Development of spent fuel examination technology
Description
The KMP and MBA was determined on the basis of the design of the containment and surveillance for the ACP facility. It was indicated from the safeguard ability evaluation that the pilot-scaled ACP facility is safeguardable. The prototype ASNC is composed of 20 Cd plate-attached He-3 tubes embedded in a high density PE cylinder containing a cavity of 10 cm in radius and a lead shield in its inside respectively and having a carbon neutron reflector on the top and bottom of the cylinder. The average and standard error of the neutron detection efficiency at 20 cm height are 19 % and 2 %, respectively, which satisfies the design requirements of 14 % efficiency and 2 % error. In the results of the integration analysis for the dry storage of the conditioned spent fuel, the vault type was found to be more profitable than the metal cask type, so the vault type was selected with the optimum storage system for the conditioned spent fuel. For a study of the efficient storage, the exponential decay constant for the PWR spent fuel is measured using the exponential experiment system installed in the KAERI PIEF. The neutron effective multiplication factor which is determined on the basis of the constant is shown to be roughly consistent with the calculated keff with the MCNP code. U-Nb binary alloy shows its oxidation rates one order of a magnitude less than that of the unalloyed uranium. The results from this study are applicable to the optimum stability method of the conditioned spent fuel
Availability note (English)
Available from INIS in electronic form; Also available from Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)Files
36095299.pdf
Files
(12.7 MB)
| Name | Size | Download all |
|---|---|---|
|
md5:71fd06f5be48439faca9f6ee6db1a586
|
12.7 MB | Preview Download |
Additional details
Publishing Information
- Imprint Pagination
- 483 p.
- Report number
- KAERI/RR--2432/2003
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 36095299
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Descriptors DEI
- CONTAINMENT; DESIGN; INSPECTION; M CODES; NEUTRON DETECTION; PWR TYPE REACTORS; SAFEGUARDS; SPENT FUELS
- Descriptors DEC
- COMPUTER CODES; DETECTION; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; MATERIALS; NUCLEAR FUELS; POWER REACTORS; RADIATION DETECTION; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 89 refs, 169 figs, 80 tabs