Published March 2000
| Version v1
Journal article
Calculation of waste disposal rating for the fusion experimental breeder FEB-E
Description
Using the neutron transport code BISON 3.0, activation calculation code FDKR and its associated data libraries, the activation calculation and analyses of all long-lived radionuclides are performed for the Fusion Experimental Breeder FEB-E. The results indicate that the first wall and blanket structure materials of the FEB-E can meet the nuclear waste disposal criteria for the NRC 10CFR61 Class C after a few weeks from shutdown. The inventory of important actinides during field reprocessing, such as 232U and 237Np, are also calculated. Their concentrations do not excess the limit value required for environmental safety
Additional details
Publishing Information
- Journal Title
- Nuclear Fusion and Plasma Physics
- Journal Volume
- 20
- Journal Issue
- 1
- Journal Page Range
- p. 13-20
- ISSN
- 0254-6086
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 32020800
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S43: PARTICLE ACCELERATORS;
- Descriptors DEI
- ACCELERATOR BREEDERS; ACCELERATOR DRIVEN TRANSMUTATION; CALCULATION METHODS; CONCENTRATION RATIO; EXPERIMENTAL REACTORS; HYBRID REACTORS; LIMITING VALUES; NEPTUNIUM 237; NEUTRON TRANSPORT; RADIOACTIVE WASTE DISPOSAL; URANIUM 232
- Descriptors DEC
- ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; EVEN-EVEN NUCLEI; HEAVY ION DECAY RADIOISOTOPES; HEAVY NUCLEI; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MANAGEMENT; NANOSEC LIVING RADIOISOTOPES; NEON 24 DECAY RADIOISOTOPES; NEPTUNIUM ISOTOPES; NEUTRAL-PARTICLE TRANSPORT; NUCLEI; ODD-EVEN NUCLEI; RADIATION TRANSPORT; RADIOACTIVE WASTE MANAGEMENT; RADIOISOTOPES; REACTORS; RESEARCH AND TEST REACTORS; SPONTANEOUS FISSION RADIOISOTOPES; TRANSMUTATION; URANIUM ISOTOPES; WASTE DISPOSAL; WASTE MANAGEMENT; YEARS LIVING RADIOISOTOPES