Criticality reference benchmark calculations for burnup credit using spent fuel isotopics
Description
To date, criticality analyses performed in support of the certification of spent fuel casks in the United States do not take credit for the reactivity reduction that results from burnup. By taking credit for the fuel burnup, commonly referred to as ''burnup credit,'' the fuel loading capacity of these casks can be increased. One of the difficulties in implementing burnup credit in criticality analyses is that there have been no critical experiments performed with spent fuel which can be used for computer code validation. In lieu of that, a reference problem set of fresh fuel critical experiments which model various conditions typical of light water reactor (LWR) transportation and storage casks has been identified and used in the validation of SCALE-4. This report documents the use of this same problem set to perform spent fuel criticality benchmark calculations by replacing the actual fresh fuel isotopics from the experiments with six different sets of calculated spent fuel isotopics. The SCALE-4 modules SAS2H and CSAS4 were used to perform the analyses. These calculations do not model actual critical experiments. The calculated k-effectives are not supposed to equal unity and will vary depending on the initial enrichment and burnup of the calculated spent fuel isotopics. 12 refs., 11 tabs
Availability note (English)
MF available from INIS under the Report Number; OSTI as DE91013206; NTIS; INIS; US Govt. Printing Office Dep.
Files
Additional details
Publishing Information
- Imprint Pagination
- 54 p.
- Report number
- ORNL/M--1423
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22084712
- Subject category
- S42: ENGINEERING; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- BENCHMARKS; BURNUP; CASKS; CRITICALITY; ISOTOPE SEPARATION; LICENSING; S CODES; SPENT FUELS; URANIUM 234; URANIUM 235; URANIUM 236; URANIUM 238; WATER COOLED REACTORS
- Descriptors DEC
- ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; COMPUTER CODES; CONTAINERS; ENERGY SOURCES; EVEN-EVEN NUCLEI; EVEN-ODD NUCLEI; FUELS; HEAVY ION DECAY RADIOISOTOPES; HEAVY NUCLEI; INTERNAL CONVERSION RADIOISOTO; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MAGNESIUM 28 DECAY RADIOISOTOP; MATERIALS; MINUTES LIVING RADIOISOTOPES; NEON 24 DECAY RADIOISOTOPES; NUCLEAR FUELS; NUCLEI; RADIOISOTOPES; REACTOR MATERIALS; REACTORS; SEPARATION PROCESSES; SPONTANEOUS FISSION RADIOISOTO; URANIUM ISOTOPES; YEARS LIVING RADIOISOTOPES
Optional Information
- Contract/Grant/Project number
- Contract AC05-84OR21400; AC04-76DP00789
- Funding organization
- USDOE, Washington, DC (USA).