentration is lower or higher accordingly than plutonium equilibrium concentration. AZ comprises also control units: bars made of 10B compounds and device for non-reversible injection of 238U into ZLE. AZ parametres are selected to provide setting of self-governing neutral nuclear mode, in which fast reactor operates in quasi-steady mode with KBA-1. Building up power is performed during the first 3 to 6 days, attainment of 239Np equilibrium concentration and self-governing reactor operation - during 10 to 20 days. Besides 239Pu combusting in the whole AZ is fully replaced by 239Pu produced in ZLE from 238U. Decomposition delay ensures safety of reactor. 238U insertion provides fine reactor power control and its simulteneous makeup fuel supply.
EFFECT: increasing of reactor operating period to 2 to 3 years without fuel recharging, reactor's safety improvement.
8 cl, 1 dwg
Title | Year | Author | Number |
---|---|---|---|
ACTIVE ZONE OF FAST U-Pu REACTOR FOR OPERATION IN SELF-REGULATING NEUTRON-NUCLEAR MODE (KVA ~ 1), AND REACTOR POWER CONTROL METHOD | 2010 |
|
RU2455714C1 |
METHOD OF OPERATING FAST NEUTRON REACTOR WITH NITRIDE FUEL AND LIQUID METAL COOLANT | 2012 |
|
RU2501100C1 |
OPERATION METHOD OF FAST NEUTRON NUCLEAR REACTOR WITH NITRIDE FUEL AND LIQUID-METAL COOLANT | 2017 |
|
RU2638561C1 |
METHOD OF NUCLEAR RECTOR OPERATION IN FUEL CYCLE WITH EXTENDED PRODUCTION OF FISSILE ISOTOPES | 2015 |
|
RU2601558C1 |
OPERATING METHOD OF FAST NEUTRON NUCLEAR REACTOR WITH NITRIDE FUEL AND LIQUID-METAL COOLANT | 2012 |
|
RU2510085C1 |
METHOD OF OPERATING FAST NEUTRON REACTOR WITH LIQUID METAL COOLANT | 2012 |
|
RU2501101C1 |
METHOD OF OPERATING NUCLEAR REACTOR IN THORIUM FUEL CYCLE WITH PRODUCTION OF URANIUM ISOTOPE U | 2016 |
|
RU2634476C1 |
METHOD OF OPERATING A NUCLEAR REACTOR IN A CLOSED THORIUM FUEL CYCLE | 2018 |
|
RU2690840C1 |
METHOD OF OPERATION OF THE NUCLEAR REACTOR IN THE URANIUM-THORIUM FUEL CYCLE WITH THE WORK OF ISOTOPE U | 2016 |
|
RU2619599C1 |
LOW-POWER FAST NEUTRON MODULAR NUCLEAR REACTOR WITH LIQUID METAL HEAT CARRIER AND REACTOR CORE (VERSIONS) | 2019 |
|
RU2699229C1 |
Authors
Dates
2010-08-20—Published
2008-11-06—Filed