Zobrazeno 1 - 10
of 32
pro vyhledávání: '"J.P. Renier"'
The Primary objective of the proposed project is to apply and extend the latest advancements in LWR fuel management optimization to the design of advanced boiling water reactor (BWR) fuel assemblies specifically for the recycling of minor actinides (
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7247fe00b750254972c4710d29c68495
https://doi.org/10.2172/978472
https://doi.org/10.2172/978472
This report summarizes the neutronics analysis performed during 1991 and 1992 in support of characterization of the conceptual design of the Advanced Neutron Source (ANS). The methods used in the analysis, parametric studies, and key results supporti
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https://explore.openaire.eu/search/publication?articleId=doi_________::1ce76490fa36ecd1df68b7b8c706ab74
https://doi.org/10.2172/206382
https://doi.org/10.2172/206382
The original ANSL-V cross-section libraries (ORNL-6618) were developed over a period of several years for the physics analysis of the ANS reactor, with little thought toward including the materials commonly needed for shielding applications. Material
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https://explore.openaire.eu/search/publication?articleId=doi_________::2e6c444b6460289683e05ab50ae76471
https://doi.org/10.2172/205673
https://doi.org/10.2172/205673
Autor:
J.P. Renier, L.A. Smith
A module in the VENTURE reactor analysis code system, CTRLPOS, is developed to position control rods and perform control rod position criticality searches. The module is variably dimensioned so that calculations can be performed with any number of co
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https://explore.openaire.eu/search/publication?articleId=doi_________::b64ecc7934f25a16caae44c36c42b1cf
https://doi.org/10.2172/10171499
https://doi.org/10.2172/10171499
A new fuel loading design has been developed for the Advanced Neutron Source Reactor. In this reactor the combination of a small core volume and high power results in a very high power density. Using a direct optimization procedure the thermal-hydrau
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2610b97a14e67d87e0df6971ed378299
https://doi.org/10.2172/10152570
https://doi.org/10.2172/10152570
Autor:
C. Parks, J.P. Renier
The requirements of ANSI/ANS 8.1 specify that calculational methods for away-from-reactor criticality safety analysis be validated against experimental measurements. Criticality safety evaluations of spent fuel storage and transportation casks have t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f39641adcafcffa70dbaabf04a0f7d31
https://doi.org/10.2172/6882841
https://doi.org/10.2172/6882841
The use of an external neutron source, generated via an accelerator, represents a potential means for producing the fissile isotopes /sup 233/U and /sup 239/Pu. One promising accelerator-breeder concept employs a sodium-cooled ternary metal fertile b
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1ad138bd38bef302cc3413ed23681b15
https://doi.org/10.2172/6164310
https://doi.org/10.2172/6164310
Autor:
S.B. Ludwig, J.P. Renier
The purpose of this report is to describe an updated set of reactor models for pressurized-water reactors (PWRs) and boiling-water reactors (BWRs) operating on uranium fuel cycles and the methods used to generate the information for these models. Sin
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d3a435ad0b4e8aee62b3be9283cb0bd4
https://doi.org/10.2172/5229728
https://doi.org/10.2172/5229728
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