Zobrazeno 1 - 10
of 22
pro vyhledávání: '"W.P. Barthold"'
Autor:
W.P. Barthold, R.P. Wichner
Modular High-Temperature Gas-Cooled Reactor (MHTGR) concepts that house the reactor vessel in a tight but unsealed reactor building place heightened importance on the reliability of the fuel particle coatings as fission product barriers. Though accid
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::86bc33b7416046fdff6d595e798313f1
https://doi.org/10.2172/10171564
https://doi.org/10.2172/10171564
Autor:
W.P. Barthold, J. C. Beitel
Publikováno v:
Nuclear Technology. 44:44-60
Six homogeneous and heterogeneous core configurations with different fuel pin diameters and different degrees of neutronic coupling have been analyzed. All designs were based on the same design ass...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::434e6ba0d28f74441a4b330fca3fe56c
https://doi.org/10.13182/nt79-a32237
https://doi.org/10.13182/nt79-a32237
Autor:
W.P. Barthold, Constantine P. Tzanos
Publikováno v:
Nuclear Technology. 36:262-274
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bdd178d457a47728a8a9ce3f8efe875f
https://doi.org/10.13182/nt77-a31940
https://doi.org/10.13182/nt77-a31940
Publikováno v:
Nuclear Technology. 46:525-528
To avoid high energy releases in unprotected loss-of-flow accidents, cores can be designed such that the removal of sodium would add only a small amount of reactivity or even a negative reactivity to the reactor. Reduction in sodium void reactivity c
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::770fce5e2afcc54642537ae821570b7c
https://doi.org/10.13182/nt79-a32361
https://doi.org/10.13182/nt79-a32361
Autor:
W.P. Barthold, E. Hutter, R.V. Batch, Y. Orechwa, S.F. Su, R. B. Turski, J.C. Beitel, P.S.K. Lam
A parameter study was conducted to determine the interrelated effects of: loosely or tightly coupled fuel regions separated by internal blanket assemblies, number of fuel regions, core height, number and arrangement of internal blanket subassemblies,
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9b6c6980f0598026f925b74ac2a6cc14
https://doi.org/10.2172/5671539
https://doi.org/10.2172/5671539
Autor:
S.F. Su, R.V. Batch, R. B. Turski, W.P. Barthold, E. Hutter, J.C. Beitel, Y. Orechwa, P.S.K. Lam
A parameter study was conducted to determine the interrelated effects of: loosely of tightly coupled fuel regions separated by internal blanket assemblies, number of fuel regions, core height, number and arrangement of internal blanket subassemblies,
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a50c3ab9d65341924f325899ec227e5d
https://doi.org/10.2172/5545658
https://doi.org/10.2172/5545658
A critical analysis of the core/blanket complex as defined in the Phase A LMFBR Pool Guidelines was performed with respect to consistency and feasibility of the nuclear, thermal and mechanical design assumptions. Recommendations were made for changes
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e5450994db644ae5aee03a3ecaa8d60b
https://doi.org/10.2172/6519014
https://doi.org/10.2172/6519014
Autor:
C.P. Tzanos, W.P. Barthold
A numerical core/blanket design is presented for a large, 1000-MW(e) LMFBR that has a much lower sodium void coefficient of reactivity than would be the case for a core assembly made up entirely of fuel subassemblies with an appropriate number of con
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::cdb3ecd57534e83511a3e1d304410961
https://doi.org/10.2172/6943290
https://doi.org/10.2172/6943290
Autor:
C.P. Tzanos, W.P. Barthold
A numerical core/blanket design is presented for a large, 1000 MW(e) LMFBR that has a much lower sodium void coefficient of reactivity than would be the case for a core assembly made up entirely of fuel subassemblies with an appropriate number of con
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9970604c6761e0ba137bdaaac23834db
https://doi.org/10.2172/6711115
https://doi.org/10.2172/6711115
Autor:
I.G. Barthold, W.P. Barthold
The whole-core LMFBR thermal-hydraulics codes COBRA-WC, COMMIX, CORE-3D, CORTRAN and SUPERENERGY-2 were evaluated from a design analyst's point of view. The issues considered in this evaluation were the basic algorithms, code capabilities, physical m
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::11c0c06e0c023e1a7bae86491464b5f9
https://doi.org/10.2172/5757408
https://doi.org/10.2172/5757408