Published 1999 | Version v1
Book Metadata-only

Development of NDA measurement method to determine the fissile material contents for DUPIC fuel

Creators

  • 1. Korea Atomic Energy Research Inst., Taejon (Korea, Republic of)

Description

Neutron measurement method by NDA is being developed and simulated for the possible use in determination of fissile contents of DUPIC (Direct Use of Spent PWR Fuel in CANDU) fuel. This method could effectively be applied to DUPIC fuel design, fabrication and its safeguard implementation under the condition of very high radiation environment. The change of neutron count between the induced and non induced fission by Cm 244 spontaneous fission neutron in spent fuel was analyzed. Results from MCNP calculation model for the two-parameter (singles and doubles) are compared with NDA measurements using PWR spent fuel rod-cuts at KAERI. It shows that the measured neutron count ratio versus quantity of spent fuel material is reasonably well agreed with the calculated values. (author)

Availability note (English)

Available on CD-ROM from Canadian Nuclear Association, Toronto, Ontario, Canada M5J 2L7
Part of:
Proceedings of the 39. annual Canadian Nuclear Association conference and 20. annual Canadian Nuclear Society conference

Additional details

Publishing Information

Publisher
Canadian Nuclear Association, Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
Imprint Title
Proceedings of the 39. annual Canadian Nuclear Association conference and 20. annual Canadian Nuclear Society conference
Imprint Pagination
640 Megabytes
Journal Page Range
(Session A3) [8 p.]
ISSN
0227-1907

Conference

Title
Communicating the nuclear advantage
Dates
30 May - 2 Jun 1999
Place
Montreal, PQ (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
32002706
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CANDU TYPE REACTORS; COMPARATIVE EVALUATIONS; FISSILE MATERIALS; FISSION PRODUCTS; NEUTRON MONITORS; SPENT FUELS
Descriptors DEC
ENERGY SOURCES; EVALUATION; FISSIONABLE MATERIALS; FUELS; HEAVY WATER MODERATED REACTORS; ISOTOPES; MATERIALS; MEASURING INSTRUMENTS; MONITORS; NUCLEAR FUELS; POWER REACTORS; PRESSURE TUBE REACTORS; RADIATION MONITORS; RADIOACTIVE MATERIALS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS

Optional Information

Notes
6 refs., 3 figs.