A simple gamma spectrometry method for evaluating the burnup of MTR-type HEU fuel elements-Reference-Cited by-同舟云学术

A simple gamma spectrometry method for evaluating the burnup of MTR-type HEU fuel elements

Published:2016-10 Issue: Volume:834 Page:175-182
ISSN:0168-9002
Container-title:Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment
language:en
Short-container-title:Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment

Author:

Makmal T.,Aviv O.,Gilad E.

Publisher

Elsevier BV

Subject

Instrumentation,Nuclear and High Energy Physics

Reference54 articles.

1. Introduction to Nuclear Reactor Theory;Lamarsh,1966

2. Dissolution and burnup determination of irradiated U-Zr alloy nuclear fuel by chemical methods;Kim;Nucl. Eng. Technol.,2006

3. ASTM C1769-15, Standard Practice for Analysis of Spent Nuclear Fuel to Determine Selected Isotopes and Estimate Fuel Burnup, ASTM International, West Conshohocken, PA, 2015.

4. EGADSNF, Spent nuclear fuel assay data for isotopic validation - State-of-the-art Report, Paris, France: OECD, NEA/NSC/WPNCS/DOC(2011)5, 2011.

5. Irradiated fuel measurements;Phillips,1991

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