Design basis accident studies. Final report

Nicholson, Randy

doi:10.2172/4258876

Cited by 5 publications

(2 citation statements)

References 5 publications

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“…Set 1 generated using t h e narrow resonance approximation, and Version-IV c r o s s s e c t i o n S e t 2 generated using t h e RABANZ i n t e g r a l t r a n s p o r t theory over t h e resonance energy i n t e r v a l . The i n n e r core void worth based on t h e 3.36 t o 0.10 keV causes most of the i n c r e a s e i n t h e i n n e r core void worth. I n ' Version-IV c r o s s s e c t i o n S e t 2 2 3 8~ c a p t u r e c r o s s s e c t i o n s over t h i s energy i n t e r v a l a r e 2 t o 29% h i g h e r t h a n those i n Version-IV c r o s s s e c t i o n Set 1.…”

Section: (Kalimullah) the E F F E C T Of Using Endf/b Version-iv C R mentioning

confidence: 97%

Physics of Reactor Safety (Quarterly report, January - March 1976)

Author¹

1976

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TWra repart was prepared a s an account d work aponsazad by the United Skate5 Gaverment. Neitber 1 the United States nor the W t a d Sbates Energy Research and DevelopmentAdministration, n~n any of thsir e m p h Y e e~,~n o r any of their ~o n t r a c b r s , subcontractars,or theh employeas, makes any ' w a r r a t y , express or implied, or asaumea any legal iiabil-. ity or respowibility for t b accuracy, rbmpletenese o r usefulness of a~y idomnation, oppar~tus~ product or prose-sr disclased, 5Tf represehts that its U s e Would not infri. privatelybwned sights. Menti-OR of cemuae~cial product their r a a n u f a~k u r~r s , o r their suppliaes in this publicatio I does not inply si-connote appi.oval ar disapproval ~f t product by Argonne %tianal Laborato~y er the U. W. Energ Research and Development A

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Section: (Kalimullah) the E F F E C T Of Using Endf/b Version-iv C R mentioning

confidence: 97%

Physics of Reactor Safety (Quarterly report, January - March 1976)

Author¹

1976

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“…As before, these results are compared with the theoretical work reported by Nicholson. 6 A neutronics nodel has been incorporated into the PAD analyses which calculates the UNCLASSIFIED UNCLASSIFIED (regionw.ise) reactivity feedback associated with changes in the void content at each rime step. This model also includes a spatial reactivity weighting function.…”

Section: Introductionmentioning

confidence: 99%

Effects of neutron streaming and geometric models on molten fuel recriticality accidents

McLaughlin¹

1975

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This report wr.i prepared as an account ofwnrk sponsored b\ Ihe United Slates Covernmenl. Neither the United Slates nor thr 1 nited State* Energy Research and Development Administration, nor anv of their employers, nor *nv of their contractors, nulM-nnlractor*, or their employee*, ma hen any warranty, express or implied, or assumes any legal liahilitvor ifflponHibility for the aecuracv, compleU-nnifl, or us*fulnenM o( anv information, appuratuii. produrt. or process dwlosed, or reprenentn that il* use would not infringe privately owned ihl UNCLASSIFIED EFFECTS OF NEUTRON STREAMING AND GEOMETRIC MODELS ON MOLTEN FUEL RECRITICALITY ACCIDENTS by Thomas P. McLaughlln -NOTICE-71m report was prepared as in account of work sponsored by the United Sum Gomiawn. Neither the United States not the United Stale* Enetgy Rcseaich and Development AdminJltntkM, nor any of their employees, not any of their contractors. subcontractors. 01 their employee*, sake* any warranty, express or implied, or aauiaes any lefal HaMity or responsibility for .huccuracy,completeness 01 usefulneai of any information, apparatus,product or process disclosed, or represents that its use would not iflrnnjc privately owned rtjhti.

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Streaming in Lattices

Gelbard

1983

Advances in Nuclear Science and Technology

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Design basis accident studies. Final report

Cited by 5 publications

References 5 publications

Physics of Reactor Safety (Quarterly report, January - March 1976)

Physics of Reactor Safety (Quarterly report, January - March 1976)

Effects of neutron streaming and geometric models on molten fuel recriticality accidents

Streaming in Lattices

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