Method for criticality calculations and estimation of the fissile mass based on the theory of multiplicity counting
Creators
- 1. Division of Subatomic, High Energy and Plasma Physics, Chalmers University of Technology, Goeteborg (Sweden)
- 2. Department of Physics, Faculty of Science, University of Tuzla, Tuzla (Bosnia and Herzegovina)
Description
Recently, for safeguard purposes, a theoretical model and corresponding numerical framework was elaborated by us for the calculation of the first three factorial moments of the number of neutrons leaving a fissile sample, due to one source event (a spontaneous fission with a random number of neutrons). The method is based on full 3-D transport theory, until recently only in one-speed theory. From the factorial moments, the detection rates of so-called singles, doubles and triples (S, D and T rates, also called multiplicity rates) can be derived. The model can be used for criticality safety applications in two different ways. One is that from the equations for the mean number of neutrons leaving the sample, the keff of the system can be determined with the same collision number type iteration as in traditional transport theory, even if the calculated quantities (number of emitted neutrons and the flux inside the system, respectively) are different. The second application is based on the fact that from the knowledge (via measurement) of the S, D and T rates, the mass of both the fissile and the fertile isotope can be extracted. Hence with the application of multiplicity counting, not only the keff of the system, but also the amount of fissile material can be determined in principle. (author)
Files
Additional details
Identifiers
Publishing Information
- Imprint Title
- Proceedings of the 12th international conference on nuclear criticality safety (ICNC2023)
- Imprint Pagination
- 48 p.
- Journal Page Range
- 10 p.
- Report number
- JAEA-Conf--2024-001
Conference
- Title
- 12. international conference on nuclear criticality safety
- Acronym
- ICNC2023
- Dates
- 1-6 Oct 2023
- Place
- Sendai, Miyagi (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 56006640
- Subject category
- S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FEYNMAN METHOD; FISSILE MATERIALS; ISOTOPE RATIO; MULTIPLICATION FACTORS; NEUTRON EMISSION; NEUTRON TRANSPORT THEORY; PLUTONIUM ISOTOPES; ROSSI ALPHA METHOD; SPONTANEOUS FISSION; URANIUM 235
- Descriptors DEC
- ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; CALCULATION METHODS; DECAY; DIMENSIONLESS NUMBERS; EMISSION; EVEN-ODD NUCLEI; FISSION; FISSIONABLE MATERIALS; HEAVY NUCLEI; INTERNAL CONVERSION RADIOISOTOPES; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MATERIALS; MINUTES LIVING RADIOISOTOPES; NUCLEAR DECAY; NUCLEAR REACTIONS; NUCLEI; RADIOISOTOPES; SPONTANEOUS FISSION RADIOISOTOPES; TRANSPORT THEORY; URANIUM ISOTOPES; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- 11 refs.; Also available as CD-ROM Data in PDF format, Folder Name: Session03_-Oct2_-T01 in T01_-Oral, Paper ID: of5_-0_-101_-0_-5508782.pdf