Published July 2000
| Version v1
Journal article
The methodology for determination of WWER-1000 reactor pressure vessel radiation exposure
- 1. NTs 'Institut yadernykh issledovanij', NAN Ukrainy, Kiev (Ukraine)
Description
The calculational-experimental methodology for determination of fast neutron fluences accumulated by WWER-1000 pressure vessel critical zones during fuel cycle is presented. Results of the methodology calculational part verification in mock-up and dosimetry experiment on operating Unit are given. The principal possibility of the presented methodology usage for monitoring of operating Unit reactor pressure vessel radiation exposure is shown
Additional details
Additional titles
- Original title (Russian)
- Методика определения радиационной нагрузки корпуса реактора VVEhR-1000
Publishing Information
- Journal Title
- Yadernaya i Radiatsionnaya Bezopasnost'
- Journal Volume
- 3
- Journal Issue
- 3
- Journal Page Range
- p. 32-40
- ISSN
- 1608-2214
INIS
- Country of Publication
- Ukraine
- Country of Input or Organization
- Ukraine
- INIS RN
- 33004363
- Subject category
- S99: GENERAL AND MISCELLANEOUS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Is Lead record
- Yes
- Descriptors DEI
- COMPUTERIZED SIMULATION; D CODES; FAST NEUTRONS; FUEL CYCLE; MATERIALS TESTING; MONTE CARLO METHOD; NEUTRON FLUENCE; NEUTRON FLUX; NEUTRON TRANSPORT; PROGRAMMING; REACTOR VESSELS; WWER-5 REACTOR
- Descriptors DEC
- BARYONS; CALCULATION METHODS; COMPUTER CODES; CONTAINERS; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; FERMIONS; HADRONS; NEUTRAL-PARTICLE TRANSPORT; NEUTRONS; NUCLEONS; POWER REACTORS; PWR TYPE REACTORS; RADIATION FLUX; RADIATION TRANSPORT; REACTORS; SIMULATION; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS