Overview of spent fuel burnup measurements

Conference · Tue Jan 01 00:00:00 EST 1991 · Nuclear Materials Management. Annual Meeting Proceedings; (United States)

OSTI ID:5711443

McLeod, N B ^[1]

---

1. Johnson (E.R.) Associates, Inc., Oakton, VA (United States)

The purpose of this paper is to provide a summary of the principal factors that influence burnup measurement accuracy, and the manner in which different combinations of these factors in any particular application influence the achievable accuracy in that application. The principal focus of the paper is on the passive measurement of various burnup indicators. This paper also provides a general background for four subsequent papers which discuss burnup measurement in two particular applications: for burnup credit in spent fuel shipping casks; and for safeguards purposes. This paper provides a basis for comparing these two applications in terms that directly relate to the measurement process.

• OSTI ID: 5711443
• Report Number(s): CONF-910774-; CODEN: NUMMB
• Journal Information: Nuclear Materials Management. Annual Meeting Proceedings; (United States), Vol. 20; Conference: 32. Institute of Nuclear Materials Management (INMM) annual meeting, New Orleans, LA (United States), 28-31 Jul 1991; ISSN 0362-0034
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL PROTECTION
BURNUP
REVIEWS
SPENT FUELS
ACCURACY
MEASURING METHODS
SAFEGUARDS
SPENT FUEL CASKS
USES
CASKS
CONTAINERS
DOCUMENT TYPES
ENERGY SOURCES
FUELS
MATERIALS
NUCLEAR FUELS
REACTOR MATERIALS
220300* - Nuclear Reactor Technology- Fuel Elements
050900 - Nuclear Fuels- Transport
Handling
& Storage
055000 - Nuclear Fuels- Safeguards
Inspection
& Accountability