Activities of design studies on innovative small and medium LWRs in JAERI

Iwamura, Takamichi; Ochiai, Masaaki

Proceedings of 1st Asian Specialist Meeting of Future Small-Sized LWR Development, p.7_1 - 7_9, 2001/00

JAERI has developed two types of small and medium size Light Water Reactors to meet the goals of innovative nuclear reactors such as sustainability and diversification of energy utilization. One is the Reduced-Moderation light Water Reactor (RMWR) with passive safety features. The reactor core consists of MOX fuel assemblies with tight lattice arrangement to increase the conversion ratio by reducing the moderation of neutron energy. The core design of 330MWe output with the operational cycle of 26 months was accomplished. A breeding ratio of 1.01, negative void coefficient and natural circulation cooling of the core were realized under the discharged burn-up of 60GWd/t. The other is the Passive Safe small Reactor for Distributed energy systems (PSRD) to diversify the nuclear energy utilization. An innovative advanced marine reactor (MRX) is used to supply the small grid electricity or electricity and heat co-supply by installing it on a barge. A small integral LWR for underground deployment is also studied for exclusive use of heat supply to household or office.

The Role of nuclear energy in future energy systems of Japan

Sato, Osamu; *;

Proc. of Int. Conf. on Future Nuclear Systems (Global'97), 2, p.963 - 968, 1997/00

no abstracts in English

None

Ishido, Akio; ; *;

PNC TN7440 96-002, 86 Pages, 1996/02

PNC-TN7440-96-002.pdf:2.26MB

None

None

PNC TN1311 95-002, 16 Pages, 1995/03

no abstracts in English

Effects of energy demand and fuel prices on carbon dioxide emission reduction

*; Sato, Osamu;

Kagaku Kogaku Rombunshu, 20(6), p.902 - 911, 1994/00

https://doi.org/10.1252/kakoronbunshu.20.902

no abstracts in English

None

; ;

PNC TN9410 91-143, 69 Pages, 1991/05

PNC-TN9410-91-143.pdf:4.07MB

None

Evaluation of Symbiotic Energy System between Gas-Cooled Fast Reactor and Multi-Purpose Very High Temperature Reactor (I) - An Investigation of GCFR Core Concept -

; ; *; *; *; *

JAERI-M 9544, 174 Pages, 1981/07

JAERI-M-9544.pdf:4.77MB

no abstracts in English

Atomic power and heavy water

Kagaku Kogyo, 27(6), p.652 - 656, 1976/06

https://ci.nii.ac.jp/naid/40000412420

no abstracts in English