Published October 2000 | Version v1
Miscellaneous Metadata-only

Comparison between Monte Carlo Method and 3-D SN method for fast neutron fluence calculation at RPV

Creators

  • 1. Hanyang Univ., Seoul (Korea, Republic of)
  • 2. Seoul National Univ., Seoul (Korea, Republic of)
  • 3. Korea Institute of Nculear Safety, Taejon (Korea, Republic of)

Description

Fast neutron fluence was evaluated for KNGR RPV using Monte Carlo code, MCNP and 3-D discrete ordinates code, TORT. The power distributions were calculated by ROCS code. Number density of 38 assemblies and reactor composition materials were calculated by using CASMO run, and the weighted fission spectrum from U-235 and Pu-239 was used as neutron source for MCNP and TORT. BUGLE96 was used for nuclear interaction data in TORT run and continuous nuclear interaction data was in MCNP run. As a result, the both runs give maximum values near 34 .deg. C, and TORT gives 3.19x1010 and MCNP gives 2.769x1010

Part of:
Proceedings of the KNS autumn meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the KNS autumn meeting
Imprint Pagination
[CD-ROM]
Journal Page Range
[9 p.]

Conference

Title
2000 autumn meeting of the KNS
Dates
26-27 Oct 2000
Place
Taejon (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
34050682
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COMPARATIVE EVALUATIONS; FAST NEUTRONS; M CODES; MONTE CARLO METHOD; NEUTRON FLUENCE; POWER DISTRIBUTION; PRESSURE VESSELS; R CODES; REACTOR VESSELS
Descriptors DEC
BARYONS; CALCULATION METHODS; COMPUTER CODES; CONTAINERS; ELEMENTARY PARTICLES; EVALUATION; FERMIONS; HADRONS; NEUTRONS; NUCLEONS

Optional Information

Notes
10 refs, 6 figs, 1 tab