Published 1993
| Version v1
Report
Open
New developments enhancing MCNP for criticality safety
Description
Since the early 80's MCNP has had three estimates of keff: collision, absorption, and track length. MCNP has also had collision and absorption estimators of removal lifetime. These are calculated for every cycle and are averaged over the cycles as simple averages and covariance weighted averages. Correlation coefficients between estimators are also calculated. These criticality estimators are all in addition to the extensive summary information and tally edits used in shielding and other problems. A number of significant new developments have been made to enhance the MCNP Monte Carlo radiation transport code for criticality safety applications. These are available in the newly released MCNP4A version of the code
Availability note (English)
MF available from INIS under the Report Number; OSTI as DE93010698; NTIS; INIS; US Govt. Printing Office Dep.Files
24069784.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 8 p.
- Report number
- LA-UR--93-758
Conference
- Title
- American Nuclear Society meeting.
- Dates
- 19-23 Sep 1993.
- Place
- Nashville, TN (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24069784
- Subject category
- S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COLLISIONS; CRITICALITY; ENERGY DEPOSITION; M CODES; MONTE CARLO METHOD; NEUTRAL-PARTICLE TRANSPORT; NEUTRON TRANSPORT; PHOTON TRANSPORT; RADIATION PROTECTION; SAFETY
- Descriptors DEC
- CALCULATION METHODS; COMPUTER CODES; RADIATION TRANSPORT
Optional Information
- Contract/Grant/Project number
- Contract W-7405-ENG-36
- Funding organization
- USDOE, Washington, DC (United States).
- Secondary number(s)
- CONF-9309120--1.