Published 1997
| Version v1
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Application of neutron multiplicity counting to waste assay
Creators
- 1. Los Alamos National Lab., NM (United States)
- 2. North Carolina State Univ., Raleigh, NC (United States)
Description
This paper describes the use of a new figure of merit code that calculates both bias and precision for coincidence and multiplicity counting, and determines the optimum regions for each in waste assay applications. A open-quotes tunable multiplicityclose quotes approach is developed that uses a combination of coincidence and multiplicity counting to minimize the total assay error. An example is shown where multiplicity analysis is used to solve for mass, alpha, and multiplication and tunable multiplicity is shown to work well. The approach provides a method for selecting coincidence, multiplicity, or tunable multiplicity counting to give the best assay with the lowest total error over a broad spectrum of assay conditions. 9 refs., 6 figs
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Additional details
Publishing Information
- Imprint Title
- Proceedings for the nondestructive assay and nondestructive examination waste characterization conference. No. 5
- Imprint Pagination
- 521 p.
- Journal Page Range
- p. 195-210.
- Report number
- CONF-970126--
Conference
- Title
- 5. nondestructive assay/nondestructive examination waste characterization conference.
- Dates
- 14-16 Jan 1997.
- Place
- Salt Lake City, UT (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 29021830
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCURACY; ALPHA-BEARING WASTES; COINCIDENCE METHODS; NEUTRON DETECTION
- Descriptors DEC
- COUNTING TECHNIQUES; DETECTION; MATERIALS; RADIATION DETECTION; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; WASTES