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.

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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.