Published October 2000 | Version v1
Miscellaneous Metadata-only

Enrichment measurement development of fuel material by NDA neutron counter

Creators

  • 1. KAERI, Taejon (Korea, Republic of)

Description

A neutron count method has been developed to determine the fissile content by NDA neutron counter. Active neutron multiplicity measurements to assay enrichment of uranium powder have been carried out. The total neutron counts between the induced and non-induced fission by neutron source in sample were measured. These results are compared to equivalent results obtained from MCNP calculation. It shows that the measured neutron count ratio versus quantity of UO2 enrichment is reasonably well agreed with the calculated values

Part of:
Proceedings of the KNS autumn meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the KNS autumn meeting
Imprint Pagination
[CD-ROM]
Journal Page Range
[8 p.]

Conference

Title
2000 autumn meeting of the KNS
Dates
26-27 Oct 2000
Place
Taejon (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
34050673
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
ISOTOPE RATIO; M CODES; MONTE CARLO METHOD; NEUTRON DETECTION; NEUTRON SOURCES; NONDESTRUCTIVE ANALYSIS; URANIUM DIOXIDE
Descriptors DEC
ACTINIDE COMPOUNDS; CALCULATION METHODS; CHALCOGENIDES; CHEMICAL ANALYSIS; COMPUTER CODES; DETECTION; OXIDES; OXYGEN COMPOUNDS; PARTICLE SOURCES; RADIATION DETECTION; RADIATION SOURCES; URANIUM COMPOUNDS; URANIUM OXIDES

Optional Information

Notes
3 refs, 3 figs