<i>Physics of Nuclear Kinetics</i>

Keepin, G.R.; Weinberg, Alvin M.

doi:10.1063/1.3034187

Cited by 151 publications

(81 citation statements)

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“…This is in agreement with the results of Ref. 38 and 39 but in total disagreement with the data froir. Ref.…”

Section: (Nt) Cross Sectionsupporting

confidence: 59%

ENDF/B Summary Documentation

Ozer

Garber

1973

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INTRODUCTIONThe purpose of this publication is to provide a localized source of descriptions for the evaluations contained in the ENDF/B Library.The summary documentation presented in this volume is intended to be a more detailed description than the (File 1) comments contained in the computer readable data files, but not as detailed as the formal reports describing each ENDF/B evaluation. (A list of the published formal reports is given in the table of contents.)The summary documentations were written by the CSEWG (Cross Section Evaluation Working Group) evaluators and compiled by NNCSC (National Neutron Cross Section Center). When assembling the information for this volume, a minimum amount of editing was unavoidable. This editing primarily consisted of removing computer file listings and irreproducible graphs, since these can be easily obtained from the ENDF files with the use of standard editing or plotting programs. In a few instances, sections of the formal document were reproduced. Materials for which no summary documentation has been received to date, are represented by the (File 1) comments contained in the data file only.The loose leaf"independent section format was selected for ease of updating when more documentation and/or evaluations become available. It is hoped that In the future a more standardized documentation will make the updating simplified.The publication is presented in sections, each section describing one (or more) ENDF evaluations. These sections are identified and ordered by element number (Z) and atomic weight (A). Sections describing more than one ENDF material are identified by the Z-A numbers of the lowest material described. The section number corresponding to a particular data set should be determined using the table of contents.(e.g., s Li(HAT-1115) is described in Section 3-6, whereas 1S3 Cs(MAT-1141) is described in Section 47-107, which also includes 107 Ag and 10S Ag.)The ENDF/B-III Library contains 230 materials. (A material may consist of an isotope, element, molecule, or standard mixture of elements.) Ten of these materials contain thermal scattering law data only. Eightyseven materials consist of photon interaction cross sections for elements. The summary documentations presented in this volume describe the principal part of the library consisting of the remaining 133 materials with neutron cross sections specified for all relevant reactions.The documentation for a number of "lumped" fission product materials is given following the section of the corresponding fissionable material. 1-H-1 1-H-2 2-HE 2-HE-3 3-LI-6 3-LI-7 4-BE-9 S-S-10 S-B-11 6-C-12 7-N-14 8- 29-CU 29-CU-63 29-CU-65 36-KR-83 40-ZR-95 41-NB-93 41-NB-95 42-MO 42-MO-95 42-MO-97 42-M0-98 42-MO-99 42-MO-10© 43-TC-99 44-RU-101 44-RU-102 44-RU-103 44-RU-104 44-RU-105 44-RU-106 45-RH-1O3 45-RH-10S 46-PD-105 46-PD-106 46-PD-107 46-PD-109 47-AC-107 47-AG-109 48-CD-113 S3-1-131 53-1-135 S4-XE-131 S4-XE-133 54-XE-13S 55-CS-133 S5-CS-135 S5-CS-137 57-LA-139 'S8-CE- Because of ...

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“…This is in agreement with the results of Ref. 38 and 39 but in total disagreement with the data froir. Ref.…”

Section: (Nt) Cross Sectionsupporting

confidence: 59%

ENDF/B Summary Documentation

Ozer

Garber

1973

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“…where, µ i and λ i denote the delayed neutron fraction and the decay constant of the source of i-th delayed neutrons group, respectively [8].…”

Section: Mathematical Modeling and Computational Physics 2017mentioning

confidence: 99%

Stability Analysis of the IBR-2M Pulsed Reactor in Automatic Regulated Regime at Various Levels of Average Power

2018

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Abstract. The IBR-2M pulse reactor is characterized by a high level of reactivity fluctuations and consequently by a high level of fluctuations in the regulated parameter as well as in the amplitude of the power pulses. Fluctuations of the regulated parameter relative to the average level in the standard stabilization regime usually fall within the range of 20% with certain peaks up to 40%, which is close to the limits of the emergency protection operation (50%). Under these conditions the automatic regulator may receive contradictory requirements. In this paper, the results of stability analysis of the IBR-2M reactor in the automatic regulating regime at various levels of average power are presented. It is shown that stability margins of the amplitude and the phase are enough, especially for the IBR-2M reactor operation with automatic regulator.

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“…That means these equations describe the change in the neutron density within the reactor due to a change in reactivity and are the most fundamental [5] relations.…”

Section: Inverse Kinetics With Source Termmentioning

confidence: 99%

Sub-Criticality Measurement with Source Term for Research Reactor in Inverse Kinetics Method

Jahan¹,

Rahman²,

Huda³

et al. 2017

WJNST

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In reactor physics tests, it is important to monitor sub-criticality continuously during criticality approach. Reactivity measurements by the inverse kinetics method are widely used during the operation of a nuclear reactor. This technique is successfully applied at sufficiently high power level or to a core without an external neutron source where the neutron source term in point reactor kinetics equations may be neglected. For operation at low power levels or in the sub-critical domain, the increase in the fluctuation of the neutron signal may cause difficulties in the evaluation of reactivity and the effect of direct emission from the external neutron source may not be neglected. Therefore, contribution of the neutron source must be taken into account and this implies knowledge of a quantity proportional to the source strength, which calls the source term and then it should be determined. The research work has been conducted to measure reactivity with source term using a dedicated reactivity measurement system by the Least Square Inverse Kinetics Method (LSIKM). Application to a simulator of HANARO research reactor, Korea Atomic Energy Research Institute (KAERI), with known source strength and reactivity worth has showed consistent and satisfactory agreement.

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Physics of Nuclear Kinetics

Cited by 151 publications

References 0 publications

ENDF/B Summary Documentation

ENDF/B Summary Documentation

Stability Analysis of the IBR-2M Pulsed Reactor in Automatic Regulated Regime at Various Levels of Average Power

Sub-Criticality Measurement with Source Term for Research Reactor in Inverse Kinetics Method

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