Nuclear data requirements for fast reactors

1984 ◽  
Vol 57 (4) ◽  
pp. 683-692 ◽  
Author(s):  
V. N. Manokhin ◽  
L. N. Usachev
Keyword(s):  
Nuclear Data ◽  
Fast Reactors ◽  
Data Requirements

Nuclear data requirements for accelerator-driven transmutation systems

1995 ◽  
Author(s):  
P. G. Young ◽  
W. B. Wilson ◽  
M. B. Chadwick
Keyword(s):  
Nuclear Data ◽  
Data Requirements

Uncertainty Assessment for Fast Reactors Based on Nuclear Data Adjustment

2014 ◽  
Vol 118 ◽  
pp. 592-595 ◽  
Author(s):  
T. Ivanova ◽  
E. Ivanov ◽  
F. Ecrabet
Keyword(s):  
Nuclear Data ◽  
Uncertainty Assessment ◽  
Fast Reactors ◽  
Data Adjustment

scholarly journals On the importance of target accuracy assessments and data assimilation for the co-development of nuclear data and fast reactors: MYRRHA and ESFR

2021 ◽  
Vol 161 ◽  
pp. 108416
Author(s):  
P. Romojaro ◽  
F. Álvarez-Velarde ◽  
O. Cabellos ◽  
N. García-Herranz ◽  
A. Jiménez-Carrascosa
Keyword(s):  
Data Assimilation ◽  
Nuclear Data ◽  
Fast Reactors ◽  
Accuracy Assessments

scholarly journals Nuclear data requirements for fusion-fission (hybrid) reactors.

1972 ◽  
Author(s):  
W.C. Wolkenhauer ◽  
B.R. Jr. Leonard
Keyword(s):  
Nuclear Data ◽  
Hybrid Reactors ◽  
Data Requirements

scholarly journals NUCLEAR DATA REQUIREMENTS FOR THE PRODUCTION OF MEDICAL ISOTOPES IN FISSION REACTORS AND PARTICLE ACCELERATORS

2000 ◽  
Author(s):  
MARC A. GARLAND ◽  
ROBERT E. SCHENTER ◽  
ROBERT J. TALBERT ◽  
STEPAN G. MASHNIK ◽  
WILLIAM B. WILSON
Keyword(s):  
Nuclear Data ◽  
Particle Accelerators ◽  
Medical Isotopes ◽  
Fission Reactors ◽  
Data Requirements

NEUTRONIC PERFORMANCE OF (U, Pu)C FUEL IN A LATTICE OF GFR USING SCALE 6.0

2016 ◽  
Vol 1814 ◽  
Author(s):  
A. A. P. Macedo ◽  
Carlos E. Velasquez ◽  
C. A. M. da Silva ◽  
C. Pereira
Keyword(s):  
Computer Analysis ◽  
Fast Reactor ◽  
Nuclear Data ◽  
Multiplication Factor ◽  
Assembly Model ◽  
Fast Reactors ◽  
Full Power ◽  
Data Libraries ◽  
Nuclear Data Libraries ◽  
Neutronic Performance

ABSTRACTThis paper studies the performance of (U, Pu)C fuel in a hexagonal assembly of a GFR (Gas Fast Reactor). The SCALE 6.0 (Standardized Computer Analysis for Licensing Evaluation version 6.0) code was used in the calculation. The goal is to evaluate the behavior of the infinite multiplication factor (kinf) for a heterogeneous assembly model using four nuclear data libraries: V6-238, V7-238, ENDF/B-VI.8 and ENDF/B-VII.0. The burnup of (U, Pu)C was performed by the TRITON-6 module, and the isotopic concentrations were evaluated during the cycle. The present work comprises calculations at Zero Power and Full Power condition. This study intends to achieve more information about different Fast Reactors.

scholarly journals Analysis of the EBR-II SHRT-45R Unprotected Loss of Flow Experiment with ERANOS and RELAP

2015 ◽  
Vol 2015 ◽  
pp. 1-14 ◽  
Author(s):  
W. F. G. van Rooijen ◽  
H. Mochizuki
Keyword(s):  
Liquid Metal ◽  
Fast Reactor ◽  
Flow Distribution ◽  
Nuclear Data ◽  
Measured Data ◽  
Outlet Temperature ◽  
Fast Reactors ◽  
Flow Experiment ◽  
Neutronic Parameters

This paper presents the results of the analysis of the Unprotected Loss of Flow (ULOF) experiment SHRT-45R performed in the EBR-II fast reactor. These experiments are being analyzed in the scope of a benchmark exercise coordinated by the IAEA. The SHRT-45R benchmark contains a neutronic and a thermal-hydraulic part and results are presented for both. Neutronic calculations are performed with the ERANOS2.0 code in combination with various sets of nuclear data. The thermal-hydraulic evaluation is done with RELAP5-3D. The results are that the major neutronic parameters are well predicted with error margins on the order of 1%. The thermal-hydraulic results are less favourable: a consistent overestimation of the outlet temperature occurs in combination with erroneous flow distribution. Observed differences with measured data cannot be explained easily. The work presented in this paper was undertaken to investigate and validate the effectiveness of the calculational tools and data that are commonly used in our lab for the design and analysis of liquid metal cooled fast reactors.

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