Experiment for accurate measurements of fission product energy release for short times after thermal-neutron fission of $sup 235$U and $sup 239$Pu
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- DOE Contract Number:
- W-7405-ENG-26
- NSA Number:
- NSA-32-016562
- OSTI ID:
- 4180859
- Report Number(s):
- ORNL-TM-4676
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-75
- Country of Publication:
- United States
- Language:
- English
Similar Records
Analysis of fission-product energy release after thermal-neutron fission of {sup 235}U and {sup 239}Pu by scale-6.1.3 with recently available fission product yield data - 14419
Fission-product energy release for times following thermal-neutron fission of /sup 235/U between 2 and 14000 seconds
FISSION-PRODUCT CONCENTRATION AFTER THERMAL FISSION OF $sup 235$U AND $sup 239$Pu AND AFTER FAST FISSION (E approximately 1 MeV) OF $sup 235$U, $sup 238$U, AND $sup 239$Pu.
Conference
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Tue Sep 15 00:00:00 EDT 2015
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OSTI ID:4180859
Fission-product energy release for times following thermal-neutron fission of /sup 235/U between 2 and 14000 seconds
Technical Report
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Sat Oct 01 00:00:00 EDT 1977
·
OSTI ID:4180859
+4 more
FISSION-PRODUCT CONCENTRATION AFTER THERMAL FISSION OF $sup 235$U AND $sup 239$Pu AND AFTER FAST FISSION (E approximately 1 MeV) OF $sup 235$U, $sup 238$U, AND $sup 239$Pu.
Technical Report
·
Thu Jan 01 00:00:00 EST 1970
·
OSTI ID:4180859
Related Subjects
N77900* -Reactors-Reactor Safety & Environmental Aspects
N77100 -Reactors-Power Reactors
Non-breeding
Light-water Moderated
Boiling Water-cooled
N77200 -Reactors-Power Reactors
Non-breeding
Light-water Moderated
Non-boiling Water-cooled
*AFTER-HEAT
*BWR TYPE REACTORS- LOSS OF COOLANT
*LOSS OF COOLANT
*PWR TYPE REACTORS- LOSS OF COOLANT
FISSION PRODUCTS
PLUTONIUM 239
REACTOR SAFETY
URANIUM 235
N77100 -Reactors-Power Reactors
Non-breeding
Light-water Moderated
Boiling Water-cooled
N77200 -Reactors-Power Reactors
Non-breeding
Light-water Moderated
Non-boiling Water-cooled
*AFTER-HEAT
*BWR TYPE REACTORS- LOSS OF COOLANT
*LOSS OF COOLANT
*PWR TYPE REACTORS- LOSS OF COOLANT
FISSION PRODUCTS
PLUTONIUM 239
REACTOR SAFETY
URANIUM 235