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Journal Articles

Overview of the OECD-NEA Working Party on International Nuclear Data Evaluation Cooperation (WPEC)

Fleming, M.*; Bernard, D.*; Brown, D.*; Chadwick, M. B.*; De Saint Jean, C.*; Dupont, E.*; Ge, Z.*; Harada, Hideo; Hawari, A.*; Herman, M.*; et al.

EPJ Web of Conferences, 239, p.15002_1 - 15002_4, 2020/09

 Times Cited Count:0 Percentile:0.1

Journal Articles

The CIELO Collaboration; Neutron reactions on $$^1$$H, $$^{16}$$O, $$^{56}$$Fe, $$^{235,238}$$U, and $$^{239}$$Pu

Chadwick, M. B.*; Dupont, E.*; Bauge, E.*; Blokhin, A.*; Bouland, O.*; Brown, D. A.*; Capote, R.*; Carlson, A. D.*; Danon, Y.*; De Saint Jean, C.*; et al.

Nuclear Data Sheets, 118, p.1 - 25, 2014/04

 Times Cited Count:105 Percentile:98.52(Physics, Nuclear)

CIELO (Collaborative International Evaluated Library Organization) provides a new working paradigm to facilitate evaluated nuclear reaction data advances. It brings together experts from across the international nuclear reaction data community to identify and document discrepancies among existing evaluated data libraries, measured data, and model calculation interpretations, and aims to make progress in reconciling these discrepancies to create more accurate ENDF-formatted files. The focus will initially be on a small number of the highest-priority isotopes, namely $$^{1}$$H, $$^{16}$$O, $$^{56}$$Fe, $$^{235,238}$$U, and $$^{239}$$Pu. This paper identifies discrepancies between various evaluations of the highest priority isotopes. The evaluated data for these materials in the existing nuclear data libraries are reviewed, and some integral properties are given. The paper summarizes a program of nuclear science and computational work needed to create the new CIELO nuclear data evaluations.

Journal Articles

Statistical uncertainties of nondestructive assay for spent nuclear fuel by using nuclear resonance fluorescence

Shizuma, Toshiyuki; Hayakawa, Takehito; Angell, C.; Hajima, Ryoichi; Minato, Futoshi; Suyama, Kenya; Seya, Michio; Johnson, M.*; McNabb, D.*

Nuclear Instruments and Methods in Physics Research A, 737, p.170 - 175, 2014/02

 Times Cited Count:1 Percentile:10.27(Instruments & Instrumentation)

We estimated statistical uncertainties of a nondestructive assay system using nuclear resonance fluorescence (NRF) for spent nuclear fuel including low-concentrations of actinide nuclei with an intense, mono-energetic photon beam. Background counts from radioactive materials inside the spent fuel were calculated with the ORIGEN2.2-UPJ burn-up computer code. Coherent scattering contribution associated with Rayleigh, nuclear Thomson, and Delbr$"u$ck scattering was also considered. Assuming that the total NRF cross sections are in the range of 3 to 100 eV$$cdot$$b at excitation energies of 2.25, 3.5, and 5 MeV, statistical uncertainties of the NRF measurement were estimated. We concluded that it is possible to assay 1% actinide content in the spent fuel with 2.2 to 3.2% statistical precision during 4000 second measurement time for the total integrated cross section of 30 eV$$cdot$$b at excitation energies of 3.5 to 5 MeV.

Oral presentation

NRF-based NDA of nuclear material using monochromatic $$gamma$$-ray beam

Shizuma, Toshiyuki; Hayakawa, Takehito; Angell, C.; Hajima, Ryoichi; Minato, Futoshi; Suyama, Kenya; Seya, Michio; Johnson, M.*; McNabb, D.*

no journal, , 

One of the urgent issues for NDA is to establish a reliable technique for the assay of nuclear materials in spent nuclear fuel. The system performance such as counting precision for the NRF-based NDA, would be affected by radiation backgrounds from spent fuel. Generally, the $$gamma$$-ray spectrum of radiation backgrounds from spent fuel has characteristic shape with an exponential fall-off as a function of $$gamma$$-ray energy. Therefore, the NRF measurement at higher energies is preferable to obtain a better signal-to-noise ratio. The counting precision is also affected by backgrounds from the coherent scattering. In order to minimize the Coherent scattering contribution, we propose a method in which NRF transitions to the first excited state is measured. Assuming various cross sections for NRF in the range of 3 to 100 eV barn at excitation energies of 2 to 5 MeV, we have estimated the statistical uncertainties of the proposed NDA system.

Oral presentation

Background contributions of NRF-based nondestructive assay for spent nuclear fuel

Shizuma, Toshiyuki; Hayakawa, Takehito; Angell, C.; Hajima, Ryoichi; Minato, Futoshi; Suyama, Kenya; Seya, Michio; Johnson, M.*; McNabb, D.*

no journal, , 

It is required to measure spent nuclear fuel as accurate as possible for nuclear material management concerning nuclear security and safeguards. The system performance such as counting precision for the $$gamma$$-ray nondestructive assay (NDA) based on nuclear resonance fluorescence (NRF) would be affected by radiation backgrounds from spent fuel. Generally, the $$gamma$$-ray spectrum of radiation backgrounds from spent fuel has characteristic shape with an exponential fall-off as a function of $$gamma$$-ray energy. Therefore, the NRF measurement at higher energies is preferable to obtain a better signal-to-noise ratio. The counting precision is also affected by backgrounds from the coherent scattering such as Rayleigh, nuclear Thomson, and Delbr$"u$ck scattering. In order to minimize the Coherent scattering contribution, we propose a method in which NRF transitions to the first excited state is measured. We calculated the radiation background counts from spent fuel as well as the coherent scattering background. Assuming various cross sections for NRF in the range of 3 to 100 eV barn at excitation energies of 2 to 5 MeV, we have estimated the statistical uncertainties of the proposed NDA system. We also discuss the NRF strength based on the previous experimental data as well as theoretical prediction by quasi-particle random phase approximation (QRPA).

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