Filters
Results 1 - 10 of 4080
Results 1 - 10 of 4080.
Search took: 0.03 seconds
Sort by: date | relevance |
AbstractAbstract
No abstract available
Primary Subject
Source
ANS annual meeting; Atlanta, GA, USA; 3 - 8 Jun 1979; CONF-790602--(SUMM.); Published in summary form only.
Record Type
Journal Article
Literature Type
Conference
Journal
Transactions of the American Nuclear Society; ISSN 0003-018X;
; v. 32 p. 297-298

Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Whereas the solutions for managing intact spent fuel assemblies are well-known, a specific technical solution must be implemented for managing the defective spent fuel assemblies as well. Reprocessing the defective fuel assemblies is the most decisive way to get rid of them as there is then no need to assess the behavior of this specific type of fuel assemblies in the long-term. Defective used fuel assemblies have been and are being today safely reprocessed with specific administrative or technical measures for some of them. When reprocessing is not the preferred option, the nuclear operator must implement dry storage of the defective fuel assemblies. The purpose of this paper is to describe the existing solutions for the dry storage of all types of defective fuel assemblies. A long-term dry storage solution for defective fuel assemblies is being developed, compliant with direct disposal safety requirements. The solution is based on the dry encapsulation of each defective fuel rod into a fuel rod capsule, followed by its transfer into a capsule canister (like a fuel assembly skeleton), which is replacing a fuel assembly position of the transport and storage cask, and the associated specific licensing approach: this is the best available technology regarding long term storage safety requirements
Primary Subject
Secondary Subject
Source
Societe Francaise d'Energie Nucleaire - SFEN, 103 rue Reaumur, 75002 Paris (France); 2455 p; ISBN 978-1-4951-6286-2;
; 2015; p. 1929-1935; GLOBAL 2015 - Nuclear fuel cycle for a low-carbon future; Paris (France); 21-24 Sep 2015; Available (USB stick) from: SFEN, 103 rue Reaumur, 75002 Paris (France); 1 ref.

Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
Peerasathien, W.
Department of Nuclear Technology, Chulalongkorn Univ., Bangkok (Thailand)1974
Department of Nuclear Technology, Chulalongkorn Univ., Bangkok (Thailand)1974
AbstractAbstract
[en] This thesis is a result of test of a number of nuclear fuel rods which have not been used for a long time due to leakage of radioactivity. Water was circulated through each fuel rod in a test cylinder and radioactivity in water was measured. It was found that the detection of Cesium-137 which has a long half-life, does not indicate the extent of leakage of short-lived radioisotopes, some of which are gaseous. These gases are harmful to the reactor operators and users. A better result was obtained by placing the failed fuel rod in the test cylinder close to the reactor to induce fission. Short half-life gases or other nuclides of the same series were then directly measured
Primary Subject
Source
1974; 27 p; Chulalongkorn University; Bangkok (Thailand); Available from Graduate School, Chulalongkorn Univ., Bangkok (TH); Thesis (Master Eng.)
Record Type
Miscellaneous
Literature Type
Thesis/Dissertation; Numerical Data
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Lehto, W.K.; Koenig, J.F.; Seim, O.S.; Olp, R.H.; Strain, R.V.; Colburn, R.P.
International meeting on fast reactor safety technology1979
International meeting on fast reactor safety technology1979
AbstractAbstract
[en] The Breached Fuel Test Facility (BFTF) is a multipurpose experimental facility, designed to provide the capability to conduct and monitor safety and fuel behavior experiments under more severe conditions than previously allowed in EBR-II. The BFTF has the capability to measure flow, temperature, particle size distribution and deposition, and delayed neutron levels for breach site characterization. This paper describes the design, the instrumentation, the operational safety concerns and the initial experiments. 3 refs
Primary Subject
Source
Anon; p. 2374-2382; 1979; p. 2374-2382; American Nuclear Society; La Grange Park, IL; International meeting on fast reactor safety technology; Seattle, WA, USA; 19 - 23 Aug 1979
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Baars, R.E.
Hanford Engineering Development Lab., Richland, Wash. (USA)1976
Hanford Engineering Development Lab., Richland, Wash. (USA)1976
AbstractAbstract
[en] The Damage Parameter (DP) empirical correlation of fuel pin cladding failure thresholds for TOP events has been revised and recorrelated to the results of twelve TREAT tests. The revised correlation, called the Failure Potential (FP) correlation, predicts failure times for the tests in the data base with an average error of 35 ms for $3/s tests and of 150 ms for 50 cents/s tests
Primary Subject
Source
26 Aug 1976; 11 p; International meeting on fast reactor safety and related physics; Chicago, Illinois, USA; Oct 1976; CONF-761001--9; Available from NTIS. $3.50.
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Original Title
LMFBR
Primary Subject
Secondary Subject
Source
ANS annual meeting; San Diego, CA, USA; 18 Jun 1978; See CONF-780622--. Published in summary form only.
Record Type
Journal Article
Literature Type
Conference
Journal
Transactions of the American Nuclear Society; v. 28 p. 511-513
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Short communication
Original Title
Aspekty modelirovaniya teplofiziki tvehl i teplonositelya v avariyakh tipa R IA
Primary Subject
Source
Goncharov, L.A. (ed.) (Moskovskij Inzhenerno-Fizicheskij Inst., Moscow (Russian Federation)). Funding organisation: 4205390RU; 7041987RU; 7041988RU; 7041989RU; 7041990RU; 234 p; 1995; p. 106-107; 9. topical meeting on problems of nuclear reactor safety; 9. seminar po problemam fiziki reaktorov; Moscow (Russian Federation); 4-8 Sep 1995
Record Type
Miscellaneous
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Short communication
Original Title
Radiacni havarie na reaktoru typu RBMK na jaderne elektrarne u Sosnoveho Boru
Primary Subject
Source
English translation available from Nuclear Information Center, 156 16 Prague-Zbraslav, Czechoslovakia, at USD 10.- per typewritten page.
Record Type
Journal Article
Journal
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Schmidt, J.P.
United Nuclear Industries, Inc., Richland, WA (USA)1978
United Nuclear Industries, Inc., Richland, WA (USA)1978
AbstractAbstract
[en] Two inner and two outer N-Reactor MKIV fuel elements were subjected to calculated maximum loss-of-coolant thermal transients. The fuels were heated inductively in air at one atmosphere pressure. Pertinent failure temperature and burnup data are presented
Primary Subject
Secondary Subject
Source
Mar 1978; 5 p; Available from NTIS., PC A02/MF A01
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] The thermomechanical behaviour of an hexagonal can in a benchmark problem (simulating the conditions of a BTI accident in a fuel assembly) is examined by means of the INCA code and the results systematically compared with those of ADINA
Primary Subject
Secondary Subject
Source
1988; 32 p
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
1 | 2 | 3 | Next |