Filters
Results 1 - 10 of 5505
Results 1 - 10 of 5505.
Search took: 0.035 seconds
Sort by: date | relevance |
AbstractAbstract
[en] The purpose of this standard is to provide criteria for the qualification of reference reactor physics measurements obtained from subcritical (including non-multiplying), critical and other experiments for the purpose of verifying nuclear design and analysis methods. It provides guides for documentation of reference data and independent expert review of proposed reference reactor physics data to assure compliance with the criteria of this standard
Primary Subject
Source
1978; 9 p; American Nuclear Society; La Grange Park, IL; ANSI/ANS--19.5-1978
Record Type
Book
Literature Type
Standard
Country of publication
Publication YearPublication Year
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Martinelli, R.
Nuclear Energy Agency, 75 - Paris (France)
Nuclear Energy Agency, 75 - Paris (France)
AbstractAbstract
[en] This paper is the summary record of the thirty-third meeting (Technical session) of the Nuclear Energy Agency Committee on Reactor Physics. A complete list of all the papers presented at this meeting is given in annex 4
Primary Subject
Source
1991; 57 p; 33. Meeting of NEA Committee on Reactor Physics; Paris (France); 15-19 Oct 1990
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Publication YearPublication Year
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] By making a deliberate use of physical laws it is possible to build fission reactors with a high level of inherent safety. This safety, which is independent of human intervenience or of active safety systems, protects man against the nuclear reactor but also the reactor against man. This article discusses the physical principles of a possible new generation of nuclear reactors, for which inherent safety is the starting point for the design. (author). 3 refs.; 6 figs
Original Title
Inherent veilige kernreactoren
Primary Subject
Record Type
Journal Article
Journal
Country of publication
Publication YearPublication Year
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] The article reports on the second Frederic Joliot Summer School in reactor physics which took place in Cadarache in August 1996 and gathered 46 young scientists and engineers from eleven European plus five from non-European countries
Primary Subject
Record Type
Journal Article
Journal
Country of publication
Publication YearPublication Year
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] This document is a compilation of National activity reports presented at the thirty-third Meeting of the NEA Committee on Reactor Physics, held at OECD Headquarters, Paris, from 15th - 19th October 1990
Primary Subject
Source
1990; 196 p
Record Type
Report
Report Number
Country of publication
Publication YearPublication Year
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Murray, R.L.
Proceedings: thermal-reactor benchmark calculations, techniques, results, and applications
Proceedings: thermal-reactor benchmark calculations, techniques, results, and applications
AbstractAbstract
[en] The object of the work reported is to develop educational computer modules for all aspects of reactor physics. The modules consist of a description of the theory, mathematical method, computer program listing, sample calculations, and problems for the student, along with a card deck. Modules were first written in FORTRAN for an IBM 360/75, then later in BASIC for microcomputers. Problems include: limitation of equipment, choice of format for the program, the variety of dialects of BASIC used in the different microcomputer and peripherals brands, and knowing when to quit in the process of developing a program
Primary Subject
Source
Rose, P.F.; Brookhaven National Lab., Upton, NY (USA); p. 13.1-13.5; Feb 1983; p. 13.1-13.5; Thermal reactor benchmark calculations, techniques, results and applications seminar; Upton, NY (USA); 17-18 May 1982; Available from NTIS, PC A99/MF A01; 1 as DE83009254
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Publication YearPublication Year
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] In a study of the perturbative effects of a slight internal interface shift within a reactor, the authors came across an anomaly in the use of standard first-order perturbation theory. The purpose of this work is to bring this interesting anomaly to the attention of the reactor physics community. On the more practical side, the discussion shows that the use of standard first-order perturbation theory gives an incorrect result for one particular class of problems. The source of this error is identified and the correct perturbative formula for this type of problem is derived. 3 refs
Primary Subject
Record Type
Journal Article
Journal
Nuclear Science and Engineering; ISSN 0029-5639;
; v. 78(4); p. 393-395

Country of publication
Publication YearPublication Year
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] A review is given of papers presented at the International Symposium on Fast Reactor Physics organized by the IAEA and the OECD Nuclear Energy Agency in Aix-en-Provence in France from September 24 to 28, 1979. (J.B.)
Original Title
Mezinarodni symposium o fyzice rychlych reaktoru
Primary Subject
Record Type
Journal Article
Journal
Nukleon; (no.2); p. 18-19
Country of publication
Publication YearPublication Year
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] This letter points out that the classical first-order perturbation formula will not correctly treat the case of a slight internal interface shift. Indicates that the traditional derivation, equation, and interpretation of classic first-order perturbation theory are all entirely correct if the perturbed problem differs from the unperturbed one by a material property perturbation
Primary Subject
Secondary Subject
Record Type
Journal Article
Journal
Nuclear Science and Engineering; ISSN 0029-5639;
; v. 84(1); p. 73

Country of publication
Publication YearPublication Year
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Liang, Liang; Liu, Zhouyu; Zheng, Youqi; Cao, Liangzhi; Wu, Hongchun, E-mail: liuzhouyu1985@Hotmail.com
AbstractAbstract
[en] The 2D/1D fusion method (2D/1D method) is becoming a standard transport method for whole-core calculations, which reduces the group condense and assembly homogenization approximations in the conventional two-step reactor physics calculations. In most 2D/1D codes, a pin is chosen as a 1D calculation domain, which assumes that the axial leakage of the pin is flat on top/bottom surfaces. Similar to the axial leakage, the radial leakage of every 2D plane also introduces several approximations along axial direction for the 1D calculation. This paper studied the error introduced by both axial and radial leakages, and proposed a leakage reconstruction method according to the error analysis for the 2D/1D fusion method, in which MOC is applied to the radial 2D calculation and the Sn diamond difference method is used for the axial 1D calculation. Several cases are tested to show the performance of this leakage reconstruction method especially when the leakage term is significant.
Primary Subject
Source
S0149197016302967; Available from http://dx.doi.org/10.1016/j.pnucene.2016.12.016; © 2017 Elsevier Ltd. All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
Record Type
Journal Article
Journal
Country of publication
Publication YearPublication Year
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
1 | 2 | 3 | Next |